annual report 2008 - ciematdocument sc-ciem01(08)4.1.periodic report. annual report 2008 ....

Document SC-CIEM01(08)4.1.Periodic Report

ANNUAL REPORT 2008

Asociación EURATOM-CIEMAT para Fusión

i Association EURATOM-CIEMAT. Annual Report 2008

INDEX:

INTRODUCTION .............................................................................1

I. Provision of support to the advancement of the ITER physics basis ..........................................................................................3

I.1. Development of candidate operating scenarios ............................ 3 I.1.1. High Te pedestal studies at JET...................................................... 3

I.2. Energy and particle confinement/transport ................................. 3 I.2.1. Momentum transport and shear flow physics ................................... 3 I.2.2. Parallel mass flow and Reynolds stress during externally biased shots .4 I.2.3. Investigation of zonal flow physics during the transition to improved

confinement regimes.................................................................... 5

I.3. MHD stability and plasma control .............................................. 5 I.3.1. ELM dynamics on the low and high field side of the plasma................ 5 I.3.2. Fast Visible imaging of ELM Wall interactions on JET ......................... 6 I.3.3. Inductive Current profile control during ramp up and ramp down

phases ....................................................................................... 6

I.4. Power and particle exhaust, plasma-wall interaction..................... 8 I.4.1. Studies of detritiation methods for ITER.......................................... 8

I.4.1.1. Efficiency of cleaning techniques in gaps (GAPOX, EFDA Technology Task)........................................................................................................... 8

I.4.1.2. Mechanism of film inhibition by nitrogen injection. Collaboration with PSI-2 Berlin................................................................................................ 8

I.4.2. Experimental validation of carbon transport models .......................... 9 I.4.2.1. Injection of hydrocarbons molecular beams of in TJ-II. Collaboration

KFA............................................................................................................ 9 I.4.3. Erosion of metal carbide doped graphhites ...................................... 9

I.5. Physics of plasma heating and current drive................................ 9 I.5.1. Analysis of the discrepancy between electron temperature

measurements in high temperature plasmas in JET......................... 10

I.6. Theory and modelling for ITER ................................................ 10 I.6.1. Implementation of ERO code with inclusion of Nitrogen injection ...... 10 I.6.2. Study of plasma formation within the electrostatic residual ion dump

proposed for the HNB injectors of ITER ......................................... 11

II. Development of plasma auxiliary systems...............................11

II.1. Heating and current drive systems .......................................... 11

ii Association EURATOM-CIEMAT. Annual Report 2008

II.1.1. NBI Heating studies (TJ-II) ......................................................... 11 II.1.2. EBW Heating studies (TJ-II) ........................................................ 13

II.1.2.1. High voltage modulator............................................................................ 13

II.2. Plasma diagnostics ................................................................ 14 II.2.1. Development of plasma diagnostics in TJ-II stellarator .................... 14

II.2.1.1. Reflectometry ........................................................................................... 14 II.2.1.2. Interferometry........................................................................................... 14 II.2.1.3. Thomson Scattering.................................................................................. 15 II.2.1.4. First measurements of EBW emission at 28 GHz.................................... 15 II.2.1.5. Diagnostic Neutral Beam Injector (NBI) and VUV studies..................... 16 II.2.1.6. Turbulence and plasma potential evolution by HIBP diagnostic in the TJ-

II stellarator .............................................................................................. 16 II.2.1.7. Development of a new Ti edge diagnostic ............................................... 17 II.2.1.8. Experimental system for spectral line ratio measurements in the TJ-II

stellarator.................................................................................................. 17 II.2.1.9. Development of a flexible luminescent probe to monitor fast ion losses at

the edge of the TJ-II stellarator ................................................................ 17 II.2.1.10. Characterization of phosphors.................................................................. 18 II.2.1.11. CX-NPA studies....................................................................................... 18

II.2.2. Development of plasma diagnostics in W7X ................................... 19 II.2.2.1. Interferometry........................................................................................... 19

II.2.3. Diagnostic exploitation and development in JET ............................. 19 II.2.3.1. Tools to analyse JET data......................................................................... 19 II.2.3.2. FC7-Project .............................................................................................. 19

II.2.4. Reflectometry simulations........................................................... 20 II.2.5. Diagnostic development in ITER................................................... 20

II.2.5.1. Plasma Position Reflectometer................................................................. 20 II.2.5.2. Development of Equatorial Visible/InfraRed Wide Angle Viewing

System ...................................................................................................... 21 II.2.5.3. Thomson Scattering.................................................................................. 22 II.2.5.4. Magnetic sensors. Cluster CEA /CRPP /CIEMAT /IPP-CR / TEKES.... 22

II.3. Plasma fueling ...................................................................... 23 II.3.1. Fuelling studies in TJ-II .............................................................. 23

II.4. Real Time Measurement and Control........................................ 23 II.4.1. Techniques for data storage and retrieval (ITER)............................ 23 II.4.2. Data mining techniques (pattern recognition) ................................ 24 II.4.3. Development of TJ-II operation scenarios for dynamic control of

magnetic configuration ............................................................... 24

II.5. Mechanical Engineering.......................................................... 25 II.5.1. ITER Diagnostic Equatorial Port Plug (EPP) Engineering and Integration

: EPP Hydraulic Analysis. BSM Attachment. UPP Kinematics Study .... 25 II.5.2. Ultrasonic Examination of the Divertor mock-ups manufactured with

calibrated defects ...................................................................... 26

iii Association EURATOM-CIEMAT. Annual Report 2008

II.5.3. Neutral Beam Remote Maintenance System Design ........................ 27 II.5.4. Magnetic system design for the ITER MRID (Magnetic Residual Ion

Dump) ..................................................................................... 28

III. Development of concept improvements and advances in fundamental understanding of fusion plasmas ........................28

III.1. Optimization of operational regimes for improved concepts ......... 28 III.1.1. Influence of magnetic configuration in the development of Transport

Barriers.................................................................................... 28 III.1.2. International stellarator confinement and profile database and

neoclassical transport................................................................. 29 III.1.2.1. Participation in the on-going activities of the International Stellarator

Confinement and Profile Data Bases during 2008................................... 29 III.1.2.2. Use of Global Monte Carlo codes to estimate collisional transport

properties: Explore the properties of a flux expansion divertor............... 29 III.1.2.3. Continue the benchmark of Neoclassical Transport codes. ..................... 30 III.1.2.4. Activities of the International Collaboration on Neoclassical Transport in

Stellarators................................................................................................ 30 III.1.2.5. The role of Global Neoclassical Transport in Stellarators. ...................... 31

III.1.3. Full lithium coating in TJ-II.......................................................... 31

III.2. Understanding of plasmas characteristics for improved concepts.. 32 III.2.1. Momentum transport.................................................................. 32

III.2.1.1. Multi-scale physics mechanisms and spontaneous transport bifurcations in fusion plasmas .......................................................................................... 32

III.2.1.2. Visualization of plasma flows and blob dynamics with wide angle view by means of fast intensified cameras........................................................ 32

III.2.1.3. Visualization of plasma flows in the LHD stellarator.............................. 33 III.2.1.4. Influence of electric fields on supra-thermal electrons: role of dynamic

biasing ...................................................................................................... 33 III.2.1.5. Confinement transitions and bicoherence ................................................ 34

III.2.2. Current drive physics. ECCD experiments: comparison TJ-II vs. Heliotron-J................................................................................ 34

III.3. Other experimental activities .................................................. 35 III.3.1. Remote participation .................................................................. 35

III.4. Theory and modelling ............................................................ 35 III.4.1. Modelling of kinetic effects on transport ........................................ 35

III.4.1.1. Kinetic Transport...................................................................................... 35 III.4.1.2. Electron heating and Kinetic Transport ................................................... 36 III.4.1.3. Kinetic Simulation of Heating and Collisional Transport in a 3D Tokamak

.................................................................................................................. 36 III.4.2. Divertor stellarator physics: Investigation on the feasibility of the flux

expanded divertor concept for TJ-II.............................................. 36 III.4.3. Statistical Description of Transport ............................................... 37

III.4.3.1. Topological characterization of flows in plasma turbulence ................... 37

iv Association EURATOM-CIEMAT. Annual Report 2008

III.4.3.2. Numerical evidence of fractional poloidal transport................................ 37 III.4.3.3. Mathematical aspects of fractional stochastic processes.......................... 37 III.4.3.4. Probabilistic and test particle transport .................................................... 38 III.4.3.5. Transport and stiffness ............................................................................. 38

III.4.4. Theoretical EBW studies in TJ-II................................................... 38 III.4.4.1. Ray Tracing and Full wave calculations of the O-X-B conversion process

in the TJ-II stellarator............................................................................... 39 III.4.4.2. Linear estimation of EBW Current Drive ................................................ 39 III.4.4.3. Link between particle transport and heating, using TRUBA and ASTRA

codes......................................................................................................... 40 III.4.5. Eirene code studies.................................................................... 40

III.4.5.1. Spatially resolved H�-emission simulation with EIRENE in TJ-II to study hydrogen atomic and molecular physics in low density, high temperature fusion edge plasmas ................................................................................. 40

III.4.6. Computation developments: Grid and Computing and HPC for fusion 41 III.4.6.1. Participation in EUFORIA Project........................................................... 41 III.4.6.2. Introduction of a simple 3D Geometry in TORB code that runs in HPC:

EUTERPE ................................................................................................ 41 III.4.6.3. Porting of VMEC, FAFNER and DKES to the Grid ............................... 41 III.4.6.4. Exploitation of global Monte Carlo codes in the Grid ............................. 42 III.4.6.5. Computation developments: Volunteer Computing for fusion (using

BOINC). Preliminary Simulations of ITER in a Citizen Computer ........ 42 III.4.6.6. Equilibrium reconstruction, equilibrium criticality and ELM theory at

JET. .......................................................................................................... 43 III.4.7. Simulation of the ERID of the ITER NBI system.............................. 43

III.5. Development of the stellarator concept .................................... 44 III.5.1. Optimization of stellarator configurations ...................................... 44

III.6. TJ-II Engineering and Operation.............................................. 44 III.6.1. Basic Machine Engineering .......................................................... 44

III.6.1.1. Introduction .............................................................................................. 44 III.6.1.2. Technical operation of the TJ-II............................................................... 45 III.6.1.3. Maintenance tasks .................................................................................... 45 III.6.1.4. Power supply ............................................................................................ 46 III.6.1.5. Control system.......................................................................................... 46

III.6.2. Operation of TJ-II ...................................................................... 48 III.6.2.1. ECRH system routine operation and improvements ................................ 49 III.6.2.2. Activities on Electronics for TJ-II diagnostics......................................... 52 III.6.2.3. Development of a new event-oriented database....................................... 53

IV. Emerging technologies ............................................................53

IV.1. Development of material science and advanced materials for DEMO.......................................................................................... 53

IV.1.1. Physics integration (Ceramic insulators): Study of radiation induced electrical currents for hydrogen isotopes and helium at low residual pressure and effect on insulating surfaces. .................................... 53

v Association EURATOM-CIEMAT. Annual Report 2008

IV.1.1.1. Evaluation of behaviour of silica glasses ................................................. 53 IV.1.2. Physics integration (Ceramic insulators): To characterize and assess

the behaviour of insulating materials and components during irradiation for applications in H&CD, and diagnostics...................................... 54

IV.1.2.1. Evaluation of new types of glasses (Na based) ........................................ 54 IV.1.2.2. Characterization of gamma irradiated silica (optical absorption and

photoluminescence).................................................................................. 54 IV.1.2.3. Radiation bolometer development ........................................................... 56 IV.1.2.4. Mirrors characterization ........................................................................... 56 IV.1.2.5. Window assemblies and seals, radiation enhanced T diffusion ............... 57

IV.1.3. Long term structural materials: For experimental ODS steels evaluate the fabrication route, specially heat treatments after consolidation, in the metallurgical properties of this steel as possible structural material for fusion devices ...................................................................... 57

IV.1.3.1. Feasibility studies for the production of nanostructured ODS steels ....... 58 IV.1.4. Long term structural materials: To work on mechanical and

microstructural characterization of Eurofer ODS steels .................... 58 IV.1.5. Long term structural materials: For experimental W alloys evaluate the

fabrication route in the metallurgical properties of this steel as possible structural material for fusion devices ............................................ 59

IV.1.5.1. Feasibility study for the production of W alloys with reduced oxidation properties.................................................................................................. 59

IV.1.5.2. Feasibility study for the production of nanostructured W........................ 59 IV.1.6. Long term structural materials: To work on mechanical and

microstructural characterization of W alloys.................................. 60 IV.1.6.1. Microstructural characterization of the produced W alloys ..................... 60

IV.1.7. Characterization of SiC materials for DEMO ................................... 61 IV.1.7.1. Measurement of electrical properties ....................................................... 61

IV.2. Materials modelling ............................................................... 61 IV.2.1. Long term structural materials: Modelling, continue to support this

activity for steels (Fe), insulators and SiC ..................................... 62 IV.2.2. Experiments for modelling validation: He desorption in Fe and other

model materials ........................................................................ 62 IV.2.2.1. Feasibility study to make desorption measurements................................ 62

IV.3. Techniques for controlling tritium inventory, fuel cycle ............... 63 IV.3.1. Tritium Breeding and materials (breeding blanket): To demonstrate and

visualize by a well founded ab-initio simulation of the He/Li system, the tendency of He atoms in Li to cluster into bubbles..................... 63

IV.4. Fusion safety issues .............................................................. 66 IV.4.1. Database of failure of fusion machine components for probabilistic

safety analysis .......................................................................... 66 IV.4.1.1. Definition of the database structure ......................................................... 66

IV.5. Operation of essential technological facilities according to the needs of the programme ................................................................. 67

IV.5.1. Irradiation sources..................................................................... 67

vi Association EURATOM-CIEMAT. Annual Report 2008

IV.5.1.1. Operation of the van de Graaf accelerator ............................................... 67 IV.5.1.2. Operation of the “Nayade” irradiation facility......................................... 67 IV.5.1.3. Development of an irradiation line at the CMAM ion accelerator .......... 67

IV.5.2. Liquid metal loops...................................................................... 68 IV.5.2.1. Feasibility studies of Li liquid metal loops for Li .................................... 68 IV.5.2.2. Feasibility of a coupled He/lead-lithium loop.......................................... 68

IV.6. Remote handling................................................................... 69 IV.6.1.1. Vessel in-Vessel: To support the Radiation Tolerance Assessment of RH

Components in particular for hydraulic systems...................................... 69 IV.6.1.2. RH on diagnostics port plugs ................................................................... 69 IV.6.1.3. Definition of needs for a general purpose TH test facility for diagnostic

port plugs and TBMs................................................................................ 70 IV.6.2. IFMIF....................................................................................... 71

IV.6.2.1. Test bed RH, definition of needs.............................................................. 71

V. Training and career development ............................................71

V.1. Training activities.................................................................. 71

VI. Other activities in magnetic confinement fusion......................72

VI.1. Public Information................................................................. 72 VI.1.1. Outreach activities in collaboration with the European Public

Information Group ..................................................................... 72 VI.1.2. Computation developments: Volunteer Computing for fusion (using

BOINC). Development of a Citizen supercomputer in Spain.............. 72

VI.2. Technology transfer............................................................... 73

VI.3. Socioeconomics .................................................................... 73 VI.3.1. External costs of energy sources. Validation of the EFDA Times model ,

task WP08-SER-ETM FDA Times Model.......................................... 73 VI.3.2. Social Perception of Fusion research............................................. 74

VI.3.2.1. Social Perception of Large R&D Programmes (TW5-TRE-FESS/C) ..... 74 VI.3.2.2. Investigating lay understanding and reasoning about fusion technology by

means of a group-based methodology suitable to take lay participants through a learning process about fusion (TW6-TRE-FESS-B1). ............ 74

VI.3.2.3. Towards a participative dialogue with society about the risks associated with fusion energy (WP08-SER-AWF. Activity 1) ................................. 75

VI.4. Activities related to the Broader approach ................................ 75 VI.4.1. IFMIF/EVEDA Project.................................................................. 75

VI.4.1.1. Accelerator Facilities: RF system ............................................................ 75 VI.4.1.2. Accelerator Facilities: Beam Dump & HEBT.......................................... 77 VI.4.1.3. Accelerator Facilities: Diagnostics........................................................... 77 VI.4.1.4. Accelerator Facilities: DTL & MS........................................................... 79 VI.4.1.5. Accelerator Facilities: Radioprotection.................................................... 80

vii Association EURATOM-CIEMAT. Annual Report 2008

viii Association EURATOM-CIEMAT. Annual Report 2008

VI.4.1.6. Test and Target activities: RH Engineering ............................................. 82 VI.4.1.7. Test and Target activities: Medium Flux modules engineering.............. 83 VI.4.1.8. Test and Target activities: Microfission chamber validation activities.... 85 VI.4.1.9. Design Integration: Safety........................................................................ 86 VI.4.1.10. Design Integration: RAM Evaluation .................................................. 86

VI.4.2. JT-60 SA Cryostat...................................................................... 87 VI.4.2.1. Activities in the Broader Approach. The Cryostat for JT-60SA.............. 87

VI.4.3. DEMO R&D ............................................................................... 88 VI.4.3.1. SiC/SiC characterization .......................................................................... 88 VI.4.3.2. Insulator ceramics .................................................................................... 88

VI.5. Dual Coolant Breeder Blankets................................................ 89

VI.6. Fusion Technology Facilities.................................................... 90 VI.6.1. Technofusion ............................................................................ 90 VI.6.2. b-FUS ...................................................................................... 95

VII. Keep in Touch activities on Inertial Confinement Fusion .........96

VII.1. Scientific development........................................................... 96 VII.1.1. Radiation hydrodynamics and jet impact fast ignition ...................... 96

VII.1.1.1. Fast Ignition Targets................................................................................. 96 VII.1.1.2. Laser-Plasma Interaction.......................................................................... 97

VII.1.2. Atomic Physics .......................................................................... 97 VII.1.2.1. Spectroscopic diagnostics ........................................................................ 97 VII.1.2.2. Colisional-radiative calculations of plasmas............................................ 97 VII.1.2.3. Analytical opacity formulas ..................................................................... 98

VII.2. Materials for de IFE and MFE under irradiation........................... 98

INTRODUCTION

The present document is a report of the Association activities during 2008 following the

thematic distribution of the approved 2008 Work Programme.

This programme follows the standard pattern for all the associations and requires some

specific adaptations for stellarator activities:

• Chapter I deals with the enhancement of the physics basis for the next step: ITER.

Here we report basic physics obtained in TJ-II which are applicable to the main tokamak

line (momentum transport & turbulence), together with results obtained from

experiments at JET and other devices: equilibrium reconstruction with EFIT, ITB

formation, ELM propagation physics & plasma wall, or in technology devices: tritium

retention prevention and Tritium removal

• Chapter II is devoted to the development of auxiliary systems: diagnostics, heating &

CD, Control and DAC. Here we report developments both in TJ-II, JET and W7X, as

well as developments for ITER

• Chapter III is the main section dealing with stellarator physics. It also includes

general results from plasma theory.

Here we report TJ-II status and operation summary, operation highlights (Lithium

coating) and a number of physics research results on: electric fields, magnetic topology,

stellarator confinement scaling and momentum transport.

Theory activities include studies in TJ-II, JET and general plasma physics studies.

Finally we include in this chapter our activities on W7X engineering.

• Chapters IV describes activities in technology, either under EFDA specific contracts or

in preparation for expected activities

• Chapters V covers training and education activities.

1 Association EURATOM-CIEMAT. Annual Report 2008

• Chapter VI covers other activities like:, public information, socioeconomics, activities

under the Broader Approach, preparation activities towards the new fusion technology

centre “Technofusion” and a report on Inertial Fusion keep in touch activities.

• Chapters VII describes the work on Inertial Fusion keep in touch activities.

Finally, Annex I gives a list of publications & talks generated by the Association.



I. PROVISION OF SUPPORT TO THE

ADVANCEMENT OF THE ITER PHYSICS BASIS

I.1. Development of candidate operating scenarios

I.1.1. High Te pedestal studies at JET

High pedestal discharges have been achieved in JET. Electron temperatures of about 3

keV were obtained. Several experiments were performed in order to study the properties

of those plasmas. The characteristics of ELMS were studied in those conditions, having

studied and given an explanation for the vertical displacement of the strike points [ref

nf8_solano1]: The hypothesis is that in an ELM previously closed edge field lines would

open up, releasing plasma current and leading to the formation of a new, smaller

separatrix. It was observed that after each ELM strike points have shifted a few

centimetres towards the plasma centre (up in JET). In some cases a transient (<100 μs),

upwards large (>10 cm) jump of strike positions was observed first. It was followed by

an equally fast jump down to the shifted strike positions. Such behaviour is explained by

an X-point instability, due to positive toroidal current density at the X-point, and a

diamagnetic instability, due to negative inboard toroidal current density. Impurity seed

have been used to study the reaction of the pedestal and the behaviour of the ELMs [ref

nf8_solano2]. The evolution of the pedestal with the density for several impurities was

studied.

I.2. Energy and particle confinement/transport

I.2.1. Momentum transport and shear flow physics

In TJ-II plasmas, the perpendicular rotation velocity of the turbulence changes from

positive to negative, giving rise to the so called edge velocity shear layer, when the line-

averaged plasma density exceeds some critical value, this change being dominated by

the inversion in the radial electric field. The parameters that control the inversion in the

perpendicular rotation have been investigated and a parametric dependence of the

critical density has been obtained studying plasmas confined in different magnetic

configurations (different rotational transform and/or plasma volume) and heated with

different ECH power levels. The studied data set shows a positive exponential


dependence on heating power and a negative one on plasma radius, while the

dependence on rotational transform has low statistical meaning. Besides, analysis of local

plasma parameters points to plasma collisionality as the parameter that controls the

inversion of the perpendicular rotation velocity of the turbulence [ref Mom_1]

Measurements with a two-channel reflectometer have shown that the radial origin of the

edge shear layer is linked to the plasma region with maximum density gradient,

expanding towards the edge until the edge shear flow is fully developed. The process of

creation is directly coupled to the existence of a critical density gradient, which might be

consistent with neoclassical mechanisms. At this radial position the velocity shear layer

starts to form and then expands radially until the universal edge velocity shear layer is

fully developed. The disappearance of the edge velocity shear layer has been shown to

be a radial contraction, ending at the position of maximum density gradient, thus being

the exact contrary to the emergence of the shear. These results suggest a two-step

process in the edge shear formation: first, a seeding mechanism linked to plasma

gradients and, second, an amplification process in which shearing rates and fluctuations

are self-organized near marginal stability [ref Mom_2].

I.2.2. Parallel mass flow and Reynolds stress during

externally biased shots

Parallel mass flows were studied in externally biased shots. The applied radial electric

field was seen to change the parallel rotation profile and the coupling of parallel and

radial velocity fluctuations.

The variation of the parallel return flows expected from the compressibility of the

increased perpendicular flows (i.e., the so-called parallel Pfirsch-Schlutter flow) was

found to be in agreement with the observed changes only in positions inside the LCFS

but could not explain by itself the observed the rotation profiles in either regime (with or

without external biasing).The parallel Reynolds stress drive was found to be comparable

in magnitude to the frictional slow-down measured in relaxation experiments and

suggests itself as a factor to consider in the study of parallel rotation dynamics. The

enhanced coherence of velocity fluctuations observed in the presence of externally

applied electric fields rendered the parallel Reynolds stress still substantial even in

situations of reduced turbulence levels (like that found in TJ-II’s biased shots or in

conventional H-modes). These results point out that the radial electric field can take an

active part in parallel dynamics acting as a radial-parallel symmetry breaking agent [ref

AlonsoEPL].


I.2.3. Investigation of zonal flow physics during the transition

to improved confinement regimes

Zonal flows have been suggested as an important ingredient to explain the Low to High

transition (L-H) in magnetic confinement devices. Due to the recent development of two

sets of Langmuir probes located at two different toroidal positions, TJ-II can be

considered a good laboratory to study the presence of zonal flows in the plasma edge

region. Moreover, it has been reported that TJ-II sheared flows can be easily driven and

damped at the plasma edge by changing the plasma density or during biasing

experiments.

Experiments carried out in Electron Cyclotron Resonance Heated TJ-II plasmas have

shown the emergence of a mean shear flow (for plasma densities around n ≈ 0.6 x 1019

m-3), smoothly reducing the fluctuations and promoting the development of fluctuating

long-range correlations in plasma potencial but not in density fluctuations. TJ-II findings

are consistent with the theoretical framework provided by transition models predicting

second order phase transitions triggered by zonal flows [ref PedrosaPRL].

I.3. MHD stability and plasma control

I.3.1. ELM dynamics on the low and high field side of the

plasma

In JET the ECE radiometer is designed to collect the emission in O- and X- polarization

(first and second harmonic respectively) with the antenna located in the low field (LFS)

side of the plasma. The possibility of measuring O-mode radiation (not affected by

harmonic overlap on the plasma HFS) enables to measure inboard and outboard electron

temperature pedestal measurements simultaneously, which is particularly relevant to

investigate ELM dynamics. The work on improving the calibration of the data collected

from the inboard side of the plasma (O-mode) has continued this year. Extensive

simulations of the ECE spectra have been carried out using the emission code SPECE. The

new calibration technique consists on using the simulated spectra for each specific shot

on the line of sigh of the ECE radiometer. In general, good agreement between the

inboard and outboard temperature profiles has been found after increasing the magnetic

field by a factor of ~1% and correcting the effect of refraction for high density cases.

This correction is also consistent with the radial shift that is observed when comparing

the temperature profile measured by ECE with the one measured by the High Resolution


Thomson Scattering (HRTS). A systematic study of this disagreement has revealed that

the most plausible source of error is an error on the vacuum magnetic field that it used

as an input by the equilibrium reconstruction code (EFIT) (ref LBarrera08).

I.3.2.

I.3.3.

Fast Visible imaging of ELM Wall interactions on JET

First fast camera measurements of large ELM events on JET were presented. We reported

on the observation of clear, field aligned plasma filaments visible on the images as

aligned bright spots on the outer limiters and upper dump plate. The interaction with the

later is remarkable not only in the high triangularity case studied but also in some large

ELM instances in low triangularity configurations where it is observed shortly after or

together with the first filament impacts on the outer limiters. Estimates of the radial

(200—1000m/s) and toroidal (~ 5000m/s) velocities could be obtained for particular

cases under reasonable assumptions. The observation of compound ELM aftershocks also

revealed filamentary structures. In high triangularity configurations the high fluxes on

the upper dump plate are seen to cause the desorbtion of neutral gas seen as a highly

radiating MARFE-like cloud that is dragged along the field line around the central column

until the inner divertor region. The release of macroscopic particles from a limiter was

captured 6ms after an ELM impact. The apparent velocities of the particles were

estimated in few hundred meters per second.

Inductive Current profile control during ramp up and

ramp down phases

As the new generation of nuclear fusion reactors arrives, several issues related to the

inductive start-up and termination of tokamak discharges have been identified. The most

basic one is related to the need of extending the discharge as much as possible with

limited amount of flux in the transformer primary circuit. The second one is related to

plasma ramp-down phase vertical position controllability issues at high values of plasma

inductance. Plasma inductance control is a basic control that helps in these key areas.

The objective of this collaboration was to develop and test a plasma inductance control

system for JET based on existing systems at JET, namely the Real Time Power Control

System and the Boundary flux control system.

The following milestones have been achieved:

1) Initial feasibility.

Simulation of inductance control using a transport code to show that inductance control

during the ramp-up phase can improve the reproducibility of advanced tokamak

scenarios

2) State space model development

A state space lumped parameter model that approximates the distributed parameter

equations governing flux diffusion dynamics has been derived.

This model describes the time evolution of the plasma current and inductance in terms of

the actuator inputs and disturbances, using a linearization of the flux diffusion dynamics

together with energy conservation and power balance equations. The validity of this

model has been checked against actual data from JET and the agreement is outstanding.

3) Control system design

Using feedback linearization techniques, the state space model is then used to design a

control system, and its performance has been demonstrated with simulations.

4) Control system implementation

The control system has been implemented in the RTPC and real time demand and control

signals made available to the flux control system. A number of JET shots have been used

to debug and commission the implementation.

5) Control system testing using boundary flux.

The initial scenarios for inductance control with boundary flux were chosen as high

triangularity plasmas with gradually increasing shaping during the ramp-up phase of the

discharge. The tests could not be concluded due to soft stops triggered by the coil

protection system as the main transformer coil current reference was exceeding by more

than 3kA the actual coil current. This was due to additional transformer action induced

by shaping coils interfering with boundary flux control.

6) Control system testing using neutral beam injection.

These tests were performed using NBI power as heating / current drive actuator. Control

of inductance was demonstrated in the current ramp up phase with different level of

efficiency.

7) Dissemination of results

The description of this work has been accepted at the European Physics conference that

will take place in Sofia, Bulgaria in June 2009 (Induc_1). Partial reporting has taken

place at the S2 taskforce meetings.



I.4. Power and particle exhaust, plasma-wall

interaction

I.4.1. Studies of detritiation methods for ITER

I.4.1.1. Efficiency of cleaning techniques in gaps (GAPOX, EFDA

Technology Task)

A possible concept for tritium inventory control in ITER and beyond is the removal of co-

deposits by chemical techniques. Either thermo-oxidation in pure oxygen gas or plasma

assisted removal by He/O2 cleaning plasmas have been previously proposed. The

presence of beryllium in the first wall of ITER, however, makes oxidation problematic and

time consuming. Our group has made two main contributions in the field by during the

last year. First, nitrogen or ammonia containing plasmas are as efficient as oxygen ones

for carbon removal, without the side effects of Be oxidation. In particular, it has been

shown that H2/NH3 plasma mixtures are at least as efficient as He/O2 plasmas for the

removal (Ferr_1). Secondly, the use of NO2 as oxidizing agent instead of pure O2 (a

research project coordinated with the IEM Miguel Catalán, CSIC) makes it possible to

perform the task at significantly lower temperatures, thus relieving the constrains for its

application to ITER. The efficiency of the technique for co-deposit removal from sub-

millimetric gaps (widely present in the actual design of ITER) was experimentally verified

(Tana_1).

Work on this topic constitutes the main body of the PhD Thesis presented by Dr J.

Ferreira in June 2008

I.4.1.2. Mechanism of film inhibition by nitrogen injection. Collaboration

with PSI-2 Berlin.

In 2004, the nitrogen scavenger experiment, aimed at the full inhibition of carbon-T re-

deposits in ITER, was performed in the Asdex Upgarde Tokamak, and a reduction of 80%

in the deposited carbon in the divertor region was observed upon nitrogen injection. Even

better results were recently obtained in the PSI-2 linear plasma device, at the Humboldt

University in Berlin (PSI2_1). Experiments at JET, Textor, MAST and Pilot PSI are

presently underway (Scav-1). In 2008, the required set-up for the Pilot experiment, with

nitrogen and ammonia injection at several locations respect to the plasma, was

implemented at FOM (Pilot-1). The goal of these experiments is to demonstrate that film

inhibition by scavenger injection can be made without perturbing the ionic composition of

the divertor plasma.


On the other hand the fate of the initial products from the scavenger reaction, when

transported through the pumping duct in ITER, has been investigated at CIEMAT. It was

shown that important conversion of the plasma born products takes place in the duct,

strongly dependent on the pre-existing degree of carbon coverage (PSST_1 and

ESCAMPIG-1)

[Scav-1]: F.L. Tabarés. Use of of scavenger gases for C layer inhibition: latest results 10th ITPA Meeting on

SOL/divertor physics. Avila. 07-10 January 2008

[Pilot-1]: J.A. Ferreira et al. ICPM 09, Bochum July 2009

[ESCAMPIG-1]: F.L. Tabarés et al.. Characterization of minority species in reactive plasmas by CTAMS.

Granada July 2008

I.4.2. Experimental validation of carbon transport models

I.4.2.1. Injection of hydrocarbons molecular beams of in TJ-II.

Collaboration KFA.

As mentioned above, the origin of the tritium retention problem lies on the strong

chemical erosion of carbon materials in the presence of low temperature, high-density

plasmas of hydrogen isotopes. This topic has independently been addressed in TJ-II. For

that purpose, hydrocarbons (methane and ethylene) were injected in the plasma through

a mobile limiter, and the response of spectroscopic signatures of their break-up as well

as the confinement of the generated so-generated C ions was followed. The erosion

characteristics of the layers created by the injection were investigated. In 2008, a

molecular beam of hydrocarbons was injected in the plasma edge (both H and He

plasmas) and the spatial profile of the cracking fragments (CH and H) were followed by

spectroscopy. The high spatial resolution provided by this technique has allowed the

direct study of the kinetics of hydrocarbon decomposition into the plasma, and a simple

model was developed to account for the observations (Taba_1).

I.4.3. Erosion of metal carbide doped graphhites

This task was not addressed in the 2008 campaign, partially due to the incompatibility of

carbon insertion in the plasma under full Li coated walls.

I.5. Physics of plasma heating and current drive


I.5.1.

I.6.1.

Analysis of the discrepancy between electron

temperature measurements in high temperature

plasmas in JET

The long standing disagreement between the central electron temperature measured by

Thomson scattering and electron cyclotron emission (second harmonic, X-mode) in high

performance plasmas observed in JET and TFTR has been reexamined in 2008. For this

purpose a database containing 20 high performance discharges (Te> 5 keV) from the

period 2004-2006 with combined neutral beam (NBI) and ion cyclotron resonance

heating (ICRH) was compiled. These discharges were obtained in a similar experiment

that was carried out in 2004 and later in 2006 using so called hybrid scenario with

dominant electron heating. A first screening of the database revealed that, although the

plasma conditions and heating scenario were very similar in the 2004 and 2006

experiments, the properties of the ECE spectra in these two datasets were significantly

different. Basically for the 2006 dataset a good agreement is found between the Te

profiles measured by ECE and Thomson Scattering while for the 2004 dataset a clear

disagreement is observed in the central region (Te,ECE>Te,TS for r/a<0.25). The ECE

spectra in the later case can’t be reproduced using a Maxwellian distribution function.

One of the most revealing results in our study is obtained by examining the ECE spectra.

We have found that inconsistencies between the temperature derived from the second

and the third harmonic ECE seem to be a characteristic fingerprint of the discrepancy

mentioned above, with the third harmonic peak temperature in better agreement with

the Thomson scattering data than the one deduced from the second harmonic (for the

2004 dataset). These experimental observations are consistent with the assumption of a

non-Maxwellian bulk electron distribution function that develops whenever the power

absorbed by the electrons is sufficiently high.

I.6. Theory and modelling for ITER

Implementation of ERO code with inclusion of Nitrogen

injection

The stay of Dr F. Guzman in Jülich during 2008 was devoted to this task. A

complementary atomic and molecular data basis of electron-nitrogen impact processes

has been launched for the understanding of the scavenger effect, in cooperation with the

ERO code Team. It could be used for designing T retention inhibition techniques for ITER.


I.6.2. Study of plasma formation within the electrostatic

residual ion dump proposed for the HNB injectors of

ITER

EFDA Task Reference: TW6-THHN-NBD1 (EFDA CONTRACT: FU06-CT-2006-00142 (EFDA

/06-1503)

The task started late in 2007 and carried on during the first semester of 2008.

The Final Report and all the related documents were sent to F4E in September 2008

The Final report has CIEMAT Classification code IN-IT-NBRID-001

The work was presented as a poster at the 25th Symposium on Fusion Technology in

Rostok, Germany, in September 2008 (ERID_1). The work has been published as a paper

in Nuclear Fusion (ERID_2).

II. DEVELOPMENT OF PLASMA AUXILIARY

SYSTEMS

II.1. Heating and current drive systems

II.1.1. NBI Heating studies (TJ-II)

In May 2008 the Injector #2 was put into operation. For the rest of the 2008

experimental campaign both injectors have been operative.

• Injector #2: Power Supplies and Protection System Commissioning

The goal was to achieve reliable operation of the injector.

First beams had been obtained in 2007 but reliability was poor due mainly to problems in

the High Voltage Power Supplies and the associated Protection Systems. Extensive

debugging of the system was undertaken, leading to the following actions:

a) The Crowbar electronics was revised, the grounding was improved. The unwanted

tripping of the High Voltage Switches during breakdowns diminished as a result of these

actions.

b) The Auxiliary tetrodes controlling the Bias voltage of the Main tetrodes were revised:

the connections were improved and a faulty socket was replaced. The spurious Switching

of the High Voltage Tetrodes disappeared.

c) The Decel Power supply was noisy and caused the tripping of the main High Voltage

Switches during breakdowns. Extensive revision of the Decel Supply circuits was carried

out. A temporary solution was found by adding an extermal impedance to the regulator

section of the supply.

d) The Grounding connections of the High Voltage room and the Control room were

revised. The spurious effects of the high Voltage breakdowns on the protection

electronics and the Data Aquisition System were greatly diminished.

e) New and faster electronics (home made) for the overcurrent and overvoltage

protection of the Accel and Decel Supplies were installed.

f) New and faster electronics (home made)for the overcurrent and overvoltage protection

of the Arc Supply was installed.

g) Two transformers of the High Voltage Deck had to be replaced or partially rebuilt.

After these improvements were implemented, Beam Conditioning could finally be

undertaken.

• Injector #2: Beam Conditioning

After an approximate number of 900 pulses performed along 5 days of operation, the

beam parameters were 30 kV, 50 A in the Ion Source

• Injector #2: Beam Injection

The first beam was injected into TJ-II on the 22nd of May. Beam parameters were 28 kV,

350 kW Port-Through power.

Along the 2008 experimental campaign, the parameters were gradually increased to 31

kV, 450 kW.

• Injector #1: Beam Conditioning

From the first conditioning period in February, Arcs are frequently unstable and the Gas

input must be often revised. The Arc power must be brought down in such cases. The

injected power varied from 400 to 450 kW, and the beam energy was around 30 kV. One

filament broken caused considerable contamination in the cathode chamber. In the

summer pause the filament flange was replaced and the ceramic insulator of the

piezoelectric valve was also changed. Subsequent conditioning was even more difficult,

the Arcs were very unstable. The maximum pulse length is 100 ms, and the Port-Through

power cannot be increased over 400 kW.



On the other hand, attempts to increase the beam energy failed due to an anomalous

“softness” of the High Voltage power Supplies.

• Injector #1: Beam Injection

Beams were regularly injected into TJ-II despite the difficulties with the Ion Source and

High Voltage power Supplies. Between 20 and 30 good beam pulses per day were usually

injected. The most usual beam parameters were 30 kV energy, 400 kW power.

• NBI System upgrades

The Secondary vacuum system was refurbished. The main action was the replacement of

the turbomolecular pumps and their isolation valves for the two injectors.

The Switching system of the High Voltage Power Supplies was thoroughly revised during

the summer pause. Some of the auxiliary power supplies were found to be causing

problems and were subsequently replaced. The Bias and Screen voltages were carefully

adjusted so as to minimize the voltage drop across the tetrodes. In this way, the Voltage

drop (Plate Voltage) was cut down by 4 kV in average. This improvement will allow to

increase the Accel Grid voltage in the future over their present value of 30 kV.

II.1.2. EBW Heating studies (TJ-II)

A 28 GHz electron Bernstein wave heating system is being installed in TJ-II. After many

problems related with the high voltage power supply, that finally could not be solved, a

high voltage cable was installed to connect the EBW gyrotron to the new HVPS of the

53.2 GHz system. Unfortunately, although the initial results obtained in September 2007

were promising, the old 300 kW, 28 GHz, 100 ms diode gyrotron that was to be used for

the EBW system could not be put into operation. After many attempts during the first

semester of 2008, further conditioning of the tube was not succesful and no power

generation could be obtained beyond pulses of a few milliseconds (5 ms at -58 kV). In

September 2008 it was decided to start the procedures for the purchase of a new 28 GHz

diode gyrotron. The new gyrotron will be provided by GYCOM and its installation is

expected before the end of 2009.

II.1.2.1. High voltage modulator

During 2008, the loan and improvement of a high voltage modulator based on an Eimac-

Y676A vacuum electron tube, previously used in IPP Garching, was conducted. The tube

was loaned by IPP to CIEMAT. The improvements and the later laboratory tests were

performed by IPF specialists. The equipment, which will be delivered at the beginning of

2009 consist of three parts:


• -The high voltage modulator.

• -The power supply for heating the gyrotron cathode.

• -A new module with a crowbar system for protection that uses a thyratron type gas

valve.

The laboratory tests performed in December 2008 have shown modulation capabilities up

to 10 kHz for 65/68 kV. At 70 kV supplied by the HVPS, a maximum operating voltage at

the gyrotron of 68 kV was demonstrated, which means only a 2 kV voltage drop in the

tetrode. The whole EBW system, except the new gyrotron, is now prepared.

This work has been carried out in the frame of the collaboration with IPP-Garching and

IPF-Stuttgart.

II.2. Plasma diagnostics

II.2.1. Development of plasma diagnostics in TJ-II stellarator

II.2.1.1. Reflectometry

To allow for Doppler measurements, a new antenna system has been designed to replace

that of the conventional reflectometer of TJ-II. To guarantee a good spectral resolution of

the measurements, gaussian microwave beams with well-defined beam waist radii near

the cut-off layer in the plasma are required. However, a high quality Gaussian beam with

low cross spectral power requires a large corrugated antenna which does not satisfy the

space restrictions imposed by the vacuum vessel of TJ-II. Therefore, a mixture between

choked and corrugated antenna was designed and fabricated exclusively for the Doppler

reflectometer system by the Antenna Group of the Public University of Navarra, Spain. In

combination with the antenna a steerable ellipsoidal mirror allows to focus the beam with

a constant phase and defined beam waist at the cut-off layer and to control the launch

angle of the microwave beam to obtain angles between ±10º enabling the measurement

of perpendicular wave-numbers in the range 3 to 15 cm−1. The new antenna system was

installed into the TJ-II vacuum vessel at the end of 2008 and a successful and reliable

operation has been demonstrated.

II.2.1.2. Interferometry

Development of an online processing procedure using FPGA technology for phase

measurements. Implementation and test of the three-channel interferometer.

A MIMO system including a Virtex IV FPGA and 16 input 14 bits channels from Lyrtech

has been installed. The algorithm previously used has been rebuilt for on line processing,

and is being optimized and improved in cooperation with the Electronics Department of

the Polytechnic University of Madrid. The simulations have worked properly. The

hardware implementation works also with synthetized signals. We expect to make a real

density measurement in brief. The results will be compared with those of the present off

line procedure. The FPGA to memory data transfer protocol must also be improved.

Also a Digital to Analog converting stage has been developed and tested in order to give

a signal for the machine control. It works well and a interface signal protocol is being

studied. Part of this work has been presented for the doctoral student Luis Esteban

Hernandez to obtain the DEA certificate

The hardware for the three channels interferometer has been built and some alignments

done. Some of the work has been derived to the development of the project of an

expanded beam interferometer made in cooperation with the department of Laser and

Optoelectronic in the Carlos III University. First results are published in [ref Acedo08].

II.2.1.3. Thomson Scattering

During the 2008 TJ-II summer shutdown, it was accomplished the installation of a new

calibration system for the diagnostic, including spectral lamps (Argon and Helium), a

continuous tungsten-halogen lamp, and a linear incandescent lamp equipped with small

pinholes (200 micrometres) 20 mm from each other, in a rigid mechanical framework.

This framework provides the degrees-of-freedom needed for precise location of the

different light sources used, and, in some cases, the adjustments to align them.

In the 2008 autumn plasma campaign, the Thomson Scattering group has tested for the

first time in TJ-II the performance of two notch filters in series in an attempt to eliminate

completely the stray light coming from the laser, and perturbing to some extent the

Thomson Scattering data. Preliminary results seem encouraging, but more experiments

are needed to evaluate the loss of signal implied by the additional notch filter, and to

calibrate the whole system under these conditions. If the performance of the system

turned out to be comparable with using only one notch filter, the new set-up could be

used in experiments where very low noise measurements were required.

II.2.1.4. First measurements of EBW emission at 28 GHz

A 28 GHz electron Bernstein waves emission diagnostic (heterodyne detection) was

installed in September 2007. The system was put into operation in the first half of 2008

and the first measurements were performed [ECRH2]. The main goal of this diagnostic is


to investigate EBE along the same line of sight that is going to be used for the heating

system. In this system, the last component of the power transmission line is a steerable

internal mirror located inside the vacuum vessel, which may be used to scan different

launching orientations of the heating beam. In this way, it is expected that the

determination of the internal mirror position for which emission is maximum can provide

valuable information to maximize the O-X transmission efficiency during the heating

experiments. During 2008, after some improvements in the signal to noise ratio and the

installation of 32 kHz filter, the EBE system has been measuring routinely in NBI plasma

discharges, where the electron densities at the plasma edge are well above the cut-off

density of the first harmonic O-mode. In these conditions, EBE emission is expected. The

analysis of the acquired data is underway.

This work has been carried out in the frame of the collaboration with the Oak Ridge

National Laboratory, Oak Ridge (USA).

II.2.1.5. Diagnostic Neutral Beam Injector (NBI) and VUV studies

After obtaining localized impurity ion temperature and poloidal velocity measurements

with the dedicated neutral beam injector diagnostic in plasmas heated by electron

cyclotron resonance during previous years, measurements were focussed on the neutral

beam heating phase in 2008. For this a collecting lens that covers a larger radial profile

has been installed in the upper observation window of sector A7. A previosly unreported

phenomenon has been observed in vacuum ultraviolet spectra recorded every 5 ms in

NBI heated plasmas. Broad line structures are observed about strong oxygen oin lines

during NBI operation. These features are associated with water impurities in the ion

source, which after acceleration, dissociation and neutralization, can reach the plasma

where the fast oxygen neutrals are ionized and trapped. These trapped oxygen ions

undergo further ionization as they travel around the machine, with the resulting line

emissions being detected as Doppler shifted lines.

II.2.1.6. Turbulence and plasma potential evolution by HIBP diagnostic in

the TJ-II stellarator

The direct measurements of an electric potential and its fluctuations in a core plasma are

of a primary importance for the understanding of the mechanisms of the L-H transitions

in toroidal plasmas and the role of the electric field in plasma confinement. Heavy Ion

Beam Probe diagnostics in TJ-II stellarator has been upgraded to study directly with a

good spatial (up to 1cm) and temporal (up to 1 μs ) resolution the plasma electric

potential and density, poloidal component of electric field fluctuations to extract the

radial turbulent particle flux. Recent experiments with Li-coating and NBI heating have


shown evidence for spontaneous transitions in the TJ-II stellarator. During the direct L-H

transition edge and core fluctuations are strongly reduce. Plasma potential radial profiles

show an increase in the radial electric field.

II.2.1.7. Development of a new Ti edge diagnostic

Very useful information on the electron density and temperature profiles in TJ-II have

been provided by the He beam diagnostic in a systematic way to date. The accurate

reconstruction of these profiles from the monitored emissions of the He electronic states

populated by the plasma requires the validation of the corresponding collisional- radiative

model. This work was the topic of the PhD Thesis of A. Hidalgo from 2002 to 2006. Very

recently, our group has extended the analysis of the beam data to the determination of

ion temperature profiles This pioneering work was part of the PhD thesis of Dr F.

Guzman, presented in 2008, and it has opened completely new possibilities of the

technique (He_1). Furthermore, the results obtained in TJ-II in the last year suggest that

not only the Ti profile can be reconstructed, but also the plasma rotation at the edge,

directly linked to the presence of electric fields and enhanced confinement modes, could

be deduced from the He ion emission profile. Experiments aimed at vpol and vtor

determination have been started during 2008. The full exploitation of the SHB technique

for the shake of the fusion community is now awaiting for a thorough modelling of the

observed emission lines of the He ions injected by the beam.

II.2.1.8. Experimental system for spectral line ratio measurements in the

TJ-II stellarator

The chord-integrated emissions of spectral lines were monitored in the TJ-II stellarator

by using a spectral system with time and space scanning capabilities and relative

calibration over the entire UV-visible spectral range. This system was used to study the

line ratio of lines of different ionization stages of carbon (C5+ 529.0 nm and C4+ 227.1

nm) for plasma diagnostic purposes. The local emissivity of these ions was reconstructed,

for quasistationary profiles, by means of the inversion Fisher method. The experimental

line ratio was empirically studied and in parallel a simple spectroscopic model has been

developed to account for that ratio. We investigated whether the role played by charge

exchange processes with neutrals and the existence of non-Maxwellian electrons, intrinsic

to Electron Cyclotron Resonance Heating (ECRH) heating, leave any distinguishable mark

on this diagnostic method. [ref spectral_1].

II.2.1.9. Development of a flexible luminescent probe to monitor fast ion

losses at the edge of the TJ-II stellarator


A mobile luminescent probe has been developed to detect fast ion losses and

suprathermal ions escaping from the plasma of the TJ-II stellarator device. The priorities

for its design have been flexibility for probe positioning, ease of maintenance, and

detector sensitivity. It employs a coherent fiber bundle to relay, to the outside of the

vacuum chamber, ionoluminescence images produced by the ions that impinge, after

entering the detector head through a pinhole aperture, onto a screen of luminescent

material. Ionoluminescence light detection is accomplished by a charge-coupled device

camera and by a photomultiplier, both of which are optically coupled to the in-vacuum

fiber bundle head by means of a standard optical setup. [ref flprobe]

II.2.1.10. Characterization of phosphors

We continued working on the characterization of a radiation-hard ceramic scintillator,

Al2O3:Cr, which is a promising candidate for use in the fast-ion-loss detector for ITER [for

the range of thermal (low energy) and suprathermal ions]. We quantified and compared

its ionoluminescence with that of some common luminescent materials (YAG:Ce and

ruby) when irradiated by H+ ions accelerated to <= 60 keV using a purpose built

laboratory setup. Next, studies were made on the ceramic to quantify its response as a

function of incident ion mass, i.e., to He+. For this, the absolute luminosities of the

material were estimated in terms of the number of photons emitted per incident ion as a

function of energy. Moreover, the radiation hardness and postirradiation recovery of the

ceramic were investigated. Finally, from the studies it was concluded that the ceramic

ruby is a good candidate for detecting low energy ions as long as its temporal response

(approximately several milliseconds) is not a constraint for specific ion measurements

[ref Phos_1].

We also characterized the ionoluminescent response of several phosphor powder

materials when irradiated with ions of different masses (H+, He+, Ar+) accelerated to keV

energies. In particular, we determined the absolute luminosity in terms of the number of

photons per incident ion emitted by luminescent screens of Y2O2S:Tb (P45), Y3Al5O12:Ce

(P46), Y2SiO5:Ce (P47), Y2O3:Eu (P56), and SrGa2S4:Eu (TG-green). Their

ionoluminescence was studied as a function of ion beam energy and current and ion

fluency. The energy trend and mass dependence of selected experimental results were

compared relative to stopping and range of ions in matter (SRIM) code predictions [ref

Phos_2].

II.2.1.11. CX-NPA studies

During 2008 campaign the central charge-exchange fluxes have been routinely measured

in two nearly central radial positions. The ion temperature on these two points has also



been calculated using this data. Also the fluxes in a tangential line of sight are measured,

in relative units. In the NBI discharges the fast ions coming from the injection have been

characterized with the compact neutral particle analyzer.

Some ion temperature radial profiles have been obtained both in ‘standard’ and reversed

magnetic fields, with different heating schemes, only ECRH or NBI heating. The

comparison of the profiles shows the different ion drifts depending on the magnetic field

direction. It also shows the different profile shape depending on the heating scheme,

rather flat for ECR heating or parabolic for NBI heating.

II.2.2. Development of plasma diagnostics in W7X

II.2.2.1. Interferometry

The cooperation work for the W7X interferometer can be arranged in three tasks:

a) On line phase measurement for stationary discharges. We have studied the cross-talk

problems and acceptable bounds [ref MSanchez]. Also we have built an analogue diplexer

to split the laser frequencies and we are testing now with digital filters.

b) Some studies of thermo optics effects on the ZnSe windows have been done in IPP

(W7X). Also maximum bounds are been defined.

c) Some contributions to the general design of the diagnostic have been carried on and

several practical considerations from TJ-II have been translated to W7X.

II.2.3. Diagnostic exploitation and development in JET

II.2.3.1. Tools to analyse JET data

We worked with the JET Core Spectroscopy Group to develop a new application to fit

profiles with JET data. The profiles were fitted with constrained optimization method. This

method is suitable when input data come from diverse sources (with different estimated

measurement errors, spatial resolution, local/chord measurements).

II.2.3.2. FC7-Project

Ciemat has acquired a second image intensifier to test in the JET Fast Camera System.

The intensifier must be shielded from the high magnetic fields (800 Gauss) and the

support structure reinforced. Thanks to collaborative relations with Hamamatsu Spain-

France-Japan, some modifications were accepted in the manufacturing process in order

to improve the design so as to facilitate the requirements. Calculations and first tests in


Ciemat were promising for instaling the intensifier before the end of JET experimental

campaign.

II.2.4. Reflectometry simulations

Participation in the reflectometry code benchmarking cross-validation and optimization.

During 2008 the ERCC (European Reflectometry Code Consortium) activity has

concentrated in the cross-validation of existing two-dimensional full-wave codes. Also,

the need for a European three-dimensional full-wave code has been identified and the

possibility to be incorporated into the EFDA-ITM (Integrated Tokamak Modelling task

force) work-programme has been proposed.

Fundamental studies on the Doppler reflectometry performance have been carried out

during 2008 using the two-dimensional full-wave code developed at CIEMAT. The

numerical results show that the perpendicular velocity of the density fluctuations can be

obtained with high accuracy for broad ranges of antenna tilt angles, turbulence levels and

radial correlation lengths of the density fluctuations. The diagnostic potential of Doppler

reflectometry to determine the perpendicular wave-number spectrum of the density

fluctuations depends on the reflectometer response at different probed wave-numbers

and different turbulence levels. A linear dependence between the scattered wave

amplitude and the turbulence level has been found for low turbulence levels and short

radial correlation lengths of the density fluctuations; whereas at high turbulence levels

and/or large radial correlation lengths the relationship becomes non linear. In addition,

numerical results show that reflectometer response depends only very slightly on the

probed wave-number [ref Blanco08].

II.2.5. Diagnostic development in ITER

II.2.5.1. Plasma Position Reflectometer

Diagnostic integration into the upper port plugs #01 y #14 and other port structures: A

complete integration study of all systems that are to be installed in the port plugs has not

been possible so far (complete CATIA models are not available), only a preliminary

analysis has been carried out. Upper port-plug #01 integration: Interfaces between the

central tube and both, bolometer mini-cameras and gap 5 antennas can be envisaged

near the blanket shield module. At the port plug flange interfaces are not expected

though more information is required to be conclusive. Upper port-plug #14 integration:

No interfaces are expected.

In-vessel integration of waveguides and antennas: The reference designs for the in-

vessel waveguides and antennas have been analysed and modifications have been

introduced looking for more appropriate solutions. The main modifications can be

summarized as follows:

An in-vessel waveguides flange shared by the two waveguides and with a central

hexaedrical pin is proposed to ensure a good alignment of the waveguides and to avoid

crosstalk between emitting and receiving waveguides. Preliminary ANSYS

electromechanical analysis of the waveguides flange has been done and no structural

problems are foreseen.

The in-vessel waveguides routing has been slightly modified to avoid the interface with

the vacuum vessel sector weld and to smooth waveguide bends.

Although gap 4 and 6 antennas reference design appeared to be good from the viewpoint

of the thermal studies, it has had to be modified due to the need of including an electric

insulator between the antennas and the waveguides that prevents the heat to be

dissipated through the waveguides and supports to the vacuum vessel. Taking into

account that the first constrains on the antenna design arise from simulations of thermal

loads, a finite element thermal model with ANSYS was developed. Once the temperatures

were kept at acceptable levels, structural analysis has been performed to know the

thermal stress. Simulations have been carried out using different materials and support

structure geometries. Further, it has been checked that the components can withstand

the electromagnetic loads expected during disruptions and vertical displacement events.

The stress due to these electromagnetic loads has been calculated analytically as well as

with ANSYS simulations. It has been shown that the proposed antenna arrangement is

properly designed against thermal and mechanical loads.

II.2.5.2. Development of Equatorial Visible/InfraRed Wide Angle Viewing

System

The optical design has been studied jointly by CEA and CIEMAT. Taking into account the

characteristics of an IR detector that could be reasonably available in a near future, the

spatial resolution obtained does not meet the current specification requested by ITER

Organization (5 mm for the first wall surface temperatures). This means that in the

future the optical design will have to be optimized taking into account both the best

sensor that could be developed during the design phases, and the best resolution that

could be reached with such sensor, while checking if the present spatial resolution

requirements are really mandatory or can be relaxed [ref vis-ir viewer].


For the integration into the port plug, a new approach is under study, which would

consist in inserting the diagnostic into removable cassettes. The consequence is that the

optical paths will need to be made as straight as possible along the radial axis, while

keeping labyrinths for neutron shielding.

An assessment of the materials for the optical components has also been performed. For

the visible light transport, some radiation hard materials already exist and are used in

nuclear fission facilities (quartz glass KS4, low density material doped with cerium oxide:

RS-BK7, RS-LF5, RS-SF6, RS-F2). For the infrared light transport, no radiation hard

materials are already available “off-the-shelf”. Radiation hardness tests will thus have to

be performed on conventional IR materials like Ge, Si, ZnS, ZnSe, and on materials that

are transmissive in IR and visible, like MgO and YAG.

Finally, the possibility to add fast visible cameras (time resolution ~10 µms) to the

diagnostic has been assessed, for the study of fast phenomena like ELMs, disruptions,

UFOs and pellet tracking, that could not be observed with the time resolution of

conventional visible cameras (10 ms), and also for the imaging of atomic line emission of

fuel and impurity atoms and ions. This study is based on the promising results obtained

in JET with the fast camera that has been recently installed there (FC-7 project).

II.2.5.3. Thomson Scattering

CIEMAT has contributed in 2008 with a final conceptual engineering design to support

and keep aligned mirrors # 3 and 4 in the so called “port plug interspace zone” of

equatorial port # 10 where the LIDAR diagnostic for ITER is to be located. The design has

taken into account issues related with suitable structural materials, clamping systems to

the Port-Plug flange, remote access to the structure, mechanical and thermal

computations (CATIA and ANSYS) to assess the stability of the proposed design and ray

tracing and kinematic calculations to define the movements needed in case of re-

alignment of the mirrors is required. A proposal and a conceptual design are made for

the structural framework and mechanisms able to perform these tasks, based on proven

commercial technologies like multi-axis piezoelectric motors or pneumatic gear-box

mechanisms.

II.2.5.4. Magnetic sensors. Cluster CEA /CRPP /CIEMAT /IPP-CR / TEKES

• Assessment of steady-state magnetic sensors

The specifications of CMR sensors (LCMO,LSMO,SFMO and magnetite) and their relative

ranking to ITER specs have been included in the steady state sensor assessment report,

along with the outstanding issues regarding these sensors that require some extra R&D



effort. Also, the installation and cabling requirements and cost estimates for this type of

sensors have been included in the project plan for the ITER magnetic diagnostics

• Assessment of determination of stored energy and ITER diamagnetic loop

performance analysis.

A magnetostatic suit to calculate magnetic fields of arbitrary coil geometries and

magnetic fluxes through loops of arbitrary geometry has been developed. This suite is

ready to accept ITER coils and diamagnetic loop geometries to assess the performance of

the diamagnetic loop due to arbitrary geometry changes, e.g orientation, loop torsions,

etc.

II.3. Plasma fueling

II.3.1.

II.4.1.

Fuelling studies in TJ-II

This task was not addressed in the 2008 campaign, and it is planned for the 2009

campaign.

II.4. Real Time Measurement and Control

Techniques for data storage and retrieval (ITER)

Databases of present and future fusion devices are characterized by an extremely large

amount of data. For example, the JET database stores over 40 Tbytes of data and ITER is

expected to collect Pbytes/year.

One of the reasons of the rapid increasing of the storage is the use of imaging

diagnostics. The use of lossless data compression techniques with images (not only for

data archiving but also for data transmission), was discussed in the Workshop on ‘New

Technologies and Innovative Processing Methods for Imaging in Fusion Devices’ held at

JET. Results with the JET KL7 and KL8 cameras have been presented (DSR_1).

Data retrieval in so big databases can no longer be based on signal name and shot

number. Data should be accessed according to scientific and technical criteria (DSR_2).

This means that efficient data retrieval mechanisms should be put into operation for

ITER. Different methods have been proposed that are based on pattern recognition

techniques (DSR_3, DSR_4 and DSR_5). Specific developments for the databases of two


fusion devices, the TJ-II stellarator and the JET tokamak, have been carried out for both

waveforms and images (DSR_6 and DSR_7).

In the Workshop mentioned two paragraphs above, a detailed analysis on automatic data

retrieval with TJ-II and JET images was presented (DSR_8).

II.4.2. Data mining techniques (pattern recognition)

This section is devoted to analyzing plasma physical behaviours by means of data mining

techniques. A first application of structural pattern recognition methods has been

developed for the investigation of specific physical phenomena at JET. The objectives

were the automatic search of ECE cut-offs in temperature signals and the identification of

regime transitions (DM_1). A new set of features was investigated to study disruptions in

JET (DM_2) and data tours techniques were used as classification systems to distinguish

between disruptive and non-disruptive behaviours (DM_3). Finally, a classifier based on

support vector machines was developed for JET plasma configurations (DM_4).

II.4.3. Development of TJ-II operation scenarios for dynamic

control of magnetic configuration

• Single discharge magnetic configuration sweeping at the TJ-II heliac.

Confinement in stellarators is linked to magnetic configuration structure. One of the aims

of the TJ-II device is to study the influence of magnetic configurations on confinement

and stability. This requires numerous discharges with different sets of configuration

currents that are not always easy to reproduce in terms of physic results. Discrimination

between kinetic and magnetic effects is always cumbersome. A better approach is to

establish a dynamic route in the configuration space that can be swept in a single

discharge. Then, a sequence of discharges with different kinetic parameters will have

immediately comparable magnetic characteristics. The aim is to obtain inter-shot

decoupling between kinetic and magnetic effects and consistency between

direct/reversed scans.

Dynamic configuration sweeping requires changing dynamically the configuration coil

currents during the plasma heating and fuelling phase. To avoid induction of large ohmic

currents associated with this mode of operation, a transformer coil is used to counteract

the flux variation produced by the sweeping of the configuration coil currents. This

project opens up a new research line to explore the influence of magnetic configuration in

a whole new manner.


• Project results:

a) Initial feasibility.

A numerical code to compute mutual inductances between configuration coils /

transformer coils as function of flux surface index was developed and used to test

engineering limits and to design the experiments.

b) Testing.

Open loop experiments with direct and reversed large coil currents of about 12kA/s and a

large iota variation from 1.6 to 1.85 have been performed at constant plasma volume

with no induced ohmic current. Positive testing of some theories linking transport

reduction with magnetic islands has been possible with this new operation mode.

c) Dissemination of results.

First results of this work have been reported in the 2008 IAEA Conference [DYNAM_1].

Also, a description of this work has been accepted at the European Physics conference

that will take place in Sofia, Bulgaria in June 2009 [DYNAM_2].

II.5. Mechanical Engineering

II.5.1. ITER Diagnostic Equatorial Port Plug (EPP) Engineering

and Integration : EPP Hydraulic Analysis. BSM

Attachment. UPP Kinematics Study

The task was performed by Ciemat and it was focused on the diagnostic integration on

the ITER Port Plugs (Task TW6-TPDS-DIASUP. Contract EFDA 06-1430) including the

following scope:

• Subtask 1. Cooling circuit design for ITER reference diagnostic equatorial port plug.

The objective was to provide hydraulic calculations aimed to optimise the reference

Equatorial Port Plug (EPP) cooling circuit, considering the cooling requirements of the

Diagnostic Shielding Modules (DSMs), as it was defined within the studies carried out

by UKAEA and CEA in the frame of this task, and the BSM hydraulic connections

compatible with the water inlet at the lower part and the outlet at the upper part of

the port plug. [ITERPort_1]


• Subtask 2. Study of a helping cantilever system for the assembly/disassembly of the

ITER reference upper port plug. The subtask includes the study of a helping cantilever

system for the ITER reference upper port plug. This implies the integration of two

pairs of wheels into the plug structure and the implementation of rails into the Cask

Transfer System (CTS) and into the vacuum vessel port. Furthermore, a kinematic

study of the assembly/disassembly process, the maintenance sequence and the

functional description of the plug mover and of the handling tools for the reference

upper port plug was carried out.

• Subtask 3. Mechanical designs of the diagnostic equatorial port plug BSM

attachments. This subtask was a contract extension of the main one, focused on the

final design of the BSM attachment, taking into consideration all the previous designs.

It comprises the conceptual design and subsequent structural and thermal analysis,

the hydraulic evaluation of the coolant connection, as well as the assembly procedure

definition considering remote handling requirements.

II.5.2. Ultrasonic Examination of the Divertor mock-ups

manufactured with calibrated defects

During 2008 Ciemat has continued the Ultrasonic (US) examination of the different sets

of Divertor mock-ups containing calibrated defects in the frame of the EFDA task TW5-

TVD-FABCON. The aim of the testing of these mock-ups is to set up experimental basis

for the development of appropriate non-destructive testing (NDT) procedure as well as

the definition of final acceptance criteria for the Plasma Facing Components (PFC`s) in

sight of the procurement of the ITER Divertor.

Ciemat was assigned to carry out the US inspections on the samples and for this purpose

Tecnatom (specialized company) was subcontracted. The US inspections performed

during 2008 are included in the list of references.

All the mock-ups examined have been previously tested at high heat flux (HHF) in order

to check the thermal behaviour of the joints between the different materials. The US

examinations after the HHF tests have been compared with those obtained on the

original samples (before HHF). The results show the detection of the defect, the size

changes experienced after HHF as well as changes in the materials, in particular on the

copper microstructure.

The results of the tests are included in the references [DIV-1], [DIV-2], [DIV-3] cited

below.


[DIV-1] IN-IT-DIV-008: Ultrasonic inspection after High Heat Flux of the W flat tiles mock-ups manufactured by

Ansaldo. EFDA Task TW5-TVD-FABCON.

[DIV-2] IN-IT-DIV-009: Ultrasonic inspection after High Heat Flux of the CFC monoblocks mock-ups

manufactured by Plansee. EFDA Task TW5-TVD-FABCON.

[DIV-3] IN-IT-DIV-010: Ultrasonic inspection after High Heat Flux of the W monoblocks mock-ups

manufactured by Plansee. EFDA Task TW5-TVD-FABCON.

II.5.3. Neutral Beam Remote Maintenance System Design

EFDA Task Reference: TW6-TVR-NBRH (ITA Task Reference: ITA 23-30) (EFDA

CONTRACT: FU06-CT-2006-00142 (EFDA/06-1456))

Crane

Subtasks 4.2 (Logistics and space availability) and 4.3 (Engineering crane design) were

developed during 2007, but during the first quarter of 2008 some work had to be

completed and the Final Reports were written. ITER IO revision of the crane design and

the logistics study in the Neutral Beam Cell confirmed some mechanical interferences

that needed to be resolved. In some cases the crane or monorail design were modified,

in other instances modifications to the NB Cell had to be implemented:

• The ACCC #6 and the balcony plates have been lowered by approximately 200 mm to

increase the clearance during transport of the Calorimeter

• The DNB HV line has been re-routed to avoid a clash during transport of coils ACCC

#4 and #5

• The horizontal ceiling beams at the rear area of the NB Cell have been modified to

allow monorail continuity between the DNB branch and the branch to the storage area

The Final Report and all the related documents were sent to F4E in February. Later on

the Commission requested to include the Intelectual Property Rights documentation,

which delayed the final acceptance of the report by F4E until July.

The Final report has CIEMAT Classification code IN-IT-NBRH-002


Rostok, Germany, in September 2008 (NB_Crane1).The paper has been published in

Fusion Engineering and Design (NB_Crane2).

Cut and Weld

Subtask 4.4 (Cut and Weld operations on the Neutral beam Components) was mainly

developed during 2007, but writing and revision of the Final report was carried out in the

first quarter of 2008.


The Final report has CIEMAT Classification code IN-IT-NBRH-002


Rostok, Germany, in September 2008 (Cut_Weld_1).The paper has been published in

Fusion Engineering and Design (Cut_Weld_2).

II.5.4.

III.1.1.

Magnetic system design for the ITER MRID (Magnetic

Residual Ion Dump)

The task started late in 2007 and carried on during the first semester of 2008.

The Final Report and all the related documents were sent to F4E in July 2008

The Final report has CIEMAT Classification code IN-IT-NBRID-002

III. DEVELOPMENT OF CONCEPT IMPROVEMENTS

AND ADVANCES IN FUNDAMENTAL

UNDERSTANDING OF FUSION PLASMAS

III.1. Optimization of operational regimes for

improved concepts

Influence of magnetic configuration in the development

of Transport Barriers

As a continuation of the works on the effect of magnetic resonances on the plasma

profiles of ECRH plasmas, discharges of an old campaign were re-analysed to verify that,

also in conditions of varying magnetic shear typical of TJ-II discharges with Ohmic

induction, lower effective electron heat diffusivities are found coincident around the

location of low order rational values of the rotational transform [ref LB_1]. The effect is

apparently stronger at higher densities [ref LB_2] and has motivated further studies

where the magnetic configuration is varied during the discharge but, as opposed to the

cases with Ohmic induction, there is practically no loop voltage allowing for rotational

transform scans without altering considerably the magnetic shear [ref LB_3].

The island properties have been studied under different conditions, having observed the

interesting phenomenon of island healing in the case of the onset of a steep pressure


gradient at the position of the resonance. The spontaneous island healing has been

observed both for natural and non-natural islands in the TJ-II. The healing was

accompanied by the stabilization of the resonant modes [ref Barriers].

III.1.2. International stellarator confinement and profile

database and neoclassical transport

III.1.2.1. Participation in the on-going activities of the International

Stellarator Confinement and Profile Data Bases during 2008

The Ciemat team has participated very actively in the above-mentioned activities through

the participation in the 4th Coordinated Working Group Meeting (CWGM) organized by

Ciemat and held in Madrid in October. Eight contributions were presented by Ciemat

members:

• flux expansion divertor studies in TJ-II (CWGM4_1) by P. Castejón

• lithium wall scenario in TJ-II (CWGM4_2) by P. Tabarés

• development of the edge velocity shear layer in TJ-II (CWGM4_3) by T. Estrada

• gyrokinetic simulation activities under development in Ciemat (CWGM4_4) by E.

Sánchez

• ongoing work on integrated modelling of TJ-II discharges with Astra code (CWGM4_5)

by D. López-Bruna

• simulations of the transit from ECH to EBW heated plasmas in TJ-II (CWGM4_6) by A.

Cappa

• dynamic configuration scan in TJ-II by (CWGM4_7) by D. López-Bruna

• island healing and CERC formation in TJ-II (CWGM4_8) by P. Castejón

III.1.2.2. Use of Global Monte Carlo codes to estimate collisional transport

properties: Explore the properties of a flux expansion divertor.

The full-f global Montecarlo code ISDEP has been obtained to study the 3D structure of

the ion flux as well as a map of this flux on the wall [ref GlobalMC]. It is seen that most

of the particles that escape from the plasma strikes the groove of the vacuum chamber,

which is close to the plasma centre. The proximity of the groove to the plasma centre is

the main problem of the plasma-wall interaction in TJ-II, since most of the flux is arriving

there and, thus an inward neutral particle flux happens. The strategy to improve the

plasma-wall interaction must be based on the reduction of this flux.

III.1.2.3. Continue the benchmark of Neoclassical Transport codes.

The main work that has been performed during the last year is the introduction of

momentum conservation corrections in the collision operator in order to study the effect

of this phenomenon in the Neoclassical transport. The former collision operator did not

guarantee the momentum conservation in the particle dynamics. An effort is being

performed to introduce these corrections in the several codes that are used to estimate

the Neoclassical transport. The Benchmark effect of the codes with this new effect is

under consideration.

III.1.2.4. Activities of the International Collaboration on Neoclassical

Transport in Stellarators

The International Collaboration on Neoclassical Transport in Stellarators (ICNTS) is one of

several activities initiated by the stellarator community to develop the tools and know-

how necessary to describe and predict the behaviour of non-axisymmetric plasmas

during high-performance discharges. One of the initial goals of this collaboration is the

benchmarking of mono-energetic transport coefficients determined from various

numerical solutions of the drift kinetic equation for a wide range of devices

representative of the extensive configuration space available to stellarators. Emphasis is

placed on the radial-transport and bootstrap-current coefficients which both exhibit a

strong dependence on the radial electric field which is lacking for axisymmetric

tokamaks.

The results obtained so far exemplifies the high quality of agreement obtained

throughout this activity. With the benchmarking of mono-energetic transport coefficients

largely completed, emphasis in the ICNTS is shifting to development of the theoretical

and numerical tools required for practical application of these results, including methods

to redress the neglect of momentum conservation in the original solutions of the kinetic

equation.

An analytical tokamak Plateau modelling was developed to understand the effects of the

incompressible approach on the monoenergetic diffusion coefficient. Comparisons made

with earlier Monte Carlo simulations shows that: i) tokamak plateau modelling is in very

good agreement with numerical calculations using the incompressible approach; ii)

energy diffusion model only works in lowest order.



Since the monoenergetic diffusion and bootstrap coefficients have been benchmarked

within the ICNT it was natural to benchmark also the parallel resistivity. A modified

version of the MOCA code was developed. First simulations show that the more work is

necessary to reduce the unexpectedly large error bars found in the calculation.

Along with these activities an international meeting was organized on October 2008 at

CIEMAT with fifteen participants from the international stellarator community.

III.1.2.5. The role of Global Neoclassical Transport in Stellarators.

The effect of Global Neoclassical Transport in stellarators has been demonstrated to be

non-negligible in TJ-II. The usual Neoclassical calculations assume two main assumptions

that are not fulfilled in our device: the particle radial excursions in a collision time are not

negligible, the electric field is strong enough to invalid the ion energy conservation

hypothesis during the particle orbit in a collision time. The development of ISDEP, a

global Montecarlo code has allowed us to avoid these approximations and, moreover, to

study the transport without the diffusive assumption. The ISDEP code has been also

prepared to introduce non-linear effects, which enables the study of the plasma

evolution. The non-linear effects are introduced by an iterative process in which the

background plasma is updated with the evolved test particle distribution function. This

modification converts ISDEP in a full-f Montecarlo code that permits the calculation of the

full ion distribution function. All these developments have been used to study the ion

heating during Core Electron Root Confinement (CERC) in TJ-II [ref NCTransport].

III.1.3. Full lithium coating in TJ-II

In the last two years the PWI team has implemented the lithium coating technique in TJ-

II, the first time this new concept has ever been applied to a Stellarator. The outstanding

improvement in particle and impurity control under the new wall scenario has allowed the

production of NBI-heated plasmas in a routine way. Record values of plasma parameters

such as central density, diamagnetic energy content and plasma confinement were

achieved in 2008. Transition to the H mode in TJ-II has been achieved with peaked

pressure profiles. Furthermore, the discovery of high density, central impurity-free

plasma profiles in TJ-II under Li walls represents an important milestone with promising

implications in the development of Stellarator-based reactor concepts, somehow

jeopardized by the tendency of impurity accumulation due to neoclassical central

transport. These results have motivated a series of Invited Talks (LiT-1, LiT-2, LiT-3) and

Publications (Li_1, Li_2, Li_3, Li-4 and Li-5) and the proposal for collaborations in the

Stellarator community.


In any case, extrapolation of the TJ-II results to other Fusion devices requires detailed

modelling of the plasma and atomic physics involved under the new wall operation.

[LiT-1]: F.L. Tabarés et al. Effect of Li coating in plasma confinement and performance in TJ-II. EPS

Conference 2008 Hernossisos Jun. 2008

[LiT-2]: F.L. Tabarés et al. “The Li Wall Stellartor. TJ-II as a benchmark”, Alushta Conference , Sept.2008

[Li-4]. F.L. Tabares. 18thToki Conference. To appear in Plasma and Fusion Research, 2009

[Li-5]: J. Sánchez et al. IAEA paper TJ-II Li. To appear in Nucl Fusion 2009

III.2. Understanding of plasmas characteristics for

improved concepts

III.2.1. Momentum transport

III.2.1.1. Multi-scale physics mechanisms and spontaneous transport

bifurcations in fusion plasmas

The magnitude of radial transport in magnetic confinement devices for controlled nuclear

fusion suffers spontaneous bifurcations when specific system parameter values are

exceeded (e.g., the mean density in the TJ-II stellarator). TJ-II findings show, for the

first time, that the correlation length of the plasma potential becomes of the order of the

machine size during the bifurcation itself, quite unlike the density fluctuations.

The mechanism governing the development of this bifurcation, leading to the

establishment of a transport barrier, is still one of the main scientific conundrums facing

the magnetic fusion community after more than twenty years of intense research. The

results presented here confirm the prediction that multi-scale physics constitute an

essential ingredient to explain the Low to High (L-H) transition in fusion plasmas. This is

in line with the expectation that multi-scale interactions are a crucial ingredient of

complex dynamics in many non-equilibrium systems.

III.2.1.2. Visualization of plasma flows and blob dynamics with wide angle

view by means of fast intensified cameras

Activities in TJ-II mainly comprise the scientific exploitation of the installed fast camera

system, with its recent upgrade, the image intensifier. One of the main applications of

this system is the direct observation of regions where plasma-wall interaction is

dominant: In these environments, almost no intensification is necessary, because

radiation coming out of penetrating recycled neutrals lightens the flow along significant

radial distances from the Scrape Off Layer. With the intensifier, high velocities are really

made available for the observation of both lightened and not lightened flows. In

combination with appropriated optics, this allows the observation of turbulent processes.

In particular, low intensity phenomena were possible to be visualised by the installation

of image intensifiers, allowing the direct observation of turbulent transport events in the

scrape off layer (SOL). Two kinds of phenomena have been described: first, the

observation of turbulent structures propagating poloidally at the plasma edge has not

only confirmed rotation direction changes, as observed by other diagnostics, but alo

shown enough periodicity to allow correlation between them with repetition rates around

10 kHz, as a quasicoherent mode. Second, the analysis of plasma wall interaction by

filtered imaging –in which the intensifier has proven its importance, given the signal

atenuation of the interferometric filters- have shown that there is a change in the

“preferred” plasma wall interaction area, going from a hardcore toroidally limited plasma

to a poloidally locally limited one in the transition from ECRH to NBI heated plasmas. As

a result of these studies, a paper has recently been published on Journal of Nuclear

Materials.

III.2.1.3. Visualization of plasma flows in the LHD stellarator

From October to November 2008, first phase of NIFS/EURATOM-CIEMAT cooperation has

yielded a number of fast camera observations of several LHD operation features. Main

results include:

• Broad view observation of visible Bremsstrahlung (VB) radiation from high density

core, leading to new core mechanics analysis tool. This allows the observation of

structures and events on high density cores. Along with the good spatial and

temporal resolution of VFC, this may prove a very useful tool in next step devices.

• Core Density Collapse (CDC) analysis. Of particular interest are core signal

contraction (and eventual previous fluctuation), external rotative helical filaments,

transients in separatrii structures and overall comparison with numerical simulations

• Radiative collapse observation Rotative “Serpens” found during collapse by UV arrays

is visualized on full 3D perspective. CIRC events show zonal flow-like mechanics,

including counter-rotating radial layers and blob shearing

Filament propagation observations during high beta discharges: parallel and

perpendicular velocity has been measured outside the separatrix.

III.2.1.4. Influence of electric fields on supra-thermal electrons: role of

dynamic biasing



In December 2008, a test of dynamic biasing of a graphite electrode was performed

under both on-axis and off-axis ECR launching conditions with a multifold purpose, one of

them, the study of suprathermal electron losses. Detection of fast electrons is usually

done using an intrinsic germanium detector whose line of sight is directed to one of the

poloidal limiters of TJ-II. The detected bremsstrahlung emission is the result of the

impact of part of the circulating suprathermal electrons that get trapped and lost in the

observation sector. As was expected, the observed flux intensity was higher when off-

axis heating was applied but the signal modulation produced by the a.c. biasing was

more pronounced in on-axis heated discharges.

The behaviour of the radiated power in the same shots was monitored with identical

photodiode arrays located at different toroidal positions. Two of them, A7 and D7, were

close to the Langmuir probe-arrays (B2 and D4 sectors). No matter the ECR absorption

regions were, what was observed is that, once surpassed the critical density for the

magnetic configuration studied, the modulation of outer edge (R > R0) radiation signal

detected in sector A7 reverses sign with respect to the rest of peripheral radiation

signals. At the same time, the saturation current collected with the probe in sector B2

shows also a reversal modulation with respect to the floating potential, while in sector

D4, ion saturation and floating potential signal modulations are in phase. The first

conclusion that can be extracted from the data below is that edge biasing produces both

global and local effects on TJ-II plasmas.

III.2.1.5. Confinement transitions and bicoherence

The bicoherence is generally considered to be an appropriate technique for the detection

of mode coupling, such as may occur in sheared or zonal flow generation. A systematic

analysis of the bicoherence was performed using probe data at the TJ-II stellarator,

during induced or spontaneous confinement transitions. The bicoherence was found to

rise during the transitions, but only at specific radial locations, as expected [P2_021, and

MIL_NF].

III.2.2. Current drive physics. ECCD experiments: comparison

TJ-II vs. Heliotron-J

Electron Cyclotron current drive (ECCD) experiments have been performed in

collaboration in the TJ-II and Heliotron-J stellarators, in order to compare the different

features of these devices. The dependence of the induced current with the parallel

refractive index is similar in both devices and pretty similar to the predicted by the

theory. The dependence of ECCD efficiency on other magnitudes like power or density


are very different in both devices. The results show that the kinetic effects on current

drive are stronger in TJ-II than in Heliotron-J. The reason for this difference can be

attributed to the larger ripple of TJ-II device that makes the effect of electron drifts to

have stronger influence on the current dymamics [ref comparison].

III.3. Other experimental activities

III.3.1. Remote participation

The activity during 2008 has been based on two aims. On the one hand, a federated

security infrastructure to access computational resources of EFDA sites has been

implemented (RP_1 and RP_2). On the other hand, a test-bed for on-line diagnostic

monitoring at JET has been started (RP_3). This project is being carried out with people

from JET and CIEMAT (co-ordinator). The proposal was discussed in depth in a Workshop

on Remote Participation held in Padova (Italy).

III.4. Theory and modelling

III.4.1. Modelling of kinetic effects on transport

III.4.1.1. Kinetic Transport

The study of kinetic effects on transport is a basic task in stellarators, where the

geometry imposes very different dynamics on the particles, depending on their energies

and pitch angles. The inclusion of global effects can give rise to the apparition of non-

diffusive phenomena and other interesting features. TJ-II is a very complex device where

the geometrical effects are especially strong, so their plasmas are perfect to develop

such investigations.

A new code, able to evolve the drift kinetic equation for the one-particle distribution

functions of a multi-species plasma, has entered the benchmarking process. The code

can handle arbitrary magnetic toroidal geometries, including complicated ones as that of

the TJ-II, owing to its meshing procedure: the spatial coordinates are approximately

aligned with the magnetic field lines. The kinetic coordinates permit a polynomial

expansion in Legendre and Sonine polinomials. This simplifies considerably the evaluation

of moments of the distribution function and, at the same time, imposes no essential

truncations of the distribution function in ordering parameters [ref KT_1 and ref KT_2].


III.4.1.2. Electron heating and Kinetic Transport

Another important topic to cover with these studies is the iterplay between heating and

transport. The heating modifies the velocity distribution funciton and, hence, can have

strong effects on transport, depending on the collisionality. Especifically, Electron

Cyclotron Resonance Heating (ECRH) has the property of increasing the perpendicular

energy of the electrons, thus increasing the perpendicular drifts of the particles and,

hence, the transport. This effect has been calcualted by including a simplified model of

the loss cone in TJ-II and a non-negligible extra electron flux has been calculated. The

positive electric field created by this extra flux has been also estimated, showing that the

poloidal viscosity is a key magnitude for the plasma dynamics [ref EHKT].

III.4.1.3. Kinetic Simulation of Heating and Collisional Transport in a 3D

Tokamak

We continue with the study of the mutual influence of microwave heating and plasma

transport. We have adapted the ISDEP code (Integrator of Stochastic Differential

Equations for Plasmas) to include quasi linear wave-particle interaction [ref ABustos] and

the geometry and profiles of a virtual tokamak with ripple. Also, we have introduced

nonlinear terms in order to study the heating in a more accurate way. This is done

modifying the background temperature, increasing it according to the test particles

profiles. We have included a new collision operator that approximates the momentum

conservation in collisions with the background. We have simulated the device with and

without heating and studied the differences in the behaviour of the system. The main

results are the increment of the outward fluxes and the enhancement of the distribution

function.

III.4.2. Divertor stellarator physics: Investigation on the

feasibility of the flux expanded divertor concept for TJ-

II.

The magnetic island based divertor has been shown to work in the W7-AS stellarator and

is a concept that will be installed in the new stellarator W7-X. The main characteristic of

the Wendelstein stellarators is their robust magnetic configurations, which present an

island chain in the edge at almost fixed positions independently of the plasma

characteristics. On the other hand the flux expansion divertor is a promising concept for

stellarators whose magnetic topology is not fixed during the plasma operation, like those

flexible stellarators (TJ-II) or those whose magnetic configuration relies on the plasma


current like NCSX. There is no experimental experience on the performance of such type

of divertor so it would be interesting to have some reliable data before its installation in a

large stellarator. This just the aim of this project in TJ-II: to explore the performance and

reliability of the flux expansion as a divertor concept. Further studies that take into

account the fast particles are performed and an experimental strategy is under

development [ref IAEA08].

III.4.3. Statistical Description of Transport

III.4.3.1. Topological characterization of flows in plasma turbulence

Although visualization techniques are useful in the study of turbulent fusion plasmas,

they do not provide a quantitative characterization of the flow structures. We aim to

address such characterization by measuring topological invariants of the structures. For

spaces embedded in R3 there are three topological invariants which give valuable and

intuitive information: the first three Betti numbers b0, b1, and b2. b0 gives the number of

connected components, b1 the number of independent non-contractible loops, and b2 the

number of cavities. In Ref. [ref Carreras] we have introduced the computational tools

which allow determining, in an efficient way, the Betti numbers of very complicated

structures. The technique, which can be applied to any type of turbulence dynamics, is

illustrated through the example of resistive pressure-gradient-driven turbulence in

toroidal geometry.

III.4.3.2. Numerical evidence of fractional poloidal transport

In toroidal plasmas, resistive pressure-gradient-turbulence exhibits an interesting

unstable regime for β below the threshold for fully developed turbulence. In this regime

the spectrum of the fluctuations is dominated by a few toroidal mode numbers and

quasicoherent global structures with very complicated topology may form. It is expected

that these structures dramatically break homogeneity and isotropy, so that transport

become strongly non-diffusive. In Ref. [ref Calvofpt] we have studied the poloidal

transport of particle tracers in this system, showing that it can be understood in terms of

the results where fractional diffusion equations in periodic systems and their relation with

Continuous Time Random Walks were discussed.

III.4.3.3. Mathematical aspects of fractional stochastic processes

In the last decade a remarkable amount of numerical results suggests that non-diffusive

equations might be relevant for describing transport in certain fusion plasmas. From this


perspective, it is of the utmost importance to make progress in the theoretical

understanding of the origin of transport equations which differ from the standard

diffusion equation. Since the diffusion equation is associated to Gaussian and Markovian

statistics of the underlying microscopic process, it is natural to investigate what happens

when these hypotheses are violated. In [ref Calvofsp] we have studied fractional

Brownian motion, in which Gaussianity is kept but non-Markovian effects are included

through time-correlations. In that paper we rederive the propagator of fractional

Brownian motion in the language of Feynman integrals, which might open a way to

compute more complicated observables.

III.4.3.4. Probabilistic and test particle transport

In recent years, we have focused part of our research efforts to the problem of test

particle transport, as this technique can provide additional information on transport not

revealed by more common profile analyses.

We have used this technique to study transport in existing numerical turbulence

simulation codes, revealing the existence of non-diffusive poloidal transport in resistive

pressure-gradient-driven turbulence in toroidal geometry [P2_043 and CAL_POP]. The

technique was also applied to the full-tokamak turbulence code CUTIE, showing that the

radial transport of particles is not well described by simple standard diffusive equations,

but is clearly non-local and non-Markovian [P2_039]. These conclusions, while not

completely unexpected, have important consequences for the modelling of transport in

fusion devices.

Related to this, some theoretical studies concerning Continuous Time Random Walks

were undertaken. The proper fractional generalisation of Fick’s Law was established

[P1_031] and the treatment of general boundary conditions for the CTRW in finite

domain systems was studied [MIL_JPHYSA].

III.4.3.5. Transport and stiffness

The issue of profile stiffness is a long-standing conundrum for fusion plasma research.

Studies of stiffness in a simplified but stiff transport model have led to the definition of a

set of stiffness quantifiers, allowing a more systematic approach to the problem

[MIL_PFR].

III.4.4. Theoretical EBW studies in TJ-II

III.4.4.1. Ray Tracing and Full wave calculations of the O-X-B conversion

process in the TJ-II stellarator

The O-X-B conversion process is a complicated wave phenomena that may occur in

magnetically confined plasmas depending on the wave frequency considered, the wave

propagation angle, which needs to be very precisely settled, and the plasma density.

Usually, from the theoretical point of view, the O-X mode conversion is calculated only

with WKB theory and an approximate plasma dispersion relation. This means an

electromagnetic field mainly described by plane waves for propagation directions not very

different from the optimum one. When a real Gaussian beam is considered, the results of

the ray tracing calculations may be very far from the real behaviour, depending on how

we simulate the beam with WKB rays, and also on the particular geometry of the

launching beam, that is, beam waist and focus position. Moreover, conventional beam

tracing is not valid in the O-X conversion layer and thus only full wave calculations may

give and accurate description of the O-X process.

A finite difference-difference time-domain code was used to obtain the full wave solution

to the problem. Optimum O-X conversion is found if the wave front of the incident beam

is matched to the local curvature of the O-X conversion layer [ref Ray_1]. Two-

dimensional calculations were performed in the toroidal and the poloidal planes of a TJ-II

like plasma cylinder. Quasi-3D calculations have also been carried out taking into account

the plane waves spectrum of the beam. A preliminary comparison between these

calculations with former ray tracing simulations [ref Ray_2] that were designed to take

into account the plane waves spectrum of the beam and its divergence in the k-space in

an approximate way has shown comparable results in certain conditions. A detailed

comparison between both results is still missing.

III.4.4.2. Linear estimation of EBW Current Drive

Electron Bernstein waves (EBW) have been confirmed as a suitable choice for plasma

heating and current drive generation (EBCD) at densities where the O and X modes find

cut-off values. In the work carried out so far, an estimation of the efficiency function of

current generated for a relativistic distribution function were estimated using Langevin

equation techniques. The arbitrary large values of the refractive index, due to the EBW

propagation properties, made necessary the expansion of our calculation up to any

Larmor radius order. Particle diffusion into the trapping region in momentum space was

also included considering the Okhawa effect, and the estimation of the fractions of power

absorbed by trapped and circulating particles were separately represented. First

calculations with this numerical tool were carried out considering a circular tokamak

geometry with temperature and density profiles similar to the plasmas confined in TJ-II,



varying the parallel refractive index and trapping parameters. The results show optimal

values of parallel refractive index for current generation as also a more stressed influence

on the trapping parameter than in the launch direction. This method was successfully

implemented to the ray tracing code (TRUBA) in order to include the complex geometry

of TJ-II as well as refraction effects [ref linearest].

III.4.4.3. Link between particle transport and heating, using TRUBA and

ASTRA codes

The EBW absorption and transmission properties strongly depend on the plasma

characteristics, namely electron density and temperature profiles. Those profiles are

determined by transport, which is governed by the power deposition profile. EBW heating

is envisaged to be used as the routinely heating system in overdense plasmas in TJ-II, so

the power will be delivered by EBW in such cases. Therefore the calculation of the

interplay between transport and heating with the ASTRA and TRUBA codes is basic to

guarantee that we are having a good performance of EBW in TJ-II. The ASTRA code

transport evolves plasma profiles and every millisecond (a time shorter than the energy

confinement time) the ray tracing code TRUBA is launched in order to estimate the

evolving power deposition profile. The calculation is performed in order to simulate the

prescribed sequence of fuelling and heating in TJ-II: in order to transit from the X mode

to EBW heating scheme it is necessary to perform a gas puffing for increasing the

density. The preliminary results show that this transit can be performed avoiding easily

the radiative collapse and the EBW power deposition profile becomes more and more

centred during the plasma evolution.

III.4.5. Eirene code studies

III.4.5.1. Spatially resolved H�-emission simulation with EIRENE in TJ-II to

study hydrogen atomic and molecular physics in low density, high

temperature fusion edge plasmas

We have validated the recently implemented EIRENE code in TJ-II stellarator by

simulating the radial H�-emission profile as obtained experimentally with a camera

looking tangentially to a poloidal limiter for a low density, high temperature plasma. The

good fit between experimental data and simulation is a strong indication of the correct

treatment of the complex atomic and molecular reactions made by the code. The neutral

density distributions of H and H2 were than analysed in TJ-II for different toroidal

locations. Finally, the physics of atomic and molecular hydrogen has been studied in

detail, the radial profiles of the most important reactions being obtained. Since for low


density (ne < 1013 cm-3), high temperature (Te > 15 eV) fusion plasma edges the

effective reaction rate coefficients do not strongly depend neither on electron

temperature nor on density, the relative importance of the different reactions should be

equivalent for other devices with similar edge parameters. In fact our simulations show

the same trends as those obtained with the DEGAS 2 code for a low density divertor edge

plasma in JT-60 U. Some further simulations show the radial profiles of the plasma

fuelling rate of the different channels of the H�-emission and of its S/XB ratio. An

interesting output reveals that the main molecular precursor of the H�-emission near the

separatrix is H2+ and not H2 [ref delaCal_NF]

III.4.6. Computation developments: Grid and Computing and

HPC for fusion

III.4.6.1. Participation in EUFORIA Project

EUFORIA (a 7th work programme project to develop computing tools for fusion research)

is a project whose main objective is to bring the fusion community to the use of large

scale computing infrastructures: HPCs and computing grids. In this way it is possible to

join three strong communities: the HPC, the grid and the fussion communities. The

Asociación Euratom/CIEMAT para Fusión is the leader of the code porting activity (JRA1).

Three codes have been selected to be ported to the grid: BIT1, a PIC code devoted to

study Scrape-off-Layer transport; EIRENE, an MC code that studies the neutral transport

in the plasma; and GEM a gyrofluid code that studies the linear evolution of turbulence.

III.4.6.2. Introduction of a simple 3D Geometry in TORB code that runs in

HPC: EUTERPE

EUTERPE is an evolution from TORB code, which was initiatilly developed to study the

gyrokinetic turbulence in a pinch and, due to its PIC nature that implies a strong

communicatin between CPUs, it must be run in an HPC. EUTERPE is a PIC code that

studies the gyrokinetic turbulence in arbitrary three dimensional fusion devices, thus

being suitable for stellarator studies. During 2008, the code has been prepared to read

the 3D VMEC equilibrium code output. This task is not easy at all since it is necessary to

change the integrator of the kinetic equations, due to the more complex geometry.

Prelimnary results on the linear evolution of the modes in TJ-II have been obtained. The

work is progressing to obtain non-linear results and to discern the important point of the

existence of Zonal flows in this complex device.

III.4.6.3. Porting of VMEC, FAFNER and DKES to the Grid

The strategy for extending the grid use in the fusion community is to enable different

standard and useful tools to be run. So the main task is to find suitable codes to run in

this platform and to put them in production.

The 3D VMEC equilibrium code has been ported to the grid. The strategy is to estimate a

single equilibrium in every node of the grid, changing any characteristic of the

equilibrium, like the pressure or the currents of the device coils. In this way it is possible

to obtain a large data base of configuration with different pressures and currents. As will

be described below, VMEC can be plugged to a Genetic Algorithm to explore the optimum

configurations under some conditions.

FAFNER is a Montecarlo code that studies the plasma heating by NBI. The code has been

ported to the grid using the strategy of following neutral particle trajectories in the

different nodes of the computing grid [ref FAFNER]. FAFNER can be easily plugged to

ISDEP code, thus creating a complex workflow between two grid codes.

DKES (Drift Kinetic Equation Solver) is a standard code to solve the Neoclassical

transport in 3D magnetic devices. This code estimates the mononergetic coefficients

and, from their integrals, it calculates the whole transport matrix. The strategy for

porting DKES to the grid has been to estimate the monoenergetic coefficients at different

cores. DKES has been already ported to the grid and a relevant use case is under

preparation.

III.4.6.4. Exploitation of global Monte Carlo codes in the Grid

All the results presented here based on ISDEP have been obtained by means of

calculations performed in the grid. So the computing grids have revealed as basic tools to

exploit the Global Montecarlo codes in the different Physcis problems to be solved. A

relevant example of these achievements is that the fusion application one of the two was

elected applications that were presented in the Final Review of EGEEII project [ref

FusionDemo].

III.4.6.5. Computation developments: Volunteer Computing for fusion (using

BOINC). Preliminary Simulations of ITER in a Citizen Computer

The middleware BOINC has been used together with other developments to implement

the first citizen computer for different applications. IBERCIVIS, as it is called, has been

deployed in Spain to run several codes [ref CIVICO]. In June 2008 Ibercivis, the new

Spanish Volunteer Computing Platform was presented and launched. It started with three

different applications: protein folding, material science and fusion. The fusion application

is the adaptation of the ISDEP code for calculations in the ITER device. Our target is the



study of the effect of the ripple in the ion transport. We have included a previously

calculated 2D MHD equilibrium in ISDEP, and extended it to a 3D equilibrium introducing

the ripple as a small perturbation. We will solve the neoclassical transport for ITER for

different ripples and compare them. ISDEP is still in production in IBERCIVIS, waiting for

definitive results. Presently, IBERCIVIS has more than 20,000 registered citizens and

about an average of 10,000 CPUs are available high scale distributed calculations.

III.4.6.6. Equilibrium reconstruction, equilibrium criticality and ELM theory at

JET.

The EFIT-f90 code has been developed to include the new iron core model at JET device.

In this way it is possible to perform a detailed reconstruction of the equilibrium based on

multiple diagnostics. The equilibrium reconstruction has allowed us to study the pedestal

at JET [nf8_solano2]. We have continued with the studies of the criticality of the Grad-

Shafranov equation, which includes the study of magnetic phase transitions, including

the situations of current hole in tokamaks like DIII-D [nf8_solano0]. The development of

these studies allowed us to explain the vertical displacement of the strike point of type I

ELMs at JET [nf8_solano1].

III.4.7. Simulation of the ERID of the ITER NBI system

The neutral beam system for ITER consists of two heating and current drive neutral beam

injectors and one diagnostic neutral beam injector, which are directly coupled to the ITER

vacuum vessel. The electrostatic residual ion dump (ERID) represents the reference RID

design for the neutral beam system. This device is composed of five polarized panels of

CuCrZr alloy, whose function is to deflect and dump the residual D- and D+ ions coming

from the neutralizer, in order to prevent them from arriving at the sensitive parts of the

beamline and beam duct. The beam entering the ERID carries a total current of 40 A,

constituted by 60% D0 atoms, and by 20% D- and 20% D+ ions, all having an energy of

1 MeV. Even if the ERID concept shows some advantages with respect to more

conventional magnetic RID designs, nonetheless it presents problematic issues,

concerning, for instance, the power load suffered by the panels, the deuterium recycling

process and the possible formation of a plasma that could affect the ERID deflection

properties. In this respect, the results obtained show that the peak power density should

be lower than 8 MW/m2, which is admissible from a thermo-mechanical point of view.

The simulations concerning the outgassing of deuterium indicate that the gas flow

approaches a saturation level in less than seven minutes, and therefore that the process

tends to reach a steady state within a time comparable with the duration of the foreseen


ITER short pulses (about 400 s). Moreover, the contribution due to the steady-state

outgassing appears to be smaller than the value of the residual background gas. Finally,

the study of the ionization, within the ERID channels, induced by the beam and

secondary electrons strongly suggests that plasma formation is unlikely to occur inside

the ERID, since the estimated ionization density rate is tiny compared to the critical

threshold for plasma production. However, some open issues still remain, such as the

role of the stripped electrons directed toward the ERID channel entrances and the

possible influence of the neutralizer plasma [ref Luca08].

III.5. Development of the stellarator concept

III.5.1.

III.6.1.

Optimization of stellarator configurations

The main target of this task is to search for optimized stellarator configurations

compatible with a blanket, i. e., and compatible with a fusion reactor concept. The first

step is to build computer tools suitable for this exercise. We are working with the grid

version of the VMEC code to estimate the properties of the different configurations. The

VMEC code is plugged with a Genetic Algorithm (GA) that looks for the optimized

configurations estimated on the basis of minimizing target functions. The chromosomes

of the GA are in our case the coefficients of the Fourier series that describe the magnetic

configuration, as calculated by VMEC. A complex workflow has been built in the grid for

these computations. The first target function implemented in the algorithm was the

measurement of the total average perpendicular curvature and grad(B)-drifts. The

implementation of new functions to include more optimization criteria is envisaged. The

next ones are the Mercier criterion of stability and the Ballooning modes stability.

The inclusion of the condition of leaving space between the plasma and the coils to

include a blanket is also studied.

Finally, these calculations, performed in the grid, will be benchmarked with the ones

obtained with the standard code Stellop.

III.6. TJ-II Engineering and Operation

Basic Machine Engineering

III.6.1.1. Introduction

The engineering group of TJ-II carried out a number of tasks for TJ-II, JET, ITER, BA

activities (Cryostat for JT-60SA and RF system for IFMIF) during the year 2008. The

tasks carried out related with the experimental device TJ-II have been dedicated to the

three as usual following aspects:

• -The technical operation and supervision of TJ-II during the plasma operation

• -The maintenance of the machine and auxiliary systems

• -The modifications to improve the performance of the experiments.

III.6.1.2. Technical operation of the TJ-II

The technical operation of the TJ-II is carried out by an engineer of the group. He is in

charge of the surveillance of all the parameters of the experimental device and all the

auxiliary systems except the power supply. Other engineer is in charge of the power

supply with the responsibility of implement the currents in the coils, the surveillance of

the pulse generator, transformers and rectifiers, etc. The operation of the machine in

“Mode C” to vary the rotational transform during the plasma pulses has been tested

during the year with promising results.

The incidences occurred during the operations are documented in the operation books of

the TJ-II. Two of them for each year are filled. [ENG1]

III.6.1.3. Maintenance tasks

The maintenance and inspection tasks during 2008 have been the following:

• Cooling System: only the periodic checking was carried out in the cooling plant and

its main components (special attention to the cleaning of the filters in the cooling

tower and the main circuits of the cooling plant). Outside the plant a few flow-meters

in the Toroidal Field Coil circuits were required to be changed due to the blocking

problem in the rotary elements of the instrument.

• Cranes bridges: the elements installed in the different buildings related with TJ-II

facility and other parts of the Fusion Laboratory have been reviewed as usual. No

special problem is worth to be remarked.

• Control System: the maintenance of the different Control Systems of the TJ-II has

been performed. Periodic checks were made and some preventive maintenance tasks

were conducted through, as e.g. calibration and test of the whole system channels,

and repairing damage channels.


• Power supply: the maintenance was carried out in August with no incidences and at

the same time an important modification of the lubrication system was done as

described hereafter.

III.6.1.4. Power supply

The pulse generator is resting on two bearings, one of them in the coupling side to the

pony motor. From the beginning some difference in the temperature of operation was

observed. Due to the increasing of the performance of the machine, during continuous

operation mode of the motor-generator, a big difference between temperatures of two

bearing was observed. The measurements of the oil flow in the different part of the

lubrication system show that not all quantity of the oil delivered by the pump comes into

the bearings but the part of it enter into the branch pipe. The difference of the oil flow in

the bearings results on a larger temperature difference. It was decided to install two

check valves in order to equalize the flow in the both inlets. This work has been done in

August of 2008 and presently the temperature difference is not far away 3ºC between

the two bearings.

III.6.1.5. Control system

The activities in relation to the TJ-II Control System during the year 2008 have been

concentrated mainly in the system upgrade and especially in the tasks related to

translate the old code from OS-9 to VxWorks, the new real time operating system that

has been chosen for the TJ-II Control System and will be installed in different steps. In

the meantime the maintenance of the present system in operation has been carried out

regularly. The main works during the year 2008 have been the following ones:

a) The TJ-II operation in C mode.

The new mode of operation, Mode C, is now fully functional. There have been numerous

tests to refine its features and to improve their functionality. A new protection has been

added to this mode of operation in order to avoid mechanical vibrations of the whole

experiment during the fast ramp down of the coil currents when the pulse fails suddenly.

The real-time algorithm produces a controlled current ramp-down in case of failure in any

rectifier [ENG2].

b) Update of the control system

Continuing with the tasks for updating the Control System of TJ-II, almost all the

software for the Fast Control System has been rewritten and tested. The old version,

written in OS9, has been ported to the new operating system VxWorks.


The strategy for the renovation of the entire Control System is to gradually replace each

of the subsystems. This fact forces the coexistence of different operating systems in the

same network.

A new communication middleware architecture called XML-based Messages Distribution

Service (X-MDS) has been developed for the TJ-II Control System. X-MDS has been

designed to exchange and distribute information such as commands, status and data

among heterogeneous systems. The middleware permits easy communication between

distributed control applications that run on different real-time operating systems (OS9

and VxWorks for the TJ-II environment) and Java-based applications running on any

Windows or Linux platform.

X-MDS is configured for each system by means of three XML-based configuration files

which are stored on a network disk.

Specific software tools have been developed to create control variables and generate

easily configuration files. No low-level network programming for applications

development is needed. The middleware provides libraries to manage both

communication models. It supports the C programming language for both OS9 and

VxWorks real-time operating systems. Also it provides APIs to read, write, and

manipulate XML-based data stream from Java code. It is based on a parser independent

Java API named JDOM (Open source with an Apache-like license).

The communication middleware architecture (X-MDS) has been fully tested and found to

be both, reliable and safe. It will be applied to the new TJ-II Control System based on the

VxWorks operating system and Java-based graphical user interfaces.

For graphical user interfaces we have developed a Java application, which will act as

main console of the TJ-II Control System.

In order to ensure the security of the Control System and to increase the bandwidth, we

have installed a VLAN that isolate the Control Systems from the broadcast traffic. In

addition, some communications problems have been resolved after detecting a bug in the

original MVME167 BSP Ethernet drivers from OS9.

Reboot problems have been solved by means of an optic link between the main Control

Room and the Ground Loop System, which is located far away from the main Control

Room.

c) TV surveillance system

The TJ-II implemented from the very beginning a TV surveillance system. The number of

TV cameras in the system has been increased by installing a set of three additional



cameras, two cameras to view the two NBI injectors, and another one in the high voltage

area of the NBI power supplies.

[ENG1]: Diarios de Operación TJ-II (not available in electronic form)

III.6.2. Operation of TJ-II

Plasma operation activity in TJ-II during 2008 was organized in two experimental

campaigns. The spring campaign proceeded between 19 February and 26 June, with 40

days of operation and 1601 shots. The autumn campaign took place between 28 October

and 18 December with 20 days of operation and 868 shots. The main remarks that must

be mentioned as regards TJ-II operation in 2008 are:

a) The new ECH high voltage power supply (HVPS) -installed and commissioned in 2007-

has worked very reliably. It allows routine and steady ECH plasma operation at the

maximum available power of 600 kW (two gyrotrons, 53,2 GHz, 2nd harmonic, X mode,

300 kW each). A new high voltage filter was installed at the HVPS in September and an

output ripple around 1 % was been finally obtained

b) The co-NBI injector has continued performing with stable mode of operation at 31 kV,

60 A, voltage and current levels, respectively, with pulse length up to 130 ms. These

beam parameters correspond to a port-through injected power into the TJ-II vessel of

about 450 kW.

c) The counter-NBI injector has reached a steady operation condition in May 2008. It has

been operated since then at 31 kV, 55 A, 450 kW port-through injected power.

d) Preparatory work on the EBW heating system has proceeded along the year. After

detailed calculations and specifications preparation a contract for a new 28 GHz gyrotron

was placed. The transmission waveguide, polarizers and mirrors were successfully

installed. A new modulator to allow independent operation of ECH and EBW gyrotrons

(collaboration with IPP Greifswald and IPF Stuttgart) was installed and commissioned.

e) Li coating by vacuum evaporation has been routinely used as plasma wall conditioning

technique. The lithiumization process was repeated four times along the spring campaign

(18 February, 24 March, 19 may and 24 June) ant three times during the autumn

campaign (28 October, 10 November and 2 December). This procedure has allowed TJ-II

to enter in a more relevant NBI operation domain, with much lower recycling, improved

density control and improved confinement. H-mode discharges have been obtained since

June 2008.

A summary of the experimental sessions performed, along with the number of shots

allocated to each experiment/activity, is listed below:

• Start-up, commissioning of control and data acquisition systems and diagnostics: two

sessions, 34 shots

• ECRH studies: calibration, power deposition profile (modulation) and ECCD

experiments: 2.5 sessions, 99 shots

• NBI plasmas in H and He (experiments devoted to optimize the coupling of the

neutral beam to the ECH target plasma: working gas, ECH providing on/off axis

heating, electrode biasing, characterization after lithium coating): fifteen sessions,

544 shots

• Rotational transform and plasma volume scan in NBI plasmas: eight sessions, 311

shots

• Impurity transport in NBI plasmas. Evolution of radiation profiles driven by external

puff: three session, 120 shots

• Alfven activity in NBI plasmas: four sessions, 172 shots

• Studies of critical density for plasma rotation and shear flow in ECH plasmas: three

sessions, 141 shots

• Dynamic configuration scan in ECH plasmas: two sessions, 72 shots

• Core-edge coupling in ECH plasmas: 1 session, 39 shots

• Transport studies using cold pulse propagation: 1 session, 34 shots

• 2D visualization of turbulence with fast cameras: 2 sessions, 69 shots

• Characterization of ECH plasmas in inverted magnetic field configuration: 5 sessions,

149 shots

• Characterization of NBI plasmas in inverted magnetic field configuration: 2.5

sessions, 94 shots

• Electrode biasing and electric fields: two sessions, 82 shots

• Impurity transport in NBI plasmas. Blow-off impurity injection: 1 session, 50 shots

• Studies of causality between potential, flux and temperature: 1 session, 30 shots

• Asymmetries in the CX-neutrals flux: 2 sessions, 79 shots

• Test of diagnostics: 3 sessions, 138 shots

III.6.2.1. ECRH system routine operation and improvements

• 53.2 GHz ECRH system


The ECRH system of the TJ-II stellarator consists of two triode-53.2 GHz-gyrotrons which

can deliver a maximum power of 300 kW each during 1s. Both gyrotrons are fed by a

high voltage power supply (HVPS) that was installed in April 2007. Each gyrotron is

controlled by an anode modulator. After the installation of the new HVPS the

performance of the gyrotrons and the reliability of the ECRH system have been clearly

improved in respect to previous campaigns [ECRH1]. In approximately 2200 TJ-II shots,

only 3 of them were lost due to a failure in the HVPS. Most of the specifications were

demonstrated during the final acceptance tests, except the level of the required output

voltage ripple which was found to be 2.5 % peak to peak ripple whereas 1 % was initially

demanded. This problem has been solved in September 2008 by the installation of a new

high voltage filter and an output ripple around 1 % has been finally obtained. Other

general tasks concerning the modification of the internal mirrors design and other

improvements in the system were accomplished. More details are given in the following.

• High power filter

The filter is made-up of 50 identical modules serial connected. Each of these modules is

composed by power resistors, one capacity component and one IGBT. Moreover, each

module is fed independently by a 1 W solar panel illuminated by a 100 W lamp in order

to achieve perfect electric isolation and to eliminate the parasitic capacities between the

different modules as well as between the modules and the ground.

• Internal mirror design modification

The power emitted by both gyrotrons is driven to the TJ-II vessel by means of two quasi-

optical transmission lines. The last mirror of each line is a steerable mirror located inside

the vacuum vessel. In July 2008, during the summer maintenance period, some parts of

the hardware related with the movement of the mirrors were improved. After their

mandatory recalibration, the two internal mirrors were successfully reinstalled inside the

vessel.

• General maintenance and improvements tasks

The main tasks concerning the improvement and the maintenance of the ECRH system

that were carried out during 2008 are:

• Maintenance works on the microwave energy measurement device (MEMD) needed

for the calorimetric measurements of the power generated by both gyrotrons. This


work has been carried out in the frame of the collaboration with PLASMA IOFAN

Science and Technology Center, Moscow, Russia (Ref. 07/302).

• Remote control of the gyrotron ionic pumps.

• Complete reorganization and improvement of the whole fibre optics wiring of the

ECRH control system.

• Preparation of the optical fibre connection from the Bernstein system inside the TJ-II

hall to the ECRH control room.

• Building of a data base containing all the information of the control system wiring.

• Improvement of the microwave laboratory capabilities, including manufacturing of

printed circuit boards and microcontroller programming.

• Improvements in IR diagnostics to measure the properties of a Gaussian

beam

The determination of the structure of a microwave beam by means of an infrared camera

has been improved with experiments in different highly anisotropic materials. The

anisotropy of the target material in the perpendicular and parallel directions allows us to

minimize the heat transport effects and thus we may obtain a picture of the beam

directly related to the power deposition zone within the target. In particular, a graphite

target has been tested and good results have been obtained. The remote control system

of the camera and the treatment of data, including the reconstruction of the beam from

different viewing angles, have also been improved.

• Design of a new quasi-optical transmission line

One of the quasi-optical transmission lines of the 53.2 GHz ECRH system (QTL2) is an old

line with only linear polarization capabilities, non controllable by remote means, and non

optimized mirrors. A new design of the whole line is underway. The following features will

be considered in the new design:

• Remotely controlled universal polarization

• Specifically designed mirrors for optimum beam transmission

• Possibility of changing the beam waist and focus position inside the plasma within the

range allowed by the TJ-II vacuum vessel restrictions

• Monitors for absolute power and polarization measurements


• ECCD experiments

After the ECCD investigations carried out in 2007, field reversal experiments were

conducted. The field reversal experiments, that were performed with the aim of

distinguish clearly the bootstrap current contribution from the ECCD contribution, were

not conclusive. The operation of TJ-II with reversed magnetic field lasted only one month

and it was found to be more complicated than expected from the point of view of plasma

performance.

• Influence of the controlled modulated power reflected back to the gyrotron.

It was demonstrated in previous experiments that a low fraction of the gyrotron emitted

power reflected back to the source (modulated with a thin oscillatory metallic foil) can

modify the its behaviour and produce a reaction on the output radiation, in particular

power modulation and frequency changes. During 2008, further studies were performed

[ECRH3]. In short, different delays between the starting of the microwaves generation

and the starting of the metallic foil oscillations were explored paying attention to the

gyrotron reaction. Moreover, the gyrotron power was modified and the consequent slight

change in the frequency of the output radiation was determined using this method.

This work has been carried out in collaboration with the Institute of Applied Physics

(Russian Academy of Science), Moscow and Nizhny Novgorod (Russia).

III.6.2.2. Activities on Electronics for TJ-II diagnostics

The following activities have been carried out during 2008 in support of diagnostic

development of TJ-II:

• Automation of the Doppler Reflectometer control system for the single-axis

movement with drivers. Two main innovations have been implemented in this

system: a) a combinational logic that detects which optical barrier is activated and b)

the positioning system is based on optical barriers instead of microruptors.

• Design, implementation and assembly of the three-phase 1KW/1KV/1A Power Supply

of for the Glow Discharge system.

• Development of a ballast system for the Glow Discharge cleaning which regulates

automatically the input current.



• Optical fiber System Selector for the source trigger of the California Limiters (Three

Phase Power Generator) implementing the trigger system by means of fibre optics

and a selector that disconnects the system in case of any failing condition.

• Automation and control design of the Berstein wave heating system mirrors with

EPOS Driver and control system.

III.6.2.3. Development of a new event-oriented database

A new database for storing data related to the TJ-II experiment has been designed and

implemented. It allows the storage of raw data not acquired during plasma shots, i.e.

data collected continuously or between plasma discharges while testing subsystems (e.g.

during conditioning pulses of the neutral beam system) (EVENT_1).

IV. EMERGING TECHNOLOGIES

IV.1. Development of material science and advanced

materials for DEMO

IV.1.1. Physics integration (Ceramic insulators): Study of

radiation induced electrical currents for hydrogen

isotopes and helium at low residual pressure and effect

on insulating surfaces.

IV.1.1.1. Evaluation of behaviour of silica glasses

Silica will be used in ITER and beyond in optical components and also potentially as an

electrical insulator in different heating and diagnostic systems. The material will be

subjected not only to neutron and gamma irradiation, but also to particle bombardment,

due mainly to ionization of the residual gas and acceleration of the resulting ions by local

electric fields. Hence the insulators in a fusion reactor will be subjected to a wide energy

spectrum of ion bombardment ranging from ≤ keV up to MeV. As a consequence of this

hostile environment severe electrical and optical degradation may be expected. Previous

work has shown that the vacuum face of not only silica, but also other candidate

insulators for fusion applications, rapidly degrade when subjected to bombardment by

protons and alpha particles with energies from 27 to 900 keV . Such vacuum surface


degradation was also observed to occur after 1.8 MeV electron irradiation. This type of

surface degradation was shown to be due to loss of oxygen caused by radiolytic

preferential sputtering. The aim of the work is to extend the study of this type of

degradation to lower energies, where the ion implantation is even more superficial.

KS-4V samples were implanted at 13 ºC with He ions from 5 to 21 keV, producing very

narrow near-surface He implanted profiles. The evolution of the surface electrical

conductivity was measured in-situ for different doses. After implantation SEM X-ray

analysis of the implanted surface was performed to check for oxygen loss, and optical

absorption measurements were carried out to evaluate the optical degradation. The

results show that surface degradation occurs more rapidly for the lowest energy (5 keV)

ions, indicating that the superficial narrow implanted He profile must play an important

role in the surface degradation, the process being both accelerated and apparently

enhanced by the presence of a high density of He near the surface (ref Eval_1).

IV.1.2. Physics integration (Ceramic insulators): To

characterize and assess the behaviour of insulating

materials and components during irradiation for

applications in H&CD, and diagnostics.

IV.1.2.1. Evaluation of new types of glasses (Na based)

The glass samples were provided by SCK-CEN and the nominal composition of both types

of glasses in weight percentage was 75%SiO2 22%Na 3%CaO. One of the types was

0.05% Cerium doped meanwhile the other type was undoped. The two types, Ce doped

and undoped, materials have been studied in terms of radioluminescence,

photoluminescence and radiation induced optical absorption. The two materials studied

exhibit very high sensitivity to radiation in terms of optical absorption and

radioluminescence. Particularly the radiation induced optical absorption reaches values of

the order of 10 cm-1 in optical density after only 50 kGy at 15 C. In order to anneal the

coloration during irradiation the temperature of the glass has to be increased up to 200

C The radioluminescence for both types of glasses is higher than in the case of KU1

quartz glass and Ce-doped type of glass exhibit high photoluminescence. KU1 quartz

glass demonstrates to be far superior to the special glasses studied in terms of both

optical absorption and radioluminescence.

IV.1.2.2. Characterization of gamma irradiated silica (optical absorption and

photoluminescence)

The effects of neutron (1021 -1022 n/m2 fluences) and gamma irradiation (23,8 MGy dose)

on the IR-Vis-UV optical absorption spectra of high purity silica with different OH

content: KU1 (~ 820 ppm) and KS-4V (< 0.2 ppm) , and commercial silica Infrasil 301

(< 8 ppm) have been compared (ref GNIS_1). The results show that the UV-vis optical

degradation of the silica, after neutron irradiation at the highest fluence is similar for the

three grades studied, while gamma induced optical absorption depends on the material

grade (KS-4V shows the lowest optical absorption). The effects of both types of radiation

on the IR band related with the hydroxyl group (3650 cm-1) depend on the silica grade.

For KU1, the shape of this band changes with neutron fluence, (the height decreases and

its position shifts to lower energies). For Infrasil 301 gamma and neutron irradiated, this

band height increases, possibly due to free molecular or hydrogen atoms. The shift to

lower energies observed for the 2260 cm-1 band in the three neutron irradiated silica

grades, reflects the changes induced by neutrons in the lattice bonding angle distribution.

Also electron paramagnetic resonance (EPR) studies were carried out on KU1 silica

irradiated with neutrons (1021 and 1022 n/m2), and gamma-ray up to 12 MGy dose

(ref.GNIS_2).

The post-irradiation isochronal annealing up to 850ºC of KU1 and KS-4V silica grades

gamma irradiated up to 11.6 MGy under identical conditions, together with five

commercial types of silica (natural and synthetic) with different OH and impurity contents

have been carried out. After each annealing temperature the optical absorption of the

different grades has been obtained. The general effect of the isochronal annealing is a

decrease in the optical absorption bands as the temperature increases. Optical absorption

bands have been identified with known defects from the literature or impurities, and their

concentration-temperature dependence is being analyzed, The results obtained allow one

to predict the behaviour of the transmission properties for different types of silica over a

wide temperature range.

The temperature dependence from 300K to 10K of the photoluminescence induced at 2.7

eV by ultraviolet (UV) and vacuum ultraviolet (VUV) excitation of neutron irradiated

(1021 n/m2 and 1022 n/m2 fluences) KU1 and KS-4V silica and commercial silica Infrasil

301 has been studied (ref GNIS_3). At the highest neutron fluence and at the same

temperature, the three irradiated silica grades show similar excitation spectra. An

excitation band at 4.8 eV, related to the triplet-singlet transition in SiODCs(II) ,

decreases on decreasing temperature from 300 to 10K and an excitation band at 5.1 eV,

probably related to SiODCs(I), is observed only at very low temperatures (~ 10K). An

important VUV excitation structure, observed at low temperature, could also be related to

SiODCs(I). A shift of the irradiated bands is detected at low temperature.


Photoluminescence measurements were made using synchrotron radiation in the

SUPERLUMI station at DESY (Hamburg).

IV.1.2.3. Radiation bolometer development

High temperature bolometers fabricated with thin ceramic substrates as the foil with a

platinum meander sensor and absorber has been analysed in terms of their temperature

behaviour and radiation tolerance. Alumina and aluminium nitride were examined due to

their adequate thermal and dielectric properties. Using platinum instead of gold as metal

sensor will present reduced transmutation problems. Al2O3 and AlN bolometers were

electron irradiated at 203 and 450 ºC with ionizing dose rates up to 200 Gy/s to total

doses of about 8 and 11 MGy, respectively. Electrical resistance variations lower than 1

% over periods of time far greater than one ITER shot can be well suited. But during

radiation testing such prototype devices suffered from loss of electrical connection.

During 2008, research was devoted to develop new bolometer configurations with special

attention to attain more robust electrical contacts. To improve stability and reliability of

the bolometer electrical contacts, new sensor designs and modifications of the meander

terminals were achieved. Proposed designs mean the need of electrical connections

between a delicate sensor and a basic robust connector. However due to the harsh fusion

environment, standard techniques such as those used in microelectronics packaging are

inadequate. To address this problem, the possibility of laser welding electrically

conducting miniature binding posts with attached platinum wires to delicate insulating

substrates, has been examined. Within SCK•CEN collaboration (ref SOFT08_ERH), the

use of 1 mm diameter Pt binding posts filled with soda-silica-lime low melting

temperature glass were proposed to provide connectors of proper adhesion to the

substrate. Trial tests were carried out to weld these kind of posts to Pt sensor tracks

sputtered onto 80 µm thick alumina and aluminium nitride substrates using an industrial

Nd:YAG laser. Initial results for these simple configurations electron irradiated in vacuum

at high temperature, show that the technique provides a strong and reliable low

resistance electrical connection. Suitable prototypes have now been prepared, and are

being loaded into a vacuum capsule ready for in-reactor (BR2) testing at SCK-CEN, Mol.

IV.1.2.4. Mirrors characterization

Different types of dielectric coated mirrors have been tested. They include standard

visible to IR, UV enhanced, and multilayer enhanced narrow range (“cold”) mirrors. The

radiation resistance observed for all the mirrors tested has been good, with no marked

degradation following gamma irradiation up to doses of 60 MGy at 170ºC in dry nitrogen

atmosphere. Also for some mirrors, irradiation tests up to 13 MGy in humid air at 170ºC



were carried out showing good response and corrosion protection. The main problem is

the discrepancy found between manufacturers specifications and measured values of

reflectivity and overcoating material. (ref Mirr 1)

The degradation of the reflectivity for mirrors made from various steels subjected to

ionizing radiation, at moderate temperature and in different environments (vacuum, air,

nitrogen) up to a total dose of 9 MGy, has been examined. Mirrors were prepared from

conventional austenitic stainless steel (316L) and reduced activation ferritic/martensitic

steels (Eurofer, ODS-Eurofer, F82H). The reflectivity was studied from UV to near IR,

before and after different treatments. For the reduced activation steels important

reflectivity degradation for wavelengths below 1000 nm are observed for the different

conditions. The austenitic steel mirrors only degrade slightly under all conditions.

Surface morphology and microstructure has been also investigated using scanning

electron microscopy. (ref Mirr 2).

IV.1.2.5. Window assemblies and seals, radiation enhanced T diffusion

Different window assemblies will be mounted in an special irradiation chamber mounted

at the end of the beam line of a Van de Graaff accelerator The experimental system

developed to measure the radiation induced diffusion of H, D, and He has been improved

in order to fit 6 simplified window assemblies. One face of the window assembly is in

vacuum and exposed to a 1.8 MeV electron beam meanwhile the other face was

subjected to pressurized hydrogen, deuterium or helium. Gas leakage through the

window assembly during irradiation will be measured with a helium/hydrogen leak

detector. Optical absorption measurements will be carried out before and after

irradiation. Once irradiated the gas chamber pressure will be increased up to 3 bars in

order to check mechanical failure of the assemblies. The window assemblies have been

already produced at UKAEA and will be shipped to CIEMAT during 2009. Such window

assemblies consist of sapphire with edge brazed AuCu bond on titanium, fused silica, with

Al-diffusion bond on tantalum, crystal quartz with Al-diffusion bond on 316 stainless

steel, silicon nitride with Al-diffusion bond on titanium, silicon nitride with Al-diffusion

bond on titanium, and fused silica with a eutectic braze (lead-silver compound) welded

on 316 stainless steel.

IV.1.3. Long term structural materials: For experimental ODS

steels evaluate the fabrication route, specially heat

treatments after consolidation, in the metallurgical


properties of this steel as possible structural material

for fusion devices

IV.1.3.1. Feasibility studies for the production of nanostructured ODS steels

The microstructural characterization of Fe-12 wt% Cr alloys, ODS with 0.4 wt% Y2O3 non

ODS, both produced by mechanical alloying followed by hot isostatic pressing (HIP), was

accomplished [ref ODSFeCr1]. The results revealed the presence of lath martensite, and

M3C and M23C6 carbides, as a consequence of C-intake during the milling process. An

intra-granular dispersion of Y2O3 nanoparticles was observed in ODS Fe-12Cr. These

nanoparticles were also found associated to the carbide particle or on grain boundaries.

Small voids with sizes <10 nm were found associated to the ODS nanoparticles [ref

ODSEuro1 and ref ODSEuro2]. The results obtained in these materials suggested the

need of optimizing the mechanical alloying conditions to reduce the contamination by C

and formation of voids in the consolidated material.

Fe-14wt%Cr-0.3 and Fe-14wt%Cr-0.3wt%Y2O3 alloys have been produced by mechanical

alloying under different atmospheres (He and H) followed by hot isostatic pressing (HIP)

consolidation for 1 h at 1300 K under a pressure of 200 MPa. After consolidation the

materials has been forged at ∼ 1000 K and 1100K, respectively. The microstructural of

these materials: grain structure, characteristics of oxide particle dispersion and thermal

stability have been investigated by High Resolution Transmission Electron Microscopy

(HR-TEM). Ingots of these materials to be processed by equal channel angular pressing

(ECAP) and characterized by tensile tests have been prepared.

IV.1.4. Long term structural materials: To work on mechanical

and microstructural characterization of Eurofer ODS

steels

Samples EUROFER steel with dimensions 12×12×65 mm3 have been subjected to equal

channel angular pressing (ECAP) at a temperature of 550 ºC up through a die with an

intersection angle of 105º. The texture and microstructural analyses of the ECAP

processed samples by different routes and number of passes have been performed using

X ray, and optical and transmission electron microscopy. The ECAP effect on the

mechanical characteristics have been investigated by means of tensile and Charpy impact

tests, and microhardness measurements. The results of the microstructural analyses

have shown that an equiaxed submicron-grained structure can be obtained in EUROFER


after four passes. However, the preliminary mechanical tests do not show an

improvement in tensile properties as high as the one predicted by the grain refinement

produced by the ECAP processing in comparison with the material in as-received

conditions.

IV.1.5. Long term structural materials: For experimental W

alloys evaluate the fabrication route in the metallurgical

properties of this steel as possible structural material

for fusion devices

IV.1.5.1. Feasibility study for the production of W alloys with reduced

oxidation properties

The role played by the microstructure, and the influence of the oxidation in the

mechanical behaviour of W and W-Ti-Y2O3 has been studied in the temperature range 20-

1000 ºC. It was found that Y2O3 improved the high temperature properties by inhibiting

oxidation. The strength and toughness retention of W-Y2O3 was much better than pure W

above 400ºC due to the strong reduction of the oxidation rates induced by the Y2O3

dispersion. The W-Ti alloys presented the highest strength, toughness and hardness from

ambient temperature up to ∼800 ºC. Above ∼600 º C, the mechanical properties of the

W-Ti alloy decreased rapidly due to oxidation and were below those of W-Y2O3 at 1000ºC

(ref ODSW2).

The La2O3 dispersion effect on the oxidation resistance of W-V-La2O3 alloys prepared by

powder metallurgy is being evaluated between room temperature and 1500 ºC.

IV.1.5.2. Feasibility study for the production of nanostructured W

The mechanical behaviour of pure W, W-0.5 wt. % Y2O3 and W- 4wt.% Ti manufactured

by powder metallurgy was studied from ambient temperature to 1000ºC (ref ODSW2).

The microstructural and compositional characteristic of these materials are reported in

(ref ODSW1). Strength and toughness was measured from the three-point bend tests in

smooth and notched prismatic bars. The dominant deformation and failure

micromechanisms were assessed as a function of temperature for each material through

the analysis of the fracture surfaces and transverse cross-sections in the scanning

electron microscope. Ti acted as a sintering activator and the W-Ti alloy was fully dense

and presented smaller grain size. Both factors enhanced the mechanical properties at

ambient and intermediate temperatures but the ductile-to-brittle transition temperature

of this material was higher, leading to brittle behaviour up to very high temperature.


Small laboratory scale batches of W, W-V and W-V-La2O3 have been produced by

mechanical alloying and consolidation by hot isostatic pressing (HIP). La2O3 dispersion

can improve the mechanical strength and increase the recrystallization temperature of W,

although the decrease of the DBTT has not been reported in the literature. The

microstructural, compositional and wear characteristics of these materials have been

investigated. The aim of the present work is to produce W and W-V alloys reinforced with

La2O3 and investigate their microstructure and thermal stability in order to obtain a

structural material with favorable properties to be used for developing plasma-facing

components. W alloys having 1 wt % La2O3 and (0 − 4) wt % V have been prepared by

mechanical alloying and consolidated by hot isostatic pressing at 1573 K for 2 h under a

pressure of 200 MPa. The microstructural analyses of the alloys have been performed

using optical and electron microscopy and X-ray diffraction measurements. The results

show that fully dense alloys with V dissolved in the W lattice can be obtained. The

thermal stability and recrystallization characteristics of the alloys are being investigated.

Samples of these materials have been delivered to perform mechanical tests by the

ESTRUMAT.

IV.1.6. Long term structural materials: To work on mechanical

and microstructural characterization of W alloys

IV.1.6.1. Microstructural characterization of the produced W alloys

The mechanical behavior of polycrystalline W, W- Y2O3 (0.5 wt. %) and W-Ti (4 wt. %)

manufactured by powder metallurgy (ref UPM-1 and ref UPM-2) was studied from

ambient temperature to 1000 ºC. Y2O3 nanoparticles were added to refine grain growth

and improve oxidation resistance, while Ti is a sintering activator. Strength and

toughness was measured from the three-point bend tests in smooth and notched

prismatic bars. Pure W was brittle below 400 ºC and the dominant fracture mechanisms

were intergranular cracking and cleavage of large W grains. Plastic deformation was

observed at 400 ºC and above, and contributed to improving the strength and

toughness, which were maximum at 400 ºC. Nevertheless, oxidation of W very rapidly

degraded the mechanical behavior above 600 ºC.

The dominant deformation and failure micromechanisms were assessed as a function of

temperature for each material through the analysis of the fracture surfaces and

transverse cross-sections in the scanning electron microscope. The addition of Y2O3

nanoparticles did not substantially change the microstructure of the material. The

nanoparticles were not well dispersed and, in addition, led to the formation of a complex

W-Y eutectic oxide which was fused during sintering. Both factors limited the potential of


the oxide dispersion to inhibit grain growth and porosity and average grain size were

very similar in W and W- Y2O3.

The role played by microstructure (porosity, grain size distribution), dominant failure

mechanisms (intergranular cracking and cleavage of large W grains below the ductile-

brittle transition temperature combined by plastic deformation above this temperature)

and oxidation rates in mechanical behavior were elucidated for each material in the

whole temperature range. It was found that Y2O3 improved the high temperature

properties by inhibiting oxidation. Ti acted as a sintering activator and the W-Ti alloy was

fully dense and presented smaller grain size. Both factors enhanced the mechanical

properties at ambient and intermediate temperatures but the ductile-to-brittle transition

temperature of this material was higher, leading to brittle behavior up to very high

temperature.

IV.1.7. Characterization of SiC materials for DEMO

IV.1.7.1. Measurement of electrical properties

Silicon carbide materials (SiC and SiCf/SiC) are considered as potential long term reduced

activation structural materials, as well as possible flow channel inserts in Li-Pb tritium

breeding blanket modules. Studies of silicon carbide based ceramic composites for

applications in fusion have been carried out for more than ten years, and although

understanding of the basic radiation damage processes as well as microstructural

evolution has shown significant advances, considerable further work is required to fully

understand the physical mechanisms and varied irradiation effects for the different forms

of SiC and SiCf/SiC

Work has begun at CIEMAT on hot pressed (HP) SiC. Results for radiation induced

degradation of the electrical conductivity, show almost an order of magnitude decrease in

the volume conductivity for electron irradiation in high vacuum to 420 MGy at 450 ºC. In

contrast surface conductivity markedly increases after both electron irradiation and 50

keV He bombardment (implantation). Following He bombardment surface amorphization

is observed, but of more concern is the unexpected amorphization of SiC within the

volume after electron irradiation to low dose, and at moderate temperature (ref Eval_2).

IV.2. Materials modelling


IV.2.1.

IV.2.2.

Long term structural materials: Modelling, continue to

support this activity for steels (Fe), insulators and SiC

Experiments for modelling validation: He desorption in

Fe and other model materials

IV.2.2.1. Feasibility study to make desorption measurements

A Rate Theory model was developed to predict the evolution of He and its interactions

with carbon impurities in irradiated bcc-Fe. The parameters of the model were primarily

based on ab initio calculations, i.e. the parameters were not obtained from fits to

experimental results. Taking explicitly into account the formation of He-V-C complexes,

this rate theory model is able to naturally reproduce the different stages of existing He

desorption experimental results (ref. HEMOD_1), with all parameters for reactions being

obtained from first-principle calculations. In order to test the validity of the model and

find optimal experimental conditions to evidence the role of carbon, the desorption of He

was simulated under different conditions using the rate theory model. We studied the

desorption of He from bcc-Fe containing C for an homogeneous He profile, the initial He

concentration varying from 0.1 to 10 at.ppm, for carbon concentrations ranging from 0 to

50 wt.ppm, and during isothermal annealing for temperatures between 473 K and 773 K.

We also studied the He desorption under ramp annealing for a He concentration of 0.1

at.ppm, various C concentrations and for a ramp rate of 10 K/min.

Results obtained with isothermal annealings

For an initial He concentration of 0.1 at.ppm and for a temperature of 573 K a clear

difference is expected to be observed in the desorption curves, in particular for high

carbon concentrations (higher than 100 at.ppm). Carbon seems to enhance He

desorption rate in these conditions. A detailed analysis revealed that this is due to the

formation of VC and VC2 complexes that trap most vacancies generated during

irradiation at room temperature. This strongly reduces the migration of vacancies and

hence inhibits the formation of higher order and more stable HenVm clusters.

The other conditions that were explored in this study did not show significant differences

in the desorption curves. This can be easily explained. On one hand, when the initial

concentration of vacancies is significantly higher than the carbon one, i.e. for high

implanted He concentrations, the number of vacancies that is trapped into VC and VC2

clusters is relatively small. Therefore, for high V/C ratios, the migration of vacancies is


barely affected and consequently He desorption is almost not influenced by the presence

of carbon. On the other hand, when the temperature is relatively high (about 673 K and

higher) carbon complexes that form, even when the V/C ratios is low, dissolve rapidly

and thus barely affect the He kinetics.

In conclusion, for an initial homogeneous implanted He profile, the experimental

conditions to evidence the carbon influence on He desorption seems to be optimal for a

temperature of about 573 K and for a low initial V concentration in comparison to the

carbon concentration (low V/C ratio), i.e. for a low He concentration.

Preliminary results obtained with ramp annealings

The flux of He emitted from Fe containing different carbon concentrations was also

studied in the case of a ramp annealing of 10 K/min. As a first case, He diffusion was

simulated for a He content of 0.1 at.ppm and carbon concentrations ranging from 0 to 50

wt.ppm. Simulations show that when carbon is present, in particular at high

concentration, different peaks clearly appear in the structure of the He flux, in

comparison to the case of pure Fe. A peak centred at T~400 K exhibits a difference in

amplitude of about one order of magnitude between the flux obtained in the case of pure

Fe and the one obtained with 50 wt.ppm carbon content. Simulations with different ramp

rates and other He contents are in progress.

IV.3. Techniques for controlling tritium inventory,

fuel cycle

IV.3.1. Tritium Breeding and materials (breeding blanket): To

demonstrate and visualize by a well founded ab-initio

simulation of the He/Li system, the tendency of He

atoms in Li to cluster into bubbles

Helium bubble nucleation in liquid metal and analysis of its impact on design on Li/LiPb

liquid metal Fusion technology systems (IFMIF target, breeding blanket channel analyses,

LM first wall concepts) represents a genuine, pioneer and singular contribution of Spanish

fusion technology groups. During the last years the CIEMAT work has established the

significance of He bubble production in NFT breeding systems. Main conclusions for FT

systems under study are summarized hereafter.

As is today well established, Helium bubbles exist in LM breeding systems and have a

major impact on NFT designs, in particular on tritium transport along LM BB channels.

For the role of helium at IFMIF Li-jet target the main underlying question is related with

the possible helium bubble nucleation within the Li-jet residence time in the target.

Precise quantitative answer to this question was provided by the comparison of

characteristic times of He-nucleation rates (clustering rates for stable He-clusters in Li)

with Li residence time in IFMIF target stripping surface. Characteristic times for helium

clustering (bubble nucleation) under helium supersaturated conditions in lithium was

assessed by adapting Continuum Scale Nucleation Models in Solids developed for 3He/tritides to He in Li. This adaptation represents a genuine contribution. This

adaptation was fundamentally well supported by quasi-crystalline nature of alkali liquids

and certitude on the order of magnitude in this minimum kinetic time can be reasonably

assumed. The residence time of 15 m/s Li-jet in the breeding area (length: L ~ 25 cm,

assuming plate curvature) stripping target is also within the range of tenth ms (roughly

20 ms). Assessment of nucleation kinetics drives to slightly lower values of clustering

characteristic times. In this sense, with a large probability, the He bubbles are formed

out of stripping target in the concave plate and then with no major impact on target

performances. Bubbles nucleating in the bottom part of the concave plate of IFMIF target

would impact Li-jet hydrodynamic stability (Li jet versus Li-jet plus Helium bubbles) and

must be considered for future (not present, other stability analyses are preferential) CFD

refinements of jet stability analyses. Bubbles formed in form of small bubble

(nano/micron) are transferred into the reservoir and flow through Li-loop channels. There

is experience on pernicious impact of helium supersaturated flowing lithium on EM

pumping (AP-100, AP-1000 US Space Programme) derived from possible condensation of

Helium at channels wall of impact to internal EM pumping machinery. Design of IFMIF Li-

loop should consider on-line He purging conditions. On line purging can be easily

achieved by some intermediate MHD stirring device and less efficiently with free

sweeping surfaces under vacuum.

For DEMO-2003 Breeding Blanket /He-cooled Lithium-Lead blanket conditions

and according with He atomic breeding and actual approximation for values of He

Henry´s constant in Pb15.7Li, the LM is supersaturated in helium. The main question is if

ionic breeding can create the local perturbation conditions (as cloud chamber in high

energy physics) for He bubble nucleation. It can be assumed as reasonable that ion

breeding in LM can create the microscopic conditions for bubble nucleation. Many direct

and indirect proofs of it exist. In principle, bubbles might be nucleated with minimum

number of atoms. It is observed in diverse tritides. Following the available equation of


state valid for native bubbles, the bubbles in LM need a larger number of atoms (n ~

104) for high inner bubble pressures (100 MPa). Bubble nucleation process is fast

enough. Nucleation can be considered instantaneous for technical BB design purposes. In

HCLL channel conditions bubble formed are about diameter 20 nm. This value is based

on liquid metal surface tension data and assessment made here for He solubility in LM.

Bubble generation rates in HCLL have been obtained from atomic breeding and from the

number of atoms per stable bubble created. The bubble concentrations and sizes allow to

consider bubbles as independent with low coalescing probabilities. Proposed values for

nano-bubbles are given. Small and independent nano-bubbles evolve stably in slow LM

HCLL channels. The main important driving forces for bubbles are derived from the

momentum transfers from LM, i.e.: viscous drag forces. Bubble brownian diffusion

overlaps this drag component. Thermal gradients can have an effect on bubble transport

and can justify a transfer of bubbles to the interface between LM and CP and non-

nucleated gas condensation. If such a regular and homogeneous interface is established

it can justify a mass-transfer resistive mechanism for tritium transfer permeation into the

CPs. Precise description of bubble plume transport can be numerically achieved from

precise solution of fluid velocity fields accounting for both MHD and thermal convection

effects. For a plume of independent nano-bubbles no major wall rebound effects can be

expected. According to bubble sizes and distribution in channels the coalescing

probability of bubble along HCLL channels is low. Basic fundamentals of 2-phase

dispersion models can be applied for the analysis of helium bred in LM channels and to

assess its impact on tritium transport. Simple approximation available of such models

can be exploited to evaluate the final role of bred bubbles. The specific in the case of

HCLL channels is the small size of bubbles and the low mass flow rates. Use of such

approximations (assuming common reference values for the rest of parameters) permits

one to justify POTENTIALLY LARGE IMPACT of bubbles on tritium transport. Reference

case values of natural extraction efficiencies of 0.27 (!) (as fraction of tritium transported

by bubble) may be justified. This fraction, if confirmed, would mean an important impact

on the conceptual design of tritium cycle technology for Fusion Reactor DEMO in many

aspects: - relaxing or complementing requirement of tritium permeation barriers, - on

design definition of tritium extraction systems, etc. Activities, on modelling and on

definition the appropriate experimental programme (specific tests (CAVITEX) seem

absolutely necessary) are ongoing in CIEMAT. Developments towards the numerical

implementation of 2-phase dispersion models for a bubble plume in LM conducts

represents a major computational goal and strong progress and consistent results are

being obtained at present produced by Technical University of Catalonia.

New activities are undertaken assessing potential needs and/of purging techniques for

helium in liquid metals for ITER TBM HCLL and DEMO.



Fundamental work is ongoing concerning rigorous and systematic literature review of

inter-atomic potentials for Li-Li, Li-He and He-He system has been accomplished. Li-Li,

He-He and He-Li inter-atomic potentials. They can be found in the literature, with only

narrow margins of uncertainty for the obtaining by computational ways basic physical

magnitudes in this system. These input on potentials have been reviewed so that an ab-

initio simulation of the He/Li system with He super-saturation can be carried out in order

to look for a visualisation of bubble nucleation in Li system.

From this review a large confidence on the available Li-Li, Li-He and He-He potentials for

simulations can be concluded. Li-Li potentials and Li-He potentials have a large

experimental (spectroscopic) validation. Among them DFT and in particular OF-AIMD

potentials have shown the largest reliability to reproduce Li-Li neutron and x-ray

diffraction experimental data (at lower k numbers) with relaxed computational costs.

Another question is the computational costs for each type of potential and computational

approach. Diverse potentials (Li-Li, Li-He, He-He) have proven large capabilities to

reproduce bulk and physical magnitudes of systems and interaction properties. Potential

are then available for the simulation and visualisation of He dynamics in liquid Lithium.

Global representation of each pair potential advances the possible He behaviour in Li-

system: tendency of Li atoms to cluster at short distance, weakness of He-Li interaction

and comparative stronger long-range He-He interaction. Such characteristics advance

natural tendency of He atoms in liquid lithium for nucleation. SIESTA DFT potentials have

been produced. Such values are genuine products because DFT potentials for DFT system

had never been produced before. Ways to generate directly He-Li simulations have been

explored. Conclusion is that DFT are not useful for direct DFT/MD simulations of He-Li

systems in order to visualize nucleation phenomena. Extra large computational demands

would be needed according to reference values of He/Li solubility and number of atoms

needed to constitute a bubble within the LM.

Alternatively, classical MD makes an accessible route to approach the problem and is

assumed as the method for the final attempt. Computations are ongoing with MDCASK

updates.

IV.4. Fusion safety issues

IV.4.1. Database of failure of fusion machine components for

probabilistic safety analysis

IV.4.1.1. Definition of the database structure


Component taxonomy, developed from IAEA taxonomy adapted to FRDB, and a basic

event coding, similar to used in fission nuclear power plants, were proposed for IFMIF

Failure Rate Database.

On the other hand, fission, fusion, and accelerator database were reviewed as sources of

data for IFMIF RAM analysis. (ref RAM1).

IV.5. Operation of essential technological facilities

according to the needs of the programme

IV.5.1. Irradiation sources

IV.5.1.1. Operation of the van de Graaf accelerator

During the year 2008 the 2 MeV Van de Graaff electron accelerator has been operating

for 56 days corresponding to 370 hours. Optical, electrical and diffusion measurements

have been performed during irradiation for SiC and LiNbO3. A new experimental set up

was mounted during the year 2008 in order to perform radiation enhanced desorption

measurements of He and H isotopes during 1.8 MeV electron irradiation. Also

improvements on the radioluminescence set up system have been carried out.

IV.5.1.2. Operation of the “Nayade” irradiation facility

Irradiation of special mirrors for diagnostics at different conditions of temperature and

environment have been performed during the year 2008 in the 60Co NAYADE irradiation

facility at CIEMAT. A total of 2200 hours have been dedicated to these irradiations. Steels

mirrors (316, F82H, Eurofer 97, and Eurofer ODS) have been irradiated in synthetic air

and dry nitrogen to examine possible degradation of potential first mirror materials due

to gamma irradiation during ITER shut-down. Commercial dielectric coated mirrors from

PGO (Präzisions Glas & Optik), and SiO2 coated mirrors prepared by CIEMAT and ENEA

have also been irradiated in humid air and dry nitrogen to study the stability of the

different coatings.

IV.5.1.3. Development of an irradiation line at the CMAM ion accelerator

An irradiation line is being developed at the 5 MV tandem ion accelerator at the CMAM.

An special irradiation chamber and sample holder has been designed and fabricated at

CIEMAT during 2008. This will permit to measure both optical and electrical degradation

and also diffusion of He and H isotopes for candidate fusion materials during ion


irradiation. Vacuum leak tests of the irradiation chamber has been performed before

mounting the irradiation chamber at the accelerator beam line. During year 2009 first

irradiations are planned to be performed.

IV.5.2. Liquid metal loops

IV.5.2.1. Feasibility studies of Li liquid metal loops for Li

The activities related to the feasibility studies of a liquid lithium metal loop during this

year have been mainly focused on the following aspects:

• Review of the R&D needs concerning liquid lithium in fusion technology, proposing

some conceptual designs for the possible experiments, such as free surface,

corrosion, safety, etc.. and identifying the required technical conditions of the loop(s)

to perform them (lithium temperature, speed, mass flow, etc.., main components and

instrumentation, atmosphere required, etc.).

• The development of a preliminary study of the safety aspects related to the lithium

loop (ref LMLi_1)

• The visit to different experimental facilities such as the Bi-Lead loop of CIEMAT

materials group, and the lithium loop of the Osaka University, in order to collect

useful technical information from the main responsible of such experiments.

• The first draft calculations concerning the power deposition on a lithium jet from

different particles (electrons, deuterons, protons and photons) of different energies,

in order to assess the feasibility of coupling a particle accelerator with the lithium

loop. The objective of this coupling would be to obtain a power deposition similar to

that appears in the bulk of IFMIF target.

All this activities have been performed in collaboration with UPM and IDOM, being part of

them in the framework of a CDTI project “Estudio de viabilidad para la integración de dos

aceleradores de partículas en el Laboratorio de Metal Líquido de Technofusión” SAE-

20081014.

IV.5.2.2. Feasibility of a coupled He/lead-lithium loop

An activity was launched in order to assess the interest and programmatic needs of a

new loop for fusion technology use (breeding blanket technology). Analysis of available

facilities reveal the need of couple loops He/lead-lithium upgrading ranges up of the

present one under construction (EBBTF). A tentative preliminary design of such as loop

has been proposed. Loop couples 2 MWth pressurized helium loop with a lead-lithium one

(high molar rates) through a representative exchanger working under strong magnetic

field. A cost assessment (25 M€) prospectively justifies consider such facility in the

panorama of new S&T infra-structures being planned in Spain; as it was proposed for

Barcelona Fusion Centre (b_Fus). At present the project is entering in a new phase of

detailed studies and deep technical justification of possible experimental uses programme

in the new facility.

IV.6. Remote handling

IV.6.1.1. Vessel in-Vessel: To support the Radiation Tolerance Assessment of

RH Components in particular for hydraulic systems

Remote Handling is one of the most challenging aspects of the ITER project, and the

European home team is building a major prototype of the divertor region (the Divertor

Test Platform 2) to confirm the RH concepts in this area.

To handle the 9t divertor cassette, the Cassette Multifunctional Mover (see right)

incorporates water hydraulics because it offers high forces and precise control in a

compact envelope, with minimal long-term contamination should a leak develop. Water

hydraulics components use mainly stainless steel - unaffected by gamma radiation – but

the internal seals are known to be sensitive to irradiation, which could cause failures. For

radiation testing of these components, a modular approach was adopted, enabling up to

11 seal carriers assemblies to be irradiated simultaneously in the limited space available,

with individual carriers being removed at varing total doses up to 10 Mgy. Each carrier

was then installed in a real hydraulic ring for testing, revealing not only at what total

dose the components became unusable, but also hoe they fail, enabling condition

monitoring to asses the state of seals long before their failure might render the RH

equipment irrecoverable. (ref RH_1)

IV.6.1.2. RH on diagnostics port plugs

A preliminary review of the maintenance operations and procedures to be carried out in

the Hot Cell for the ITER Port Plugs has been carried out, focussed particularly on

establishing the requirements of the buildings for the Tecnofusion RH Laboratory. The

number, dimensions and function of the Equatorial Port Plugs and Upper Port Plugs in

ITER and some of the basic maintenance operations to be carried out in the ITER Hot Cell

on such Port Plugs are described. Finally recommendations for the definition of the size


and layout of the buildings for the RH Laboratory in Tecnofusion have been produced (ref

RHE_1).

IV.6.1.3. Definition of needs for a general purpose TH test facility for

diagnostic port plugs and TBMs

One of the missions of ITER, as it is nominally stated in the ITER Agreement, is to test

the Test Blanket Modules (TBM). Such TBM are prototypes scaled with dimensions of

ITER test semi-ports of the different tritium breeding blanket designs which are being

developed by the respective Technology Programs of the ITER partners, as concepts for

future demonstration reactors (DEMO). ITER does not need such TBM to achieve its

objectives as scientific experiment, but it supposes an unique opportunity to test a

multiplicity of future reactors key technologies in a fusion environment: neutrons of 14

MeV, relevant thermal and neutronics loads. Some of these tests are critical in the path

towards the production of electricity by fusion energy.

At the end of 2008, CIEMAT signed the Consortium of Associates Agreement for EU ITER

Test Blanket Module.

A TBM is a nuclear component which is pioneer in its class in the history of the energy

technology. Between the great number of technologies which are implied in the

development of a TBM we can find the key technologies for the integration of

components in a fusion reactor and its integral remote handling. The specific

development of such technologies is not only an operative requirement of ITER, but it

has the objective of testing and developing the operative availability of the future DEMO.

The ITER Organization will demand to its partners the integral demonstration of those

capabilities before allowing the installation of a TBM.

A test capability which has no ITER partner today is precisely a TBM integral remote

handling test facility. The demonstration of the capability of TBM integral remote

handling is one of the technology services managed by F4E/Barcelona which could be

sold for ITER outside Europe.

The position for this new experimental capability falls within the “EU ITER-TBM

Consortium of Associates”, where Spain participates, and represents one of the new

Spanish infrastructures, is estimated strong. Spain has expressed strategic interest to

host such as Integral TBM RH Demonstration facility.

In this frame preparatory activities were launched two years ago in order to perform a

deep review of TBM design, integration and TBM RH studies in order to generate baseline

specifications for a future TBM RH Integral Demonstration Facility serving to prepare a

preferential support request to F4E in the near term.



The cost assessments (15 M€) has suggested to consider the hosting of such as new

capability at any of the new R&D Centres for Fusion technology being planned.

IV.6.2. IFMIF

IV.6.2.1. Test bed RH, definition of needs

A note to define the dimensions and some requirements of the buildings for the

Tecnofusion RH Laboratory has been produced. The minimum dimensions of the building

have been estimated based on the tests to be carried out on the large components in the

Test Facilities of IFMIF. The type of a favourable overhead crane for the facility, the size

and location of the storage area and other key features of the building have been

recommended (ref RHE_2).

V. TRAINING AND CAREER DEVELOPMENT

V.1. Training activities

CIEMAT has taken part in three training actions organised by EFDA and the EU

Commission, the first one was related to the European Fusion Training Scheme, and it is

focused on microwave Technologies for diagnostics, the programme is run in

collaboration with IST and IPP and CIEMAT Hill be responsible for the training of one

researcher, who was contracted in 2008. The second action, within the EFDA Goal

Oriented Training, corresponds to the proposal EUROBREED, where CIEMAT is also

responsible for one trainee, which will be hired early in 2009. Finally, CIEMAT, together

with a number of other EU labs, has taken part in the winning proposal for training under

the Coordinated Support Actions call.

In parallel, CIEMAT has continued participating in several national and European training

programmes. Amongst the national ones it is worth to mention the Master on Nuclear

Engineering and Applications, where Fusion takes a 20 hour course or the Master on

Energy organised by the Universidad Autonoma de Madrid, where a ten hour course is

given in Fusion. However, the main action on training is run in the framework of the

European Master Erasmus Mundus on Fusion Physics and Engineering, where CFIEMAT

participates together with a number of Spanish and European universities. In 2008

CIEMAT was responsible for more than 200 hours in lectures for that Master.


VI. OTHER ACTIVITIES IN MAGNETIC

CONFINEMENT FUSION

VI.1. Public Information

VI.1.1.

VI.1.2.

Outreach activities in collaboration with the European

Public Information Group

During 2008 a number of outreach activities in collaboration with EFDA PI Group have

been carried out. Main of these was the exhibition of the Fusion Expo at the science fair

“Madrid es Ciencia” celebrated in Madrid in May. The exhibition received more than

200.000 visitors in 4 days. New exhibitions of the Fusion Expo in Spain will be organized

for the next years.

A new website for Asociación Euratom-Ciemat keeping a common image with the other

associations is being developed in collaboration with EFDA PI Group.

A number of oral presentations on fusion energy have been presented along the year in

several events for general public.

Computation developments: Volunteer Computing for

fusion (using BOINC). Development of a Citizen

supercomputer in Spain

The development of the citizen supercomputer IBERCIVIS, where the ISDEP code

adapted to ITER is running, is and has been a good tool for disseminating fusion research

and the potential advantages of commercial fusion. ITER activities have been also made

public using the related activities. A web page (http://www.ibercivis.es) has been

elaborated to disseminate IBERCIVIS activities and, particularly, fusion research on this

citizen computer. This web page is used to register citizens and CPUs in the computer

and to disseminate the research activities that are performed using IBERCIVIS. Fusion is

one of the main activities on the computer. The 20,000 persons that are registered in

IBERCIVIS are indeed interested on the results of the calculations and are the first target

of our dissemination activities. An important task of these activities is the dissemination

among the secondary school students that has been performed based on some materials:

a CD-ROM and some texts.

http://www.ibercivis.es/


The public presentation of IBERCIVIS had strong impact in the media, including high

impact journals, TV and radio interviews, and several articles have been appearing in

divulgation publications [ref IBERCIVIS]. As a result of these activities a large number of

public presentations on Fusion research have been performed in different institutions and

cities.

VI.2. Technology transfer

During 2008, CIEMAT kept active holding the chairmanship of the “Plataforma

Tecnologica de Fusion” (PTF), which involves about 70 companies and R&D institutions

who are interested in participating in the ITER construction.

In particular it is worth to note the organization of a seminar in Barcelona , in the frame

of the “BTEC Summer Sessions”, oriented to the ITER plant systems and civil

engineering. Another relevant action was the improvement and maintenance of the PTFs

web page www.iter-spain.es, oriented not only to Spanish institutions but also to other

EU organizations who might want to find Spanish partners.

VI.3. Socioeconomics

VI.3.1. External costs of energy sources. Validation of the EFDA

Times model , task WP08-SER-ETM FDA Times Model

The first objective of the task was to continue with the review, validation, improvement

and documentation of the fossil and renewable resource potentials for the different

regions of the EFDA-TIMES based on recent literature and databases.

Other objective consisted of performing model tests and assessing the results. Some

sectors requiring adjustments were identified.

This work involves the constant updated of VEDA templates and scenario files and will go

on in 2009.

Finally, CIEMAT continued collaborating with the other teams of EFDA responsible for the

review of power plants and downstream transformation given the closed relations

between the latter and the resource analysis

http://www.iter-spain.es/


Details of the work are given in TW6-TRE-ETM-RES-Del 1, TW6-TRE-ETM-RES-Del 2,

TW6-TRE-ETM-RES-Del 3 (only available under direct request to EFDA by the member

organizations)

VI.3.2. Social Perception of Fusion research

VI.3.2.1. Social Perception of Large R&D Programmes (TW5-TRE-FESS/C)

The key findings of this (EFDA) Task carried out by Ciemat and Cardiff University, and

finalised in 2006, were published in Science and Public Policy in 2008 (ref TW5-TRE-

FESS/C_4).

VI.3.2.2. Investigating lay understanding and reasoning about fusion

technology by means of a group-based methodology suitable to

take lay participants through a learning process about fusion (TW6-

TRE-FESS-B1).

The overall objective of this work, carried out from January 2007 to June 2008, was to

find practical ways of improving communication about fusion, and to enhance the quality

of lay engagement with sources of information about fusion. Three tasks were foreseen:

Design a group-based methodology suitable to take lay participants through a learning

process about fusion. (Task 1); Utilise this method to investigate reasoning process

about fusion by lay publics (Task 2); Fully evaluate this exercise in methodological

development, and draw conclusions and a general discussion on the methodology to

address learning processes about fusion (Task 3). During 2008 the corresponding Final

Report to EFDA was produced (Task 3). The key findings of this research showed that the

hybrid method has simultaneously allowed a deep and meaningful analysis of the lay

perceptions of nuclear fusion together with the generation of a further lay engagement

exercise with the technology. In addition, the method has a noteworthy capacity to

generate a significant amount of rich qualitative and quantitative data. This meaningful

analysis of both the lay perceptions of nuclear fusion and the ways in which lay citizens

“engage” with information material about the technology presents clear implications for

future communication strategies on fusion.

The main findings of this work were presented in two international congresses held in

Spain in September 2008: the First ISA (International Sociological Association) Forum of

Sociology (ref TW6-TRE-FESS-B1_1), and the ESREL (European Safety and Reliability

Association –ESRA- and Society for Risk Analysis Europe -SRA-E) Annual Conference (ref.

TW6-TRE-FESS-B1_2 and ref. TW6-TRE-FESS-B1_3).

http://www.esrahomepage.org/

http://www.esrahomepage.org/

http://www.sraeurope.org/


VI.3.2.3. Towards a participative dialogue with society about the risks

associated with fusion energy (WP08-SER-AWF. Activity 1)

The EFDA (2008) Ad-Hoc Group on Socio-Economics has identified a need to move

towards creating a dialogue with society about the risks associated with fusion energy.

Ciemat and Cardiff University has proposed work that will make a significant contribution

towards this overall objective by: Understanding and assessing stakeholders’ perception

of fusion technology and fusion energy; and Identifying appropriate communication

channels and participative methodologies. To do so, the team will rely on both the

previous Ciemat-Cardiff University EFDA work, and on additional research on which we

are collaborating, which is being funded by the UK Economic & Social Research Council

(ESRC). This latter project, which will run until August 2009, has been using the same

hybrid methodology to collect data in the UK.

In this way, a comparative corpus of data is being generated, making possible a (limited)

cross-cultural Spanish-UK analysis. The UK-based work is also addressing different kinds

of stakeholder relationship with fusion: including that of lay citizens and groups with

special values-based or occupation-based perspectives on fusion. During 2008 Ciemat

carried out additional empirical work in Spain, in order to make the Spanish and UK

corpora directly comparable. Thus, two additional discussion groups were run n Spain

with participants drawn from a) members of environmental groups, and b) people

working in the energy industries.

The main findings of this comparative work will be presented in the forthcoming Annual

Meeting of the Society for Risk Analysis Europe, to be held in Sweden (ref WP08-SER-

AWF- Activity 1_1).

VI.4. Activities related to the Broader approach

VI.4.1. IFMIF/EVEDA Project

VI.4.1.1. Accelerator Facilities: RF system

• Electrical Power Supplies

In 2008 main efforts have been dedicated to anode HVPS preliminary design and to the

technical specification description. The preliminary design of HVPS is finished and the

main components and parameters of the system are defined. The preparation of the

detailed technical specification of HVPS started at the end of 2008 and it will be finished

in February 2009. The requirements for the auxiliary PS for the control grid, screen grid

and filament for the final and driver amplifiers have been identified and contact with

possible vendors (Spellman, Glassman) have been established.

• Amplifier Integration, Transmission Lines and Singular Elements

During 2008, a conceptual design of the RF module has been finished, proposing a

steel/aluminium four wheeled bed with fast connectors for an easy maintenance. The

main characteristics of the power amplifiers, transmission lines and circulator/load are

defined and a draft of the technical specifications for these components has been written.

Preliminary studies about the power balance along the RF chain have been made to

validate the behaviour of the proposed architecture in the conceptual design. Contacts

with possible vendors of these components have been established and preliminary cost

estimations have been received from industry.

• Low Level RF regulation & Local Control System

Most of the year 2008 has been spent on the detailed design of the Low Level RF

including the needed interfaces with the RF chain components and the local control

system. The local control system conceptual design and the preliminary architecture

studies have been initiated. The technical specifications of the LLRF have been finished

with the detailed design. In the last trimester of 2008 the technical specifications of the

components for the LLRF were sent to the manufacturers for purchasing. These

components have been delivered and the LLRF integration process will start at the

beginning of 2009.

• Cooling System

In 2008 it has been performed a preliminary design of the RF water cooling system. The

dimension of the main components has been defined.

• Power Amplifiers

The new technical specifications for the three amplifier stages (pre-driver, driver and

final amplifier) are completed and the call for tender is close to be ready for consultation.


VI.4.1.2. Accelerator Facilities: Beam Dump & HEBT

During 2008 the main activity has been the performance of all the trade studies

necessary for the conceptual design of the beam dump. In July 2008 a Design

Orientation Review (DOR). Meeting was held to review the selected approach (ref BD1).

As a result of the studies prior and after the DOR, the main beam dump design

parameters were frozen. These are the following:

• Material: copper

• Conical geometry with a diameter D=30 cm and a length L=250 cm

• Cylindrical scraper with L~50 cm and D=30 cm

• Cooling system: Axial flow through annular channel of varying width in counter-beam

direction. 30 kg/s, Tin=30 ºC, pin=3.5 bar, v<9 m/s

This design has been shown to be compliant with the mechanical design rules during full

power stationary operation of the accelerator (ref BD2 and ref BD3). The radioprotection

calculations performed demonstrate that doses during beam on/off phases are below

limits provided that an adequate local shielding is installed (ref BD4 and ref BD5).

With regard to the design of the high energy beam transport line, from the exit of the

linac up to the beam dump, a definitive design is obtained with a 20° dipole (ref BD 6).

The portion upstream the dipole is kept for beam measurements by means of a

diagnostic plate, for which a 3 m long drift has been reserved. The downstream portion

expands the beam before reaching the beam dump in order to minimize the deposited

energy density.

Non interceptive methods for emittance measurement such as the quadrupole scan

method have been investigated. As strong space charge effects make linear calculations

not valid, the emittance will be inferred from numerical simulations. It has been checked

that the foreseen horizontal and vertical beam size variations are enough to deduce the

emittance value.

VI.4.1.3. Accelerator Facilities: Diagnostics

The main activities aimed at providing the instrumentation requirements along the

IFMIF/EVEDA accelerator prototype. Despite the evolution of the beam dynamics design

and new requirements, the final location and specifications are close to completion (HB_1

and HB_2): the final layout and specifications will be finalized next year. In parallel, the

conceptual design of most of the diagnostics was started. At the end of 2008, a Design


Orientation Review was held in order to follow up the status of the instrumentation

design and detect the critical issues of the package.

• Diagnostics Plate

The layout of the instruments and the specifcations was studied and a preliminary layout

has been proposed (ref DP_1).

• Beam Position Monitors

The design and construction of the cryogenic BPM’s inside the solenoid package of the

HWR were taken over by CIEMAT. The debunching effect was studied, which is extremely

important for the evaluation of the utility of the pickups at the end of the HEBT beamline

(ref. HB_1). Electromagnetic simulations are also in progress for several types of

pickups. Comparison between simulations and theory are in progress. Striplines are the

first choice for the diagnostics plate and buttons for the HWR. The electronics design was

also faced with the choice between IF and I-Q evaluation and simple Log-Ratio schemes

as the main candidates.

• Fluorescence Profile Monitor

The main work was focused in the evaluation of different types of optical schemes and

cameras. The recommended input specifications for the cameras are rad-hard tolerance

and good resolution. Suitable model from different manufacturers were identified and

evaluated (ref. FPM_1 and ref FPM_2). Several optical schemes based on optical fiber

were studied. In addition, profile distortion was studied for different types of gases,

identifying good gas candidates, like Xe. A preliminary model of the vacuum chamber

with ports for horizontal and vertical profile view, gas injection, vacuum pump was

designed.

• Transverse Halo Monitor

Most of the design work was directed to the investigation of different types of monitors:

fixed segmented metallic plates, movable metallic probes,… The so-called THM in front of

the Beam Dump will be mostly devoted to act as fast interlock in case of increase of

beam losses, permitting in the same way an analysis of the distribution of external or lost

particles. The THM in the Diagnostics Plate permitting the characterization of the beam

tails, as an extension of the Profile Monitors dynamic range, to possibly perform halo

analysis. In both cases, the type is almost decided but the final specifications from beam

dynamics estimations are not finished. Thermomechanical and activation simulations are

also being performed.

• Emittance and energy spread measurements


The design of these measurements is being carried out in combination with the beam

dynamics group (CEA & CIEMAT). For the transverse emittance, the possibility of using

quad-scan was evaluated by CIEMAT using beam dynamics simulations. Several analysis

methods were studied which must take into account the strong space charge effects (ref

EMI_1 and ref. EMI_2). With the best method, a 2mm resolution from the beam profilers

is required.

For the energy spread, the focus was on the study of beam dynamics non-interceptive

methods. Quads settings were found to maximize the ratio dispersion/betatron

downstream the dipole but still the required resolution was not achieved. Other methods

like using slits at low duty cycle, use of simulation codes or change of energy with the

cavities are going to be studied.

VI.4.1.4. Accelerator Facilities: DTL & MS

Due to the change of the DTL to superconducting technology, the DTL&MS sharing was

updated between CEA and CIEMAT. CIEMAT took over the design and construction of all

the matching section (bunchers, quadrupoles, mechanical supports and vacuum

components) and the solenoid package of the DTL (solenoid and Beam Position

Monitors). The beam diagnostics devices included in the MS are under the responsibility

of the Beam Instrumentation subsystem. In the same way, the beam dynamics

subsystem is responsible of the design of the beam dynamics of the MS.

The beam dynamics design of the Matching Section is being optimized. Whilst they do not

represent major modifications in terms of BDyn, they can have consequences in terms of

number, geometrical and technical specifications for the main components of the main

section.

• Solenoids

The work was focused first on the feasibility study of the implementation of quadrupoles

between cavities with BPM’s inside. Due to the complexity of the design, the solenoids

were taken as first option and a conceptual design of the device was carried out.

• Bunchers

CEA started the conceptual design of the bunchers in order to check the feasability. A

report was published by CEA which summarizes the main specifications and the RF

simulations of a geometrical proposal for the cavity. The design evolved from a 2-gap

design to a 1-gap design. The RF requirements were considered around 100 kW/buncher

for 1.3-1.35 MV/m. Later on, the buncher design was taken over by CIEMAT during the

sharing redistribution. The conceptual design of the cavity has been focused on the


optimization of the presented design with RF simulations, a preliminary mechanical

design, tuning and cooling designs.

• Quadrupoles

The quadrupoles number (including 2 set of steerers, for horizontal and vertical beam

correction) were initially fixed to three along the beamline by the BDyn. However, as

previously stated, as the number and, even more important, the dimensions of the quads

can be changed due to the optimization of the BDyn, the status of the design carried out

by CIEMAT is still very preliminary. The final specifications, which are now available from

the beam dynamics group, will be validated in March 2009.

• Mechanical and vacuum systems

The conceptual design for this system has been delayed in 2008 due to the lack of the

necessary specifications from the different components. The mechanical and vacuum

design can only start after the final layout of the MS has been established and the

interfaces with RFQ and DTL defined.

• Beam Instrumentation

The work focused on the evaluation of the number and types of instrumentation required

and feasible in the Matching Section and start the conceptual design of the cryogenic

BPM’s for the HWR. The lack of space is the main technical issue that needs solving. The

conceptual design of the main instrumentation devices that are probably to be installed

(e.g. current transformers and beam position monitors) is well advanced and was

reviewed during the BI DOR.

• Cooling

The requirements from the bunchers and the quads were also taken into account during

the specification of the cooling system at Rokkasho. The number and diameter of cooling

pipes were designed together with Interface, USIS and HEBT groups.

VI.4.1.5. Accelerator Facilities: Radioprotection

Some important limitations are found in the available computational tools (codes and

nuclear data) to address the radioprotection analysis in the BD design. A comprehensive

methodology has been proposed to quantitative assess neutron production from d-D and

d-Cu reactions, BD activation, prompt and residual dose rates, and determine the

radiation shielding requirements. Significant effort has been devoted to validation

purposes, and as a result we can assure that prompt and residual dose rates can be

provided with a reasonably conservative margin.


An important activity has been devoted to assess the availability and quality of both

neutron production and activation cross sections for Copper in the range 0-9 MeV. At

present there is not a well accepted data set for neutron production cross sections, and

their evaluation strongly depends on the model used to calculate them. These have been

calculated with the different nuclear models included in MCNPX as well as with dedicated

nuclear reaction model code Talys. Dominant nuclear reactions are identified and their

cross-sections validated by comparing the calculated and experimental, when available,

values. Regarding deuteron activation cross-sections reliability, the same validation

procedure is followed, adding here the comparison with data from EAF activation library.

It is shown that Talys-produced cross sections represent an acceptable option to deal

with Copper in EVEDA scenarios. The applicability of MCNPX calculations to address this

problem has shown to be unacceptable and some corrective measures have been

introduced to improve its performance when calculating the neutron source

(renormalization factor of 2.5 and removing of the high energy tail).

We are developing a modified MCNPX version able to make more realistic predictions

(using external deuteron differential cross section data libraries produced from dedicated

nuclear model codes) and to obtain results much faster (new variance reduction

technique for charged particles). For activation calculations it has been shown that the

inventory code ACAB and activation cross sections obtained by the Talys code enable

residual doses from activated Cu to be obtained with enough accuracy.

Calculations concerning the base line shielding design for the BD cartridge shows that: i)

regarding beam-on/dose rates outside the vault, additional shielding is needed to fulfill

the dose limits, and a significant effort for BD shielding optimization should be

performed; ii) concerning the beam-off phase; adding a plug at the BD entrance

seems to be a feasible solution to fulfill dose requirements for hands-on maintenance in

the beam line accelerator area; and iii) dose rates in the BD cell for beam-off are

much higher than the 12.5 µSv/h limit.

Concerning activation and the consequent doses produced by H2+ beam, a preliminary

analysis shows that for 1 day continuous full power irradiation manual maintenance is

possible in the vicinity of the BD even when the water tank is removed.

Regarding activation of the cooling water, a decay tank smaller than 3 cubic meters

seems to be necessary at the exit of the BD to meet the 12.5 µSv/h limit in the heat

exchanger room

Concerning activation of the air in the BD cell, renewal air rate and dilution seems to be a

feasible option to fulfil the limits for effluents emissions.


Tritium production into the Copper Beam Stop and cooling seems to be low enough to

have negligible radiological consequences (tritium diffusion to water remains to be

analyzed).

In regards to management of the Beam Cartridge as activated waste, it qualifies for

shallow land burial as class C low level waste (waste disposal ratings, WDR << 1)

VI.4.1.6. Test and Target activities: RH Engineering

• General and basic guidelines for the design of remotely maintained components in the

Test Facilities of IFMIF have been studied, compiled and developed. The guidelines

are presently being revised by international experts to achieve further consensus.

The guidelines are structured in two main chapters: general guidelines and specific

guidelines. The general guidelines establish general rules and guidelines for the

design of the components remotely maintained (modularity, accessibility, simplicity,

standardization, decontamination, radiation hardness, adequacy for the RH

equipment, labelling, viewing and illumination) while the specific guidelines deal with

positioning aids, gripping devices, lifting devices, electrical connectors and cables,

pipes and flanges and fasteners for enhanced and reliable remote handling.

• A study to improve the present reference design of the components in the Test Cell of

the Test Facilities of IFMIF for enhanced remote handling has been carried out.

Further modularity, better access and more accurate and reliable positioning of the

Test Modules has probably been achieved keeping approximately the cost and the

simplicity of the present reference design (ref RHE_3 and ref RHE_4).

• An assessment and analysis of the flow of HFTM Rigs and specimens in the Test

Module Handling Cell (TMHC) and in the Post Irradiation Examination (PIE) Facilities

has been performed, being the focus of the study: the interfaces between the TMHC

and the PIE, the bottlenecks in the flow of components, storage needed,

requirements to perform the operations under certain time schedule and, the

assumptions, actions to carry out and urgency of them. Certain flow of components

has been proposed.

• The tentative proposals to improve the Test Cell, sketched during the year 2007,

have been further defined. Three studies have been published: the first focussed on

the RH issues and solutions in the Test Cell, the second mainly dealing with the

improvement of access in the Test Cell, and the third focussed on the positioning and

assembling aids for faster and reliable assembling/disassembling of the components

in the Test Cell.


VI.4.1.7. Test and Target activities: Medium Flux modules engineering

• Engineering design of the Tritium Release Module

The conceptual design of a capsule to perform tritium permeation experiments on liquid

breeder blankets materials has been carried out. This design has been made compatible

with the present reference design of TRM, introducing minor modifications on it, but

considering the HCLL DEMO blanket LiPb channels conditions.

The experiment will consist of a rig containing a closed capsule partially filled with 16 cm3

of eutectic LiPb, the surrounding helium purge gas channels to sweep the tritium

generated in the rig and electrical heaters to obtain the desired temperature. The capsule

walls (EUROFER, 1 mm thick) will be coated by the fusion relevant anti-permeation

coatings materials to be tested, e.g. Al-based permeation barriers, Er2O3 or TiC, among

others. Experiments should be carried out with and without coatings, and the purge gas

conditions could be changed, in order to obtain a flexible experiment. Helium also

produced in the capsule will be released into an 8cm3 plenum.

Some thermal hydraulic calculations have been performed to evaluate the thermal

behaviour of the irradiation capsule by the CFX-11 code. The results show that even in

two extreme conditions (maximum nuclear heating and no nuclear heating at all) the

desired temperatures ranges can be achieved (ref MFTM_1).

Figure TRM-1: Conceptual design of a rig for tritium permeation experiments on liquid breeders materials

• Engineering design of the Liquid Breeder Validation Module: definition of the

required experiments towards the validation of functional materials related

to liquid breeder concepts


The objective of the task is an updating of the called Insulating Coating Test Module in

the CDA report, due to the evolution in the Liquid Blanket concepts designs, and is

focused on the functional materials used in the liquid breeder blankets components

For this, a review of the main liquid lithium blanket concepts has been carried out in

order to identify the main R&D necessities. Several problems appear associated with

liquid metals such as MHD effects, tritium permeation and control, liquid-structural

materials compatibility, etc.. depending on the blanket design. The main R&D needs

identified at the moment concerning functional materials are the development of coatings

that shall act as erosion, corrosion, permeation and/or electrical/MHD barriers,

compatibility experiments, and the development of reliable joints, among other.

In addition to the tritium permeation experiment foreseen for the TRM, some other

experiments related to functional materials may be proposed for the LBVM, such as:

• Insulating coatings experiments (in process of design) in order to test the electrical

conductivity of coatings.

• Corrosion experiments to test anti-corrosion coatings and the influence of irradiation

in the corrosion issue

• Pb-17Li compatibility experiments with: EUROFER, SiCf/SiC, Brazing material for

SiCf/SiC joints, weldings, etc.

• Testing of joints, etc..

• Analysis of the suitability of IFMIF MFTM irradiation conditions for

experiments on liquid breeders materials

In parallel to the previously described works, draft neutronic calculations have been

performed by McDeLicious and MCNP codes, to assess the suitability of the medium flux

region of IFMIF to perform experiments related to liquid breeder blankets. The calculated

irradiation conditions in different locations of this area have been compared with the

existing ones on a HCLL DEMO blanket. In case of functional materials, also the

irradiation conditions obtained in High Flux Fission reactors have been considered for

comparison, as most of current experiments are carried out under these conditions.

Concerning the tritium permeation experiment, the result of the calculations show that it

should be installed as closer as possible to the HFTM (i.e., in the position of the CFTM) in

order to generate a high amount of tritium and major damage in the EUROFER capsule

walls. As far as the expected values of damage and tritium generation rate concerns, the

obtained values in any position of the medium flux area of IFMIF are in the range of the

ones for a HCLL DEMO blanket (ref MFTM_1).


Concerning functional materials, SiCf/ SiC (needed in some concept as electrical

insulator, as previously mentioned), and also coatings like Al2O3 (ant permeation coating

and electrical insulator), Er2O3 (ant permeation coating) and AlN (electrical insulator), are

being studied, obtaining results of dpa, H/dpa and He/dpa ratios at two positions of

MFTM. Further calculations will determine the optimum IFMIF position to perform these

experiments.

VI.4.1.8. Test and Target activities: Microfission chamber validation

activities

The fission micro-chamber may be a very useful tool for operation of IFMIF, giving

information on the irradiation conditions.

For the design of the detector, simulations of the chamber behavior including the

response to neutron and gamma fields are required. The design parameters (chamber

geometry, gas pressure, etc) must be chosen in order to optimize the detector

performance for the IFMIF source characteristics. For this, a numerical code which

calculates the response of the detectors in different conditions has been developed using

as input the design parameters . Following this, the installation of a set of detectors in

different positions in the Test Cell, close to the HFTM, has been studied in order to

establish the optimum place to locate the diagnostic. The interior of HFTM (reference

design), behind it (CIEMAT proposal), lateral sides, upper reflectors and interior of the

lateral reflectors, have been analyzed in terms of current output signal, gamma

contribution, feasibility of the installation (temperature and available space), etc. The

capability of the different arrangements to monitor the spatial beam profile has been also

studied (Ref TTFC_1).


Figure FC_1: Calculations of the output signal for a set of fission chambers located immediately behind the

HFTM. The gamma contribution is also estimated and is around a 12 % of the total output signal.

On the other hand, experiments are required to validate the microchamber in the harsh

environment of the Test Cell. In order to start with the validation phase of this work, two

PHOTONIS detectors (one fission chamber with 238U as fissile deposit, and one ionization

chamber, both 3 mm diameter, inner gas Argon at 5 bar, current mode working) have

been purchased.

The objectives of the validation experiments have been established as:

• To demonstrate the robustness of the detectors under intense neutron flux achievable

in a fission reactor.

• To demonstrate that the minimum measurable neutron flux with the fission chamber

is enough for its purpose in IFMIF.

• To characterize the response to gamma fields and comparison with ionization

chamber.

• To demonstrate the linearity with the neutron flux density and with the gamma dose

rate and calculation of the proportionality.

To measure the response time for assessment of its use as safety detector.

VI.4.1.9. Design Integration: Safety

A review of the status of the safety analysis for IFMIF was performed. Revision of the

PSAR reference accident sequences and identification of needs of assessment, on one

hand, and exploring of the appropriate tool to develop these assessments, on the other

hand, were the two basic approaches.

Review of information about the source term, chemical reactions, mobilized

components… in accident sequences was made, and modified MELCOR code for fusion

applications was selected as the appropriate tool. Review of capabilities of this code

including the thermodynamic and transport properties of lithium, and physical models for

predicting the rate of reaction of and energy production from the lithium-air reaction was

made.

VI.4.1.10. Design Integration: RAM Evaluation



A preliminary review of the status of RAM activities in related projects like ITER, LHC,

DEMO, was performed, identifying peculiarities and characteristics relevant for RAM

analysis.

Regarding to the definition of reference RAM evaluation procedure and methodology for

IFMIF, several proposal were made. Riskspectrum was proposed as the appropriate

software for IFMIF RAM studies. . Furthermore, preliminary proposals for basic event

coding and component and system taxonomy were made.

Identification of existing failure rate databases was developed as a first approach to the

definition of data sources for IFMIF RAM analysis and in order to provide a road map

through the mass of reliability data that currently exist.

A model for the target facility was prepared. This model was developed in the basis of

CDA data and taking into account the conceptual design activity reduced cost.

Calculations were performed with Markov chains method and Riskspectrum. (ref RAM1)

VI.4.2. JT-60 SA Cryostat

VI.4.2.1. Activities in the Broader Approach. The Cryostat for JT-60SA

• Introduction.

Within the Broader Approach Agreement EU has to provide some of the components of

the JT-60SA tokamak, to be assembled in the site of Naka (Japan). Spain assumed the

commitment to design and manufacture the Cryostat as an in-kind supply. The

agreement determines the furnishing of the vessel without the ports of access to the

Cryostat itself and the Vacuum vessel of the experiment. Because of the assembly

sequence, the component will be manufactured in two different contracts, one for the

lower part, the Cryostat Base (CB) and another one for the upper part, the Cryostat

Vessel Body (CVB).

• Design status.

During the 2008 year the design process has been started and major modifications have

been introduced respect to the preliminary reference design provided by JAEA. Although

some development has been produce in the CVB, the work has been concentrated in the

first part to be supplied, the CB. The work carried out has been organized in the following

areas:

FE calculations: three different models are under developing and running with different

purposes.


Drawings: the Catia models are under developing, the basic configuration is finished but

minor modifications need to be done because of the results of the calculations and due to

the changes required by JAEA.

Contract basic document: the call for tender specification was developed up to a

preliminary stage.

The time schedule foresees to finish all the mentioned tasks during the first 6 months of

the next year.

The work can be summarized in the different presentations done in the follow-up

meetings of the project. [JT08_1, JT08_2, JT08_3, JT08_4]

VI.4.3. DEMO R&D

VI.4.3.1. SiC/SiC characterization

So far the SiC activities are concerned to the acquisition and characterization of the

material. Two types were acquired and crystallographic, morphological and

microstructural characterised. Commercial hot pressed (HP) and reaction bonded (RB)

SiC were purchased in 2007.

The HP SiC shows and Uniform microstructure formed by grains < 10 µm and large

amount amorphous Si phase segregated at boundaries. It is highly crystalline with mixed

phases (70 % hexagonal + 10% rhombohedral). The C excess is found as graphite (hex)

and diamond (cubic. Also an amount of amorphous Si could be detected by SEM. After

irradiation at 420 MGy, the crystal structure is lost and becomes amorphous

The RB SiC shows a not homogeneous microstructure with elongated grains joined by

extensive Si phase (≈10%). It is highly crystalline and contains mixed phases, although

the hexagonal is the major (90%). Large amount of free crystalline Si could be found

between the SiC grains (ref SiC_1).

VI.4.3.2. Insulator ceramics

Although not directly a fusion relevant material, radiation studies on lithium niobate

(LiNbO3) a radiation resistant opto-electronic oxide material, are highly appropriate due

to its close similarity with Al2O3 (main fusion insulator candidate) as well as to other Li

containing aluminium, silicon, and titanium oxides (potential tritium breeding materials).

Such materials will be used in future fusion reactors where they will be exposed to a high

flux of neutrons and gammas giving rise not only to tritium and helium generation, but

also to damage associated with displacement and ionization, all of which will modify their

properties. The aim of the work is to evaluate both the stability of the LiNbO3 within a

radiation field, and the radiation induced release of He from the material, as well as to

investigate the potential to use radioluminescence as a tool to monitor material

modification and degradation.

To examine the effect of displacement damage and ionization, single crystal coherent

lithium niobate has been irradiated with 1.8 MeV electrons in a special chamber mounted

in the CIEMAT HVEC Van de Graaff accelerator beam line. The irradiations were

performed in high vacuum (≈ 3x10-6 mbar) at 40 ºC, 500 Gy/s. Radioluminescence and

optical absorption were measured in-situ as a function of dose (≤ 3x10-6 dpa). In order

to evaluate the possible radiation enhancement of He release, lithium niobate samples

were pre-implanted with He ions at 45 keV up to a dose of 5x1017 ions /cm2. The

implanted samples were then irradiated with 1.8 MeV electrons at temperatures between

20 and 450 ºC, and ionizing dose rates up to 500 Gy/s, in an experimental set up which

permitted one to measure the release of He during irradiation and in this way any

radiation enhanced He desorption could be evaluated. Radioluminescence and optical

absorption measurements indicate that LiNbO3 is highly resistant to ionizing radiation

damage up to about 20 MGy, and that the structured luminescence spectrum can make a

useful contribution to radiation damage studies. The results for desorption indicate that

release of He is enhanced by several orders of magnitude when exposed to ionizing

radiation.

VI.5. Dual Coolant Breeder Blankets

Breeding blankets are key systems for fusion power reactors. Their development and

qualification are crucial for the demonstration of fusion as a viable near-term energy

option. In terms of its functional requirements: structural integrity, radiation shielding,

high-grade power extraction, and fusion fuel regeneration; a breeding blanket is the

most complex component conceived to date for energy technology.

Due to their dominant strategic value for the fusion programme, the ITER Parties (EU,

Japan, Russia, US, China, Korea, and India) plan to test breeding blanket modules in

ITER, the so-called Test Blanket Modules (TBM). For the EU, the TBM Programme

represents 20% of the contribution to ITER. Within the EU ITER TBM Programme, the

Spanish involvement is expected to be significant, however the real dimension of such

involvement will depend of the demonstrable capabilities.

With this aim the expected achievements a new Breeding Blanket technologies

programme (TECNO_FUS) has been recently launched at National level intending a



strong orientation, consolidation, and integration of the available R&D fusion technology

capabilities, enabling Spain to participate as a major player in the EU ITER TBM Project.

TECNO_FUS obeys to a major Spanish Fusion Programme strategic goal of reaching

design capabilities of a fusion power reactor DEMO within the next decade.

The programme, conceived initially as for a 3 year programme, involves 100 research

doctors from 12 institutions and foresees the incorporation of an additional 20 staff for

which nearly 1/3 of the total budget is considered. In this way the proposal will enable

the incorporation of singular capabilities of excellence into the Spanish fusion

programme.

TECNO_FUS sets out a new Fusion Technology Programme in Spain. The proposal

integrates in an interactive manner key fusion technology areas of knowledge and

expertise as coordinated projects intending to develop underlying engineering and key

technological areas

Breeding blanket development line is a dual coolant/ dual functional breeder blanket line.

TECNO_FUS is a technically goal oriented and integrated Programme for dual

coolant/functional He/LL blanket. Our goal is the conceptual and engineering (functionally

speaking) detailed development for BB systems.

Radically new innovative activities are considered. Among many others: 1) design

structural optimizations of modules/segments/HTS/LTS shields designs, 2) integrated

computational capabilities for design (an integrated computational platform:

neutronics/EM/TM/MHD/tritium/ safety analyses (software), 3) design proposal for of key

components (HEX) and cycle lay-out He/SC CO2, LL/CO2 SC, 4) experimental

demonstration of tritium processing technologies (as immersed in LL permeator

principle), 5) materials production (e.g. Li6), 6) development and qualifications of new

sensing and control technologies (Proton exchange, stable in LL), etc.

Activities will officially start on February 2009, detailed work plan activities being

prepared during 2008.

VI.6. Fusion Technology Facilities

VI.6.1. Technofusion

To address new technologies related to Fusion technologies, the use of large laboratories

is generally required where to test prototypes or large facilities exposed to extreme

conditions. Such facilities are normally outside the scope of a conventional laboratory. To

this end, the project for the construction of the National Centre for Fusion Technologies

(TechnoFusion) has been set off, being one of the Singular Scientifical-Technical

Infrastructure (ICTS) in the National Map which will located in Madrid, Spain.

TechnoFusion will be a consortium between the Spanish Ministry of Science and

Innovation (MICINN) and the regional government of Madrid (CM) pretending to provide

with the major infrastructure that enable the creation and establishment of a progressive

Spanish scientific and industrial structure for Fusion technologies. In other words,

TechnoFusion starts with the following key objectives: to facilitate the access to fusion-

related technologies to small research groups, to increase the Spanish participation in the

international fusion development, to promote knowledge transference to companies for

their participation in Fusion projects (ITER, IFMIF, DEMO, JT60-SA, etc.) and to

commercially run the technology development. In addition, the developed technologies at

TechnoFusion will be susceptible to a long term commercial exploitation, as well as to

create and establish of a progressive Spanish scientific and industrial structure in Fusion

technologies.

TechnoFusion will be focused on these fusion related technologies that are considered to

develop further in the near future. Also, it was taken into account the commitments that

Spain has taken within the EU-Japan bilateral agreement (initial phase of IFMIF

development and the construction of JT60-SA). The technical activities are related to the

infrastructure development needed for research lines such as: i) modification of materials

by simulating the environment under operation, ii) robotics and automatic remote

handling, iii) plasma-wall interaction, iv) development and characterization of structural

materials and insulators, v) liquid metal technologies and vi) computer simulation.

Therefore, ICTS TechnoFusion will consist of a complex of seven large laboratories and its

auxiliary buildings, many of which will be unique facilities of global significance whose

main technical objectives will be summarized as follows:

• Methods of Irradiation Lab

The effect of neutron and gamma radiation in the materials will be studied by simulating

the environment through irradiation with ions and electrons. The qualification of

components in a severe environment similar to that in ITER will be possible. The effect of

neutron radiation will be simulated with the aid of three ion accelerators used

simultaneously: a Tandem-type light ions accelerator of 6 MV for He implantation, a

second Tandem-type light ions accelerator of 5-6 MV for h (or D) implantation and a high

energy ions accelerator (k=110 cyclotron) for crystalline structure damage using high

energy heavy ions (Fe, W, Si, C) or protons. Additionally, this lab will study the effect of

an applied magnetic field (5-10T) simultaneously with irradiation. The effect of ionizing


radiation will be studied thanks to a coupled electron accelerator (Rhodotron-type of 10

MeV or Dynamitron-type) to use in common with the Remote Handling and Liquid Metal

Labs.

• Plasma-Wall Interaction Lab

The plasma beam would have two principal elements: a lineal plasma device able to

generate D plasmas with flux densities up to 1023 m-2s-1 (one tenth of what is expected

at the divertor of ITER) and ionic impact energies in the range of 20-150 eV in steady

state; and a device of type QSPA with a pulse length of 0.1- 1.0 ms and energy fluxes of

0.1- 20 MJm–2 in an axial magnetic field of at least 1 T. Both devices must be connected

to a vacuum chamber, which will make possible the exchanging of materials between

them and the simultaneous, or consecutive sample exposition to steady of transitory

plasma fluxes under controlled conditions.

• Liquid Metals Lab

The use of liquid metals in different components of ITER and IFMIF implies an increasing

interest in liquid metal associated technologies. This facility will be based on two lithium

liquid loops coupled to the electron accelerator to develop the technologies related with

liquid metal purification methodology, with liquid behaviour under a magnetic field or as

a free surface, or with the study or corrosion mechanisms in materials.

• Remote Handling Lab

It will include the facility able to install big prototype components to validate the remote

handling operations Among others, a facility for handling demonstration of ITER

diagnostic plug plugs, the facility for remote handling of test blanket modules, … In

addition, a lab for components and systems qualification in a severe environment will be

installed by using the electron accelerator.

• Materials Production and Processing Lab

It is planned to develop of new experimental facilities which allow the production of

fusion components at a semi-industrial scale. Therefore, it will count with the necessary

equipment for the production of new prototype materials (low activation steels, ODS

reinforced steels, …) by using high technological equipments as: vacuum induced

furnaces, a hot isostatic pressing, Spark Plasma Sintering or Vacuum Plasma Spraying.


• Characterization Techniques Lab

This lab will be provided with a set of advanced techniques to perform a complete

characterization of materials modified and produced at the other TechnoFusion Labs. It

will be possible to process materials by using FIB and to characterized them by their

mechanical properties (creep, fatigue, nanoindentation), by their composition (using

SIMS or APT), by its structure and microstructure (SEM, EFTEM and XRD), by their

electrical and optical properties. Some of them will be located in the line of the three ion

accelerators in an attempt to study in-beam material behaviour.

• Computer Simulation Lab

This lab will answer the physical questions still open that influence the coming

technological developments. It will include the integration of process simulation up to the

final energy generation. It has the objective of computer simulate the dynamic behaviour

of materials. It means a service in radioprotection area as well as neutronic answers.

Advanced software tools are then needed (ACAB, FISPACT, ORIGEN, CHEMCON,

MELCOR, MACCS, MCNPX, PHITS, SRIM, TMAP, EMPIRE-II).

• The start of the training staff for TechnoFusion Facility

A key aspect to build, operate and exploit TechnoFusion will be the availability of staff

(technical and / or science) with experience in those technological areas proposed. It is

evident, therefore, the need for training of personnel capable of meeting the identified

needs. Given the long time needed for this training, it is important to start now with this

issue, which means the needs for some funding along the next four years for the

recruitment of technicians and researchers. Probably, they would be sent to other centres

with proven experience in different areas of interest (probably in the area of liquid metal,

technology accelerators and plasma-wall interaction).

2008 Advances in TechnoFusion Facility

To improve the technical development of TechnoFusion, in February 2008 a group of

activities began with the aim of establishing the basis of the scientifical and technical

activities as well as starting with the required national and international cooperation to

implement TechnoFusion Facility. The started actions have been aimed at 1) the technical


definition of TechnoFusion facility and 2) the integration into the European fusion

program.

A sensible number of Spanish experts from fields related to TechnoFusion technological

aspects joint the initial nucleus. In an attempt to complete the original proposal, in March

2008 these scientific and technical advisors were organised into seven multidisciplinary

technical working groups to efficiently dedicate their knowledge on the improvement of

the technical content of the seven identified technological areas: material production at

semi-industrial scale, material modification due to ion damage, wall materials interaction

with fusion plasmas, liquid metal technology, remote handling technology, material

characterization and computational simulation. This actual structure involve up to 57

senior researchers from 10 different University departments and Research Centres (such

as CIEMAT, UPM, UC3M, UAM, CSIC and UNED). The main objective was the edition of a

technical and scientific report as the working tool to deal with the technical

implementation of the proposed technologies, equipments and labs. The document

compilation was achieved through meetings of the technical working groups (these

groups have conducted at least monthly meetings) where the original objectives were

improved, new ideas were discussed and technical parameters were defined towards the

definition of the required equipment for the best experimentation.

In addition, several collaborations with various Spanish engineering companies were

initiated to solve a number of technological aspects requiring the development of

engineering capabilities not currently available in Spain. There are a number of technical

elements of the Facility that require the implementation of some small R & D projects to

address already identified technical uncertainties: measurement of micromechanical

properties, conceptual design of a gradient energy, conceptual design of a facility for

remote maintenance of ITER diagnostic ports, the analysis of a safety methodology

required in particle accelerators, etc... The definition of immediate actions to tackle with

together with the construction of some prototype components was started in 2008.

TechnoFusion related technical comments from the Fusion Facility Review Panel

• The approach and objectives of the future Spanish TechnoFusion facility were

exposed and discussed during the Fusion Facility Review Panel held in October 2008.

The heads of the scientific direction of TechnoFusion defended the identified key

technologies that will be implemented in the facility together with the Centre strategic

technological lines focussed on the improvement of most relevant fusion technologies.

In its final report “R+D Needs and Required Facilities for the Development of Fusion

as an Energy Source”, the experts concluded that there is a still demanding range of



R&D tasks for which ITER will not be able to contribute the key information. Specific

technology facilities should be then entrusted with their execution. Some of them will

be specifically built or upgrade to acquire the capabilities needed for advancing

towards DEMO. Related to this, TechnoFusion facility was considered among the

reference facilities in Europe to contribute in the improvement of most relevant fusion

technologies. The international Panel agreed with the technologies proposed to be

developed in TechnoFusion facilities and at the same time, the Panel recommended to

strengthen the materials programme. Laboratories are needed in which candidate

materials will be developed and explored to be ultimately tested on IFMIF, in ITER

and dedicated facilities. The Panel suggested the enhancement of the capacity of

European materials laboratories for the development of new materials, pre- and post

irradiation examination and the accompanying science and modelling programme.

They mentioned the proposal for TechnoFusion, a new integrated materials test

laboratory in Spain, which would be particularly important to reduce gaps in the

IFMIF testing programme.

VI.6.2. b-FUS

EURATOM Agency, Fusion for Energy (F4E) was created in March 2007 for 35 years as

the main EC body to accomplish the EU mission to build and exploit ITER. Total assigned

budget is around 9.5 B€.

Barcelona Fusion Centre (b_Fus) represents a national initiative intending a major benefit

in terms of short-term fusion technology development, the Spanish industrial

involvement in ITER and global R&D incomes to Spain. With a strong orientation to

Fusion Technology and short-terms development needs and opportunities of Spanish

involvement in ITER, the Barcelona Fusion Centre project is today articulated around 4

main Programmes: i) a front-end ITER project office, ii) a Physics for Fusion Programme,

iii) breeding blanket R&D programme, iv) fusion plants technology programme.

Singular equipments are planned. Among others:

i) new liquid metal and helium loops for breeding blanket technologies,

ii) new RH laboratories and demonstration facilities

iii) new advanced manufacturing techniques for nuclear fusion

components

iv) new labs for production of functional materials


Urgent actions to create Front-End ITER Engineering are ongoing and would be the

flagship for the starting phase of b_Fus that will be tentatively created in the very short

time with assigned budget for urgent actions.

VII. KEEP IN TOUCH ACTIVITIES ON INERTIAL

CONFINEMENT FUSION

VII.1. Scientific development

VII.1.1. Radiation hydrodynamics and jet impact fast ignition

Radiation hydrodynamics simulations have been performed in order to model plasma

physics in the context of inertial confinement fusion and of laboratory experiments. In

the latter one, the work has been carried in relation with radiative shocks experiments

hold at high-energy laser installations relevant for astrophysical situations, [Ref

RH_FI_SIM_1]. We have shed into light the importance of radiative losses on the shocks

topology and dynamics. These losses can bend the shock, decrease significantly the time

needed to reach the stationary regime and sharpen the luminosity of the shock around a

privileged direction [Ref RH_FI_SIM_4].

In the context of inertial confinement fusion, numerical tests of radiation transport have

been performed in order to quantify the differences between the Sn model and the M1

model. The aim of this numerical work was to see the advantages and drawbacks of each

method, in order to know which one is better suited to model a given physical situation.

As we have shown that in the simple case of a Marshak wave, the differences can reach

almost 20% on the matter temperature, we are developing a series of case tests to

enhance this comparison [Ref RH-FI_SIM_5].

VII.1.1.1. Fast Ignition Targets

Work is in progress in the area numerical simulations on fast ignition, by using a model

of jet generation, with 2D and 3D Radiation Hydrodynamics; calculations are well related

also with explanation of experiments already performed in the collaboration with IPPLM

and PALS groups, which strongly will give along next year a new idea of the real

dependence of the originally proposed design of this new type of targets [Ref

RH_FI_SIM_1]. The goal in this area is very much introduced in the Target Design

corresponding to HiPER projects and LFEX (FIREX I) in Japan are doing for different


options such as cone-shaped targets, shock ignition, impact ignition and this one here

reported of jet formation.

VII.1.1.2. Laser-Plasma Interaction

The computational tools on Radiation Hydrodynamics (ARWEN code mentioned in

Numerical Modelling), developed in the frame of TUIXS project have been used to study

the physics of plasma amplifiers of coherent soft x-ray radiation [Ref RH_FI_SIM_2]. The

coupled codes ARWEN and SHADOX have been used to simulate a full multi-stage

amplifier, presenting the results as a poster on the 35th EPS Conference on Plasma

Physics. Simulations studying the influence of the plasma width have been carried on this

year. A paper summarizing the results obtained is in preparation.

VII.1.2. Atomic Physics

VII.1.2.1. Spectroscopic diagnostics

As it is know, the spectroscopic diagnostics is a technique to estimate plasma density and

temperature, which is very valuable information of plasma conditions. Work has recently

started in this new line of research. In particular the group has presented their

computational package ABAKO/RAPCAL as a useful tool to perform spectroscopic

diagnostics in the past International Conference on Spectral Line Shapes, held in

Valladolid last June, in two papers (ref SD_1 and ref SD_2). In these ones, the

temperature and density of high density aluminium plasmas obtained in several

experiments leaded by our group at the Laboratoire por l’Utilisasion of Lasers Intenses

(France) were estimated. The results obtained agreed quite well with others obtained

using different diagnostics techniques. However, we have observed that for the high

density regime the accurate determination of the Stark profile is determinant and,

therefore, it is our purpose to improve our diagnostic code in that sense. Moreover, it is

our aim to incorporate a search method based on genetic algorithms in order to optimize

the diagnostics procedure.

VII.1.2.2. Colisional-radiative calculations of plasmas

During 2008, efforts in this research line were directed to reach two objectives. The first

one was the improvement of the steady state collisional-radiative code ABAKO, by

introducing autoionizing states explicitly (ref CRC_1), which are determinant in accurate

plasma population calculations. Hence, we have observed substantially improvements in

ABAKO results, overall in low density regimes. Our second objective was the

development of a code for the calculation of plasma radiative properties such as the

spectrally resolved and mean emissivities and opacities, line intensities, source

functions…, for plasmas both under LTE and NLTE conditions. This code is named RAPCAL

(ref CRC_2), and it was coupled to ABAKO code in order to obtain a flexible computation

package to perform kinetics and radiative calculations of optically thin and thick low- to

high-Z plasmas. With this package we have carried out a detailed analysis of carbon

plasmas (ref CRC_3 and ref CRC_4), which are interesting both in astrophysics and

confinement fusion scenarios, and calculations of radiative properties of optically thin and

thick aluminium plasmas (ref CRC_5) in the detailed level approach using high quality

atomic data.

VII.1.2.3. Analytical opacity formulas

Effort has also been continued with the development of analytical expressions that permit

to evaluate the mean opacities of plasmas under a wide range of plasmas conditions in a

fast and accurate way. This kind of expressions is very relevant in hydrodynamic codes

since the use of spectrally resolved opacities for each mesh point would take a huge

calculation time. We presented a first work (ref AOF_1) where analytical expressions

were proposed to calculate Planck and Rosseland mean opacities in a wide range of

plasma densities and temperatures. The expressions were fitted to mean opacities

obtained using very accurate atomic data (under DLA approach and including

configuration interaction) and with level populations calculated solving a level-by-level

collisional-radiative steady state model, using ABAKO and RAPCAL codes. Furthermore, in

this work an extensive validation of the results was carried out by comparing them with

data available in the bibliography.

VII.2. Materials for de IFE and MFE under irradiation

3D detailed neutronics calculations have been performed for complex geometries by

using CAD/CAM original systems and connection with transport codes. These are

performed for KOYO-FI (inertial conceptual reactor from ILE OSAKA) including also fluid

dynamics in Blanket Modules for inertial and magnetic concepts [ref NEUT_MATER_1].

This is actually the state of art in designs for Inertial Fusion in addition with the work that

has been started to study chamber dynamics for HiPER system in single shot and

repetitive operation in collaboration with STFC/U.K., PALS/Czech Republic, CEA/France,

ENEA/Italy.

Fe-Cr system is the basis for the low activation steels which are being developed in the

European Fusion Materials Research Program with a strong collaboration among the


European EURATOM Associations. At DENIM-Association EURATOM-CIEMAT (thought

useful both for inertial and magnetic systems) a series of Fe-Cr alloys in the range from

1-15 at% Cr were produced at CIEMAT, and irradiated with Fe ions at different

temperatures in the form of thin foils suitable for transmission electron microscopy (TEM)

characterisation in CIEMAT. Simulations in FeCr are being performed in addition to those

already done for comparison of Fe with/without magnetic interatomic potentials. From

calculations, relevant mechanisms of He diffusion and He-V complex stability are

revealed that provide insight on the initial stages of bubble and void nucleation in f.c.c.

metals. Results are discussed and compared to other calculations in b.c.c. metals, in

particular Fe [ref NEUT_MATER_2]. A large study, very much important for Inertial

Fusion Final Optics Assembly (FOA) has been performed combining at tthis stage

simulations and experiments also relevant for magnetic fusion, but now including H

effects [ref NEUT_MATER_3 and ref NEUT_MATER_4]. The work is expected to give also

results of publication with cascade formation in 2009. A new parallel kinetic Monte Carlo

has been developed and used now for extension to higher doses [ref NEUT_MATER_5].

The study of partial dislocation in fcc metals using dislocation dynamics has also been

study with new original codes [ref NEUT_MATER_6, ref NEUT_MATER_7 and ref

NEUT_MATER_8]. DENIM-Association EURATOM-CIEMAT has started to develop

multiscale modelling for highly porous metallic foam, and ultrahigh strength materials, as

advance materials for targets.

The co-ordination of groups for Chamber studies of HPER project has started. From

already general criteria we will need to consider aspects such as: i) withstand

earthquakes; ii) be resistant to debris, radiation, shrapnel and neutrons effects from

experiments; iii) maintain deep vacuum and ultra-freezing environments required for

experiments; iv) accommodate the many diagnostic instruments, beamlines, and

associated optics and equipment; v) maintain as low as possible the activation of the

materials component of the chamber in order to induce the minimum radioactivity and

make easy the operation and maintenance; vi) take into account tritium permeation,

diffusion, contamination in that phase of operation. From calculations available in

different type of targets we have started to extract main conclusions concerning the very

different ratio of energy yields from debris, X-rays, and neutrons, also considering the

different energy spectra. The capsule design will be critical together with the calculation

of those numbers. A potential low fraction of X-rays could come from the fact that

targets are fully ionised at the end of the burn and bremmstrahlung is the dominant

emission. An important difference is also the angular dependence of X-rays, and particles

emission (this aspect could be very critical for fast ignition conical targets).


Annex I PUBLICATIONS of the Association EURATOM-CIEMAT in 2008

(compiled in Dec 2008) SUMMARY Articles published in journals and books 76 Technical reports 7 Presentations in conferences and workshops 140 PhD thesis and Advanced Studies Diplomas 8


1. Journals, books

Electron cyclotron wave power loss in fusion plasmas: a model comparison. F. Albajar, M. Bornatici and F. Engelmann Nucl. Fusion 47 (2007) 1101–1105 CIVICO: Citizen Volunteer Infrastructure for Computing. B.Antoli, D. Benito, M. Cardenas-Montes, F. Castejon, C.Castellanos, V. Castelo, C. de Alfonso, T. de Miguel, R. Gavela, V. Hernandez, L.Herraiz, J.Ibar, L. Jiménez, R. Ramos, A. Rivero, J.F. Saenz, F. Serrano, M.Rubio, A. Tarancon and P. Vuillemin Design of an advanced intelligent instrument with waveform recognition based on the ITMS platform G. de Arcas, J. M. López, M. Ruiz, E. Barrera, J. Nieto, J. Vega, G. A. Rattá, A. Murari. Computational Intelligence in Decision and Control. Proc.of the 8th International FLINS Conference. 1 (2008) 423-428 Self adaptive sampling rate for data acquisition in JET’s correlation reflectometer G. de Arcas, J. M. López, M. Ruiz, E. Barrera, J. Vega, A. Murari, A. Fonseca and JET-EFDA contributors Review of Scientific Instruments. 79, 10F336 (2008) Effect of Rotational Transform and Magnetic Shear on Confinement of Stellarators. E. Ascasíbar, D. López-Bruna, F. Castejón, V.I. Vargas, V. Tribaldos, H. Maasberg, C.D. Beidler, R. Brakel, A. Dinklage, J. Geiger, J.H. Harris, A. Kus, T. Mizuuchi, S. Murakami, S. Okamura, R. Preuss, F. Sano, U. Stroth, Y. Suzuki, J. Talmadge, Y. Turkin, K.Y. Watanabe, H. Yamada and M. Yokoyama Plasma and Fusion Research: Regular Articles. Volume 3, S1004 (2008) Conceptual design of the blanket mechanical attachment for the helium-cooled lithium-lead reactor Conceptual design of the blanket mechanical attachment for the helium-cooled lithium-lead reactor. Barrera, G., Brañas, B., Lucas, J., Doncel, J., Medrano, M., García, A., Giancarli, L., (...), Sardain, P. Fusion Engineering and Design 83 (2008), pp. 6-20 Pedestal and ELM response to impurity seeding in JET advanced scenario plasmas M.N.A. Beurskens, G. Arnoux, A.S. Brezinsek, C.D. Challis, P.C. de Vries, C. Giroud, A. Huber, S. Jachmich, K. McCormick, R.A. Pitts, F.G. Rimini, A. Alfier, E. de la Luna, W. Fundamenski, S. Gerasimov, E. Giovannozzi, E. Joffrin, M. Kempenaars, X. Litaudon, T. Loarer, P. Lomas, J. Mailloux, R. Pasqualotto, V. Pericoli-Ridolfini, R. Pugno, E. Rachlew, S. Saarelma, E. Solano, M. Walsh, L. Zabeo, K.-D. Zastrow and JET-EFDA Contributors Nucl. Fusion 48 No 9 (September 2008) 095004 (12pp) Study of Doppler reflectometry capability to determine the perpendicular velocity and the k-spectrum of the density fluctuations using a 2D full-wave code. E Blanco and T Estrada


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Plasma Phys. Control. Fusion 50 (2008) 095011 (14pp) Spatially resolved Hα-emission simulation with EIRENE in TJ-II to study hydrogen atomic and molecular physics in low density, high temperature fusion edge plasmas. E. de la Cal, J. Guasp, A. Salas, D. Reiter, P. Börner, J.A. Alonso, R. Balbín, D. Carralero, C. Hidalgo, J.L. de Pablos, F.L. Tabarés, D. Tafalla and TJ-II Team Nuclear Fusion, Volume 48, Number 9, September 2008 The path integral formulation of fractional Brownian motion for the general Hurst exponent. I. Calvo and R. Sánchez. J. Phys. A: Math. Theor. 41 (2008) 282002, Fast Track Communication. Pseudochaotic poloidal transport in the laminar regime of the resistive ballooning instabilities. I. Calvo, L. Garcia, B. A. Carreras, R. Sánchez, and B. Ph. van Milligen Physics of Plamas 15, 042302 (2008) A Systematic Study of Impurity Ion Poloidal Rotation and Temperature Profiles Using CXRS in the TJ-II Stellarator. Plasma and Fusion Research, Vol.3 (2008), S1044 J.M. Carmona, K.J. McCarthy, V.Tribaldos and M.A. Ochando Density dependence of ion temperature measured by active charge exchange spectroscopy in ECRH plasmas of the TJ-II stellarator J.M. Carmona, K.J. McCarthy, V. Tribaldos and R. Balbín Fusion Sci. and Technol. 54 (2008) 962-969 Topological characterization of flow structures in resistive pressure-gradient-driven turbulence. B. A. Carreras, I. Llerena, L. García, I. Calvo. Physical Review E 78, 066402 (2008) Computation of EBW heating in the TJ-II stellarator. F. Castejón, A. Cappa, M. Tereshchenko and A. Fernández Nucl. Fusion 48 (2008) 075011 (14pp) Estimation of pump-out and positive radial electric field created by electron cyclotron resonance heating in magnetic confinement devices. F. Castejón, S. Eguilior, I. Calvo, D. López-Bruna, and J. M. García-Regaña Physics of Plasmas 15, 012504 (2008) Grid computing opens new line of studies in fusion. F. Castejón International Science Grid: http://www.isgtw.org/?pid=1000831 Fusion plasma simulation in the interactive GRID. F. Castejón, J.M. Reynolds, F. Serrano, R. Vallés, A. Tarancón, J. L. Velasco Computing and Informatics (formerly: Computers and Artificial Intelligence), Vol. 27, 2008, 261-270


http://www.isgtw.org/?pid=1000831

The exact plasma dispersion functions in the complex region. F. Castejon and S.S. Pavlov Nucl. Fusion 48 (2008) 054003 (6pp) The Particle Flux Structure and the Search for a Flux-Expansion Divertor in TJ-II. F. Castejón, A. López-Fraguas, A. Tarancón and J.L. Velasco Plasma and Fusion Research: Regular Articles. Volume 3, S1009 (2008) EFDA-Fed: European federation among fusion energy research laboratories R. Castro, J. Vega, A. Portas, A. Pereira, S. Balme, A. Duarte, H. Fernandes, J. Kadlecsik, P. Lebourg,. A. Neto, F. Oliveira, K. Purahoo, F. Reis, C. Rodríguez, J. Signoret, J. M. Theis, K Thomsen. Campus-Wide Information Systems. Selected papers from the Terena Networking Conference 2008. 25 (5) (2008) 359-373 PAPI based federation as a test-bed for a common security infrastructure in EFDA sites. R. Castro, J. Vega, A. Portas, D.R. López, S. Balme, J.M. Theis, P. Lebourg, H. Fernandes, A. Neto, A. Duarte, F. Oliveira, F. Reis, K. Purahoo, K. Thomsen, W. Schiller and J. Kadlecsik Fusion Engineering and Design 83 (2008) 486-490 Progress of the ITER equatorial vis/IR wide angle viewing system optical design M. Davi, Y. Corre, D. Guilhem, F. Jullien, R. Reichle, S. Salasca, J. M. Travère, E. de la Cal, A. Manzanares, J. L. de Pablos, and J. B. Migozz Review of Scientific Instruments, 79, 10F509, 2008 Classifier based on support vector machines for JET plasma configurations S. Dormido-Canto, G. Farias, J. Vega, R. Dormido, J. Sánchez, N. Duro, H. Vargas, A. Murari and JET-EFDA Contributors Review of Scientific Instruments. 79, 10F326 (2008) Structural pattern recognition methods based on string comparison for fusion databases. S. Dormido-Canto, G. Farias, R. Dormido, J. Vega, J. Sánchez, N. Duro, H. Vargas, G. Rattá, A. Pereira, A. Portas Fusion Engineering and Design, Volume 83, Issues 2-3, April 2008, Pages 421-424 Data management at JET with a look forward to ITER J. W. Farthing, T. Budd, A. J. Capel, N. Cook, A. M. Edwards, R. Felton, F. S. Griph, E. M. Jones, R. A. Layne, P. A. McCullen, D. McDonald, M. R. Wheatley, M. Greenwald, J. B. Lister, J. Vega and EFDA-JET Contributors. Proceedings of the ICALEPCS07 Conference. ECCD experiments in the TJ-II Stellarator. A.Fernández, A.Cappa, F.Castejón, JM.Fontdecaba and K.Nagasaki Fusion Science and Technology. Vol. 53. 254-260 (2008) Studies of the removal of hydrogenated carbon films by nitrogen glow discharges J.A. Ferreira, F.L. Tabarés Journal of Physics: Conference Series 100 (2008) 062026


Parametric Dependence of the Perpendicular Velocity Shear Layer Formation in TJ-II Plasmas. L. Guimarais, T. Estrada, E. Ascasíbar, M.E. Manso, L. Cupido, T. Happel, E. Blanco, F. Castejón, R. Jiménez-Gómez, M.A. Pedrosa, C. Hidalgo, I. Pastor and A. López-Fraguas. Plasma and Fusion Research: Regular Articles. Volume 3, S1057 (2008). First experimental observation of a two-step process in the development of the edge velocity shear layer in a fusion plasma T. Happel, T. Estrada, C. Hidalgo Europhys. Letters, 84, 65001 (2008) Microstructural and electrical features of lithium Ce-monazite. T. Hernández, R. Vila, J.R. Jurado, E. Chinarro, J. Molla, P. Martín. Solid State Ionics 179 (2008) 256–262 Herranz, Castejón, and Pastor Reply J. Herranz, F. Castejón, and I. Pastor Physical Review Letters 101, (2008) 139504 Effect of the Phosphorous/Cerium Ratio in the Properties of Sintered Ce-Monazite. T. Hernández and P.Martín Journal of Alloys and Compounds 466 (2008) 568–575 Formation, sustainment and characteristics of current hole plasmas in DIII-D discharges. R.J. Jayakumar, M.A. Austin, C.M. Greenfield, N.C. Hawkes, J.E. Kinsey, L.L. Lao, P.B. Parks, E.R. Solano and T.S. Taylor Nucl. Fusion 48 (2008) 015004 (15pp) A Flexible Luminescent Probe to Monitor Fast Ions Losses at the Edge of the TJ-II Stellarator D. Jiménez-Rey, B. Zurro, J. Guasp, M. Liniers, A. Baciero, M. García-Muñoz, A. Fernandez, G. Garcia, L. Rodríguez-Barquero y J.M. Fontdecaba. Rev. Sci. Instrum, 79, 9 (2008). Ionoluminescent response of several phosphor screens to keV ions of different masses D. Jiménez-Rey, B. Zurro, G. García, A. Baciero, L. Rodríguez-Barquero, M. García-Muñoz J. Appl. Phys. 104, 6 (2008) The response of a radiation resistant ceramic scintillator(Al2O3:Cr) to low energy ions (0–60 keV) D. Jiménez-Rey, B. Zurro, K. J. McCarthy, G. García, and A. Baciero Review of Scientific Instruments, 79, 10E516 (2008) Full-wave calculation of the O-X-B mode conversion of Gaussian beams in a cylindrical plasma. A. Köhn, A. Cappa, E. Holzhauer, F. Castejón, A. Fernández and U. Stroth Plasma Phys. Control. Fusion 50 (2008) 085018 (17pp) Active control of type-I edge localized modes on JET Y Liang, H R Koslowski, P R Thomas, E Nardon, S Jachmich, B Alper, P Andrew, Y Andrew, G Arnoux, Y Baranov, M Bécoulet, M Beurskens, T Biewer, M Bigi, K Crombe, E


De La Luna, P de Vries, T Eich, H G Esser, W Fundamenski, S Gerasimov, C Giroud, M P Gryaznevich, D Harting, N Hawkes, S Hotchin, D Howell, A Huber, M Jakubowski, V Kiptily, A Kreter, L Moreira, V Parail, S D Pinches, E Rachlew, O Schmitz, O Zimmermann and JET-EFDA Contributors Plasma Phys. Control. Fusion 49 No 12B (December 2007) B581-B589 Development of steady-state scenarios compatible with ITER-like wall conditions X Litaudon, G Arnoux, M Beurskens, S Brezinsek, C D Challis, F Crisanti, P C DeVries, C Giroud, R A Pitts, F G Rimini, Y Andrew, M Ariola, Yu F Baranov, M Brix, P Buratti, R Cesario, Y Corre, E De La Luna, W Fundamenski, E Giovannozzi, M P Gryaznevich, N C Hawkes, J Hobirk, A Huber, S Jachmich, E Joffrin, H R Koslowski, Y Liang, Th Loarer, P Lomas, T Luce, J Mailloux, G F Matthews, D Mazon, K McCormick, D Moreau, V Pericoli, V Philipps, E Rachlew, S D A Reyes-Cortes, G Saibene, S E Sharapov, I Voitsekovitch, L Zabeo, O Zimmermann, K D Zastrow and the JET-EFDA Contributors Plasma Phys. Control. Fusion 49 No 12B (December 2007) B529-B550 Thermal stability of neutron irradiation effects on KU1 fused silica. M. León, P. Martín, D. Bravo, F.J. López, A. Ibarra, A. Rascón, F. Mota J. Nucl Mater. 374 (2008) 386-389 Vacuum ultraviolet excitation of the 4.4 eV emission band in neutron irradiated KU1 and KS-4Vquartz glasses. León, M., Martín, P., Vila, R., Molla, J., Roman, R., Ibarra, A. Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms 266 (12-13), pp. 2928-2931, 2008 Implementation of local area network extension for instrumentation standard trigger capabilities in advanced data acquisition platforms J. M. López, M. Ruiz, E. Barrera, G. de Arcas, and J. Vega Review of Scientific Instruments. 79, 10F335 (2008) Tracking magnetic resonances in the effective electron heat diffusivity of ECH plasmas of the TJ-II Heliac. López-Bruna, D., Estrada, T., Medina, F., De La Luna, E., Romero, J.A., Ascasíbar, E., Castejón, F., Vargas, V.I. Europhysics Letters 82 (6), art. no. 65002 Plasma Diagnostics for Magnetic Fusion Research. Chapter 3: Microwave Diagnostics N. C. Luhmann, Jr., H. Bindslev, H. Park, J. Sanchez, G. Taylor, C. X. Yu Fusion Science and Technology. Volume 53, Number 2, February 2008, Pages 335-396 The interactive European GRID: project objectives and achievements. J. Marco, F. Castejon, J.M.Reynolds, F. Serrano, R. Valles, A. Tarancon, J.L. Velasco et al. Computing and Informatics, Vol. 27, 2008, 161-171 A compact flexible pellet injector for the TJ-II stellarator K.J. McCarthy, S.K. Combs, L.R. Baylor, J.B.O. Caughman, D.T. Fehling, C.R. Foust, J.M. McGill, J.M. Carmona and D.A. Rasmussen Review of Scientific Instruments 79, 10F321 (2008)


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Ibercivis: la ciencia en casa. A. Medialdea, F. Castejón Boletín del Colegio Oficial de Físicos. Julio-Agosto, 2008 Workflow-based data parallel applications on the EGEE production grid J. Montagnat, I. Campos Plasencia, F. Castejón, T. Glatard, X. Pennec, G. Taffoni, V. Voznesensky, and C. Vuerli Journal of Grid Computing, 2008. DOI 10.1007/s10723-008-9108-x Molecular Dynamice study of defect in amorphous silica; generation and migration F.Mota, J.Molla, M-J. Caturla, A. Ibarra, J.M. Perlado. Journal of Physics: Conference Series 112 (2008) 032032 How to extract information and knowledge from fusion massive databases. A. Murari, J. Vega, J. A. Alonso, E. de la Luna, J. Farthing, C. Hidalgo, G. A. Rattá, J. Svensson, G. Vagliasindi and JET EFDA Contributors. Burning Plasma Diagnostics. AIP Conference Proceedings (ISBN 978-0-7354-0507-3). 988 (2008) 457-470. New Information Processing Methods for Control in Magnetically Confinement Nuclear Fusion A. Murari, J. Vega, G. de Arcas, G. Vagliasindi Computational Intelligence in Decision and Control. Proc.of the 8th International FLINS Conference. 1 (2008) 921-926 ECCD Experiments in Heliotron J, TJ-II, CHS, and LHD K. Nagasaki, G. Motojima, A. Fernández, A. Cappa, J.M. Fontdecaba, Y. Yoshimura, T. Notake, S. Kubo, T. Shimozuma, H. Igam, K. Ida, M. Yoshinuma, T. Kobuchi, Heliotron J Team, TJ-II Team, CHS Team and LHD Team Plasma and Fusion Research: Regular Articles Volume 3, S1008 (2008) Evidence of long-distance correlation of fluctuations during edge transitions to improved-confinement regimes in the TJ-II stellarator. Pedrosa, M.A., Silva, C., Hidalgo, C., Carreras, B.A., Orozco, R.O., Carralero, D. Physical Review Letters 100 (2008), art. no. 215003 Optimized search strategies to improve structural pattern recognition techniques A. Pereira, J. Vega, A. Portas, R. Castro, A. Murari and JET-EFDA Contributors Computational Intelligence in Decision and Control. Proc.of the 8th International FLINS Conference. 1 (2008) 405-410 Feature extraction for improved disruption prediction analysis at JET G. A. Rattá, J. Vega, A. Murari, M. Johnson and JET-EFDA Contributors Review of Scientific Instruments. 79, 10F328 (2008) First applications of structural pattern recognition methods to the investigation of specific physical phenomena at JET. G.A. Rattá, J. Vega, A. Pereira, A. Portas, E. de la Luna, S. Dormido-Canto, G. Farias, R. Dormido, J. Sánchez, N. Duro, H. Vargas, M. Santos, G. Pajares, A. Murari and JET-EFDA Contributors


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Fusion Engineering and Design, Volume 83, Issues 2-3, April 2008, Pages 467-470 Solar sintering of alumina ceramics: Microstructural development. R. Román, I. Cañadas, J. Rodríguez, M.T. Hernández, M. González Solar Energy 82 (2008) 893–902 Study of plasma formation within the electrostatic residual ion dump proposed for the HNB injectors of ITER L. Rossi, F. Castejón and C. Moreno Nucl. Fusion 49 (2009) 015002 (11pp) Data reduction in the ITMS system through a data acquisition model with self-adaptive sample frequency. M. Ruiz, JM. López, G. de Arcas, E. Barrera, R. Melendez and J. Vega. Fusion Engineering and Design, Volume 83, Issues 2-3, April 2008, Pages 358-362 An event-oriented database for continuous data flows in the TJ-II environment. E. Sánchez, A. de la Peña, A. Portas, A. Pereira, J. Vega, A. Neto and H. Fernandes Fusion Engineering and Design, Volume 83, Issues 2-3, April 2008, Pages 413-416 Neutron induced activation in the EVEDA Accelerator materials: Implications for the accelerator maintenance J. Sanz, M. García, P. Sauvan, D. López, C. Moreno, A. Ibarra et al. Journal of Nuclear Materials (2008), doi: 10.1016/j.jnucmat.2008.12.277 Optimization of energy confinement in the 1/m regime for stellarators B. Seiwald, S.V. Kasilov, W. Kernbichler, V.N. Kalyuzhnyj, V.V. Nemov, V. Tribaldos c, J.A. Jiménez Journal of Computational Physics 227 (2008) 6165–6183 ELMs and strike point movements. E.R. Solano, S. Jachmich, F. Villone, N. Hawkes, Y. Corre, B. Alper, A. Loarte, R.A. Pitts, K. Guenther, A. Korotkov, M. Stamp, P. Andrew, J. Conboy, T. Bolzonella, M. Kempenaars, A. Cenedese, E. Rachlew and JET EFDA contributors Nucl. Fusion 48 (2008) 065005 (12pp) Plasma performance and confinement in the TJ-II stellarator with Li-coated walls F.L.Tabarés et al. Plasma Phys. Control. Fusion 50 (2008) 124051 Cleaning efficiency of carbon films by oxygen plasmas in the presence of metallic getters. F L Tabarés, J A Ferreira, D Tafalla, I Tanarro, V Herrero, I Méndez, C Gómez-Aleixandre and J M Albella J. Physics: Conf. Series 100 (2008) 062025 Bicoherence during confinement transitions in the TJ-II stellarator B.Ph. van Milligen, T. Kalhoff, C. Hidalgo, and M.A. Pedrosa Nucl. Fusion 48 (2008) 115003


Continuous time random walks in finite domains and general boundary conditions: Some formal considerations. Van Milligen, B.Ph., Calvo, I., Sánchez, R. Journal of Physics A: Mathematical and Theoretical 41 (2008), art. no. 215004 Quantifying profile stiffness. B.Ph. van Milligen, R. Sánchez, V. Tribaldos, and V.I. Vargas. Plasma and Fusion Research, Vol. 3 (2008) S1070 Data mining technique for fast retrieval of similar waveforms in fusion massive databases. J. Vega, A. Pereira, A. Portas, S. Dormido-Canto, G. Farias, R. Dormido, J. Sánchez, N. Duro, M. Santos, E. Sánchez and G. Pajares Fusion Engineering and Design, Volume 83, Issue 1, January 2008, Pages 132-139 Development of learning systems with data tours techniques for fusion databases J. Vega, G. A. Rattá, P. Castro, A. Murari and JET-EFDA Contributors. Computational Intelligence in Decision and Control. Proc.of the 8th International FLINS Conference. 1 (2008) 103-108 Intelligent methods for data retrieval in fusion databases. J. Vega and JET-EFDA Contributors Fusion Engineering and Design, Volume 83, Issues 2-3, April 2008, Pages 382-386 Intelligent Technique to Search for Patterns within Images in Massive Databases J. Vega, A. Murari, A. Pereira, A. Portas, P. Castro and JET-EFDA Contributors Review of Scientific Instruments. 79, 10F327 (2008) Structural pattern recognition techniques for data retrieval in massive fusion databases. J. Vega, A. Murari, G. A. Rattá, P. Castro, A. Pereira, A. Portas and JET EFDA Contributors. Burning Plasma Diagnostics. AIP Conference Proceedings (ISBN 978-0-7354-0507-3). 988 (2008) 481-484. Ion heating in transitions to CERC in the stellarator TJ-II. Velasco, J.L., Castejón, F., Fernández, L.A., Martin-Mayor, V., Tarancón, A., Estrada, T. Nucl. Fusion 48 (2008) 065008 (10pp) An experimental system for spectral line ratio measurements in the TJ-II stellarator B. Zurro, A. Baciero, J. M. Fontdecaba, R. Peláez, and D. Jiménez-Rey Rev. Sci. Instrum. 79 10F540 (2008)


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2. Technical reports

Magnetic system design for the ITER MRID. EFDA Task: TW6-THHN-NBD1. Julio 2008 A. López-Fraguas, and J. Lucas Beam diagnostics for IFMIF-EVEDA CIEMAT-IN-IF-ACBI-001. 25 Enero 2008 I. Podadera and B. Brañas IFMIF beam profile monitoring using miniature fission chambers EFDA Report. Task TW6-TTMI-003 D6. November, 2008 D. Rapisarda EPP Hydraulic Analysis & BSM Attachment UPP Kinematics Study. EFDA task: TW6-TPDS-DIASUP/1430. Junio 2008. E. Rincón, G. Veredas, J. Botija, M. Medrano Study of plasma formation within the electrostatic residual ion dump proposed for the HNB injectors of ITER EFDATask: TW6-THHN-NBD1 L. Rossi, C. Moreno, F. Castejón, M. Liniers. FALTA Final Report on EFDA Task. TW6-TPP- GAPOX. Deliverable 3. Task coordinator: F.L. Tabarés ITER neutral beam remote handling maintenance design EFDA task reference: TW6-TVR-NBRH. Febrero 2008. ITA task reference: ITA 23-30 G.Taubmann, L.Brochet, O.Piñeiro, X.Sarasola, M.Liniers,M. Medrano, J.Botija, J.Alonso.


3. Conferences and Workshops

10th ITPA meeting on SOL/divertor physics. Toledo, Spain. January 7-10, 2008 1. Use of of scavenger gases for C layer inhibition:last results.

F.L.Tabarés Large Scale Simulations of Complex Systems, Condensed Matter and Fusion Plasma III BIFI International Congress, Zaragoza, Spain. 6-8 Febrero, 2008. http://bifi.unizar.es/events/bifi2008/ 1. Kinetic simulation of heating and collisional transport in a 3D tokamak.

A. Bustos, F. Castejón, L.A. Fernández, V. Martín-Mayor, A.Tarancón, J.L. Velasco 2. The search for a flux-expansion divertor in TJ-II

F. Castejón, A. López-Fraguas, A. Tarancón, and J.L. Velasco 3. Nondiffusive transport in plasma turbulence.

L. García, B.A. Carreras, L.A. Fernández, V. Martín-Mayor, D. Yllanes, I. Calvo, B.Ph. van Milligen, D. Newman, and R. Sánchez

4. A new code for collisional drift kinetc equation solving

J. M. Reynolds, D. López-Bruna, J. Guasp, J. L. Velasco, A. Tarancón. AIP Conf. Proc. November 2, 2008 – Volume 1071, pp. 72-81

5. Ion kinetic transport in TJ-II

J.L. Velasco, F. Castejón, L.A. Fernández, V. Martin-Mayor and A. Tarancón EGEE08 Meeting. Enabling Grid for E-Science. 11-14 Febrero 2008 http://www.eu-egee.org/ 1. Fusion Demo.

F. Castejón, V. Voznesenski 2. Fusion results with EGEE.

F. Castejón Workshop on ‘New Technologies and Innovative Processing Methods for Imaging in Fusion Devices’. 18th – 20th February 2008. Culham Science Center. UK. 1. Pattern Recognition for Image Processing

J. Vega 2. Lossless, advanced data compression techniques for images

J. Vega.


http://bifi.unizar.es/events/bifi2008/

http://scitation.aip.org/proceedings

http://scitation.aip.org/dbt/dbt.jsp?KEY=APCPCS&Volume=1071

http://www.eu-egee.org/

15th Joint Workshop on Electron Cyclotron Emission and Electron Cyclotron Resonance Heating. Marzo 2008. California, EE.UU. http://fusion.gat.com/conferences/ec-15/ 1. Recent ECCD experiments in the TJ-II stellarator.

A.Fernández, A.Cappa, JM.Fontdecaba, F.Castejón and K.Nagasaki 2. Linear estimation of electron Bernstein current drive.

J.M. García-Regaña, F.Castejón 3. Summary of EBW theoretical calculations in the TJ-II stellarator.

A.Cappa, F.Castejon, D.Lopez-Bruna, A.Fernández, M.Terhschenko et al. 4. ECCD experiments in Stellarator/Heliotron.

K.Nagasaki, G.Motojima, A.Fernández, A.Cappa et al. 5. Electron Bernstein Waves Emission Studies on the TJ-II Stellarator.

J.Caughman, A.Fernández, A.Cappa, F.Castejón et al. 17th Topical Conference on High Temperature Plasma Diagnostics. May 11-15, 2008. Albuquerque. New Mexico. (USA). http://www.esc.sandia.gov/htpd08/htpd08ConferenceInfo.html 1. Self adaptive sampling rate for data acquisition in JET’s correlation reflectometer

G. de Arcas, J. M. López, M. Ruiz, E. Barrera, J. Vega, A. Murari, A. Fonseca and JET EFDA contributors. FALTA

2. Classifier based on support vector machines for JET plasma configurations

S. Dormido-Canto, G. Farias, J. Vega, R. Dormido, J. Sánchez, N. Duro, H. Vargas, A. Murari and JET-EFDA Contributors.

3. The response of a radiation resistant ceramic scintillator (AL2O3:Cr) to low energy ions

(0-60 keV) D. Jiménez-Rey, B. Zurro, K.J. McCarthy, G. Garcia, A. Baciero (2008).

4. Implementation of local area network extension for instrumentation standard trigger

capabilities in advanced data acquisition platforms J. M. López, M. Ruiz, E. Barrera, G. de Arcas, and J. Vega. FALTA

5. Feature extraction for improved disruption prediction analysis at JET

G. A. Rattá, J. Vega, A. Murari, M. Johnson and JET-EFDA Contributors. 6. Intelligent Technique to Search for Patterns within Images in Massive Databases

J. Vega, A. Murari, A. Pereira, A. Portas, P. Castro and JET-EFDA Contributors. Terena Networking Conference 2008. 19th – 22nd May 2008. Bruges (Belgium). (http://tnc2008.terena.org/)


http://fusion.gat.com/conferences/ec-15/

http://www.esc.sandia.gov/htpd08/htpd08ConferenceInfo.html

http://tnc2008.terena.org/

1. EFDA-Fed: European federation among fusion energy research laboratories

R. Castro, J. Vega, A. Portas, A. Pereira, C. Rodriguez, S. Balme, J. M. Theis, J. Signoret, P. Lebourg, K. Purahoo, K Thomsen, W. Schiller, H. Fernandes, A. Neto, A. Duarte, F. Oliveira, F. Reis, J. Kadlecsik. FALTA

18th International Conference on Plasma Surface Interactions. 26-30 mayo, 2008. Toledo, España. http://psi2008.ciemat.es/ 1. Fast visible imaging of ELM wall interactions on JET

J.A. Alonso, P. Andrew, A. Neto, J.L. de Pablos, E. de la Cal, H. Fernandes, W. Fundamenski , C. Hidalgo, G. Kocsis, A. Manzanares, A. Murari, G. Petravich, R.A. Pitts, L. Rios, C. Silva, EFDA-JET contributors

2. The scavenger effect . Does it work?

W. Bohmeyer, F.L Tabares et al 3. Turbulence and Dust studies by Fast Camera Imaging Experiments in the TJ-II

Stellarator D. Carralero, E. de la Cal, J. L. de Pablos, A. de Coninck, J.A. Alonso, C. Hidalgo, B Ph van Milligen, M.A. Pedrosa

4. Optimization of non-oxidative carbon-removal techniques by nitrogen-containing

plasmas J.A. Ferreira, F.L. Tabarés and D. Tafalla

5. Determination of edge Ti profiles by means of a supersonic He beam in TJ-II

F. Guzman,F.L. Tabares, D. Tafalla,I.García-Cortés,R. Balbín 6. Impact of lithium-coated walls on plasma performance in the TJ-II stellarator.

J. Sanchez, TJ-II Team 7. Injection of hydrocarbon molecular beams in the TJ-II stellarator

F.L. Tabarés, D. Tafalla , J.A Ferreira, I. García-Cortés, N. Ordoñs and C. Garcia Rosales

8. Removal of carbon films by oxidation in narrow gaps: Thermo-oxidation and Plasma-

Assisted studies I. Tanarro, J. A. Ferreira, V. Herrero, F.L. Tabarés and C. Gómez-Aleixandre

International Conference in Electron Microscopy in Solids. Cracovia, Polonia. Junio 8-11, 2008. http://www.em2008.agh.edu.pl/ 1. Analysis of damaged region of carbon implanted alumina.

M. González, R. Román, J. González-Casablanca, A. Gomez and D. Hole.


http://psi2008.ciemat.es/

http://www.em2008.agh.edu.pl/

35th EPS Plasma Physics Conference. 9-13 Junio 2008, Creta, Grecia. http://eps2008.iesl.forth.gr/ 1. Measurement of carbon ion emissions from TJ-II stellarator plasmas and their relation

with plasma properties. A. Baciero, B. Zurro, D. Jiménez-Rey, R.J. Peláez

2. Comparison of the inboard and outboard type I ELM dynamics in JET.

L. Barrera, E. de la Luna, F. Castejon, L. Figini and JET-EFDA 3. Kinetic Simulations of ion Heating and Collisional Transport in a 3D Tokamak.

A.Bustos, F.Castejón, L.A. Fernández, V. Martín-Mayor, A.Tarancón, J.L.Velasco 4. Fractional generalization of Fick’s law: derivation through Continuous-Time Random

Walks. I. Calvo, R. Sánchez, B. A. Carreras and B. Ph. van Milligen

5. Pseudochaotic poloidal transport in toroidal geometry. Pressure-gradient-driven

turbulence and plasma flow topology. I. Calvo, L. Garcia, B. A. Carreras, R. Sanchez, B. Ph. van Milligen

6. Fast Imaging Experiments of Edge Transport in the TJ-II Stellarator.

D. Carralero, E. de la Cal, J.L. de Pablos, J.A. Alonso, M.A. Pedrosa, C. Hidalgo 7. Island healing and CERC formation in the TJ-II stellarator.

F. Castejón, D. López-Bruna and T. Estrada 8. Velocity shear layer formation and turbulence correlation characteristics measured by

reflectometry in TJ-II. T.Estrada, L.Guimarais, T.Happel, E.Blanco, L.Cupido, M.E.Manso

9. Nondiffusive transport in plasma turbulence.

L. Garcia, J.A. Mier, R. Sanchez, B.A. Carreras, I. Calvo, D.E. Newman 10. Linear Estimation of Electron Bernstein Current Drive (EBCD) in inhomogeneous

plasmas. J. M. García-Regaña, F. Castejón, A. Cappa, M. Tereshchenko

11. Radial propagation of poloidal plasma velocity changes in the stellarator TJ-II measured

by reflectometry. T. Happel, T. Estrada, L. Cupido, C. Hidalgo, E. Blanco

12. Fast Ion Losses Behaviour in the TJ-II stellarator.

D. Jiménez-Rey, B. Zurro, J. Guasp, M. Liniers, C. Fuentes, G. Garcia, L. Rodríguez-Barquero, A. Baciero, A. Fernández, A. Cappa, R. Jiménez-Gómez and TJ-II Team

13. Status of the International Stellarator/Heliotron Profile Database

A. Kus, D. Pretty, E. Ascasibar, C.D. Beidler, B. D. Blackwell, R. Brakel, R. Burhenn, F. Castejon, A. Dinklage, T. Estrada, Y. Feng, A. Fujisawa, H. Funaba, J. Geiger, J.H.


http://eps2008.iesl.forth.gr/

Harris, C. Hidalgo, K. Ida, M. Kobayashi, R. König, G. Kühner, D. López Bruna, H. Maaßberg, K. McCarthy, D. Mikkelsen, T. Minami, T. Mizuuchi, S. Murakami, N. Nakajima, S. Okamura, R. Preuss, S. Sakakibara, F. Sano, F. Sardei, T. Shimozuma, U. Stroth, Y. Suzuki, Y. Takeiri, J. Talmadge, H. Thomsen, Yu. A. Turkin, J. Vega, K.Y. Watanabe, A. Weller, A. Werner, R. Wolf, H. Yamada, M. Yokoyama, 9 - 13 June 2008 ECA Vol. 32, P-2.113 (2008)

14. Effect of magnetic resonances in the effective electron heat transport of TJ-II ECH

plasmas. D. Lopez-Bruna, T. Estrada, F. Medina, E. de la Luna, E. Ascasibar, F. Castejon, V. I. Vargas

15. Long-distance correlations of fluctuations and sheared flows during transitions to

improved confinement regimes in the TJ-II stellarator. M.A. Pedrosa, C. Silva, C. Hidalgo, D. Carralero, B.A. Carreras, R.O. Orozco and the TJ-II team

16. Damage, Fluidynamics and Tritium handling in IFE reactors.

J,M. Perlado, M.J.Caturla, A..Abanades, C.Arevalo, D.Diaz, L.Gámez, B.Gamez, Y.Herreras, A.Lafuente, J.Marian, E.Martínez, F.Mota, C,Ortiz, E.delRio, F.Sordo, M.Velarde, M.Victoria, T.Villar

17. Simulating drift kinetic electron-ion equation with collisions in complex geometry.

J.M. Reynolds, D. Lopez-Bruna, J. Guasp, J.L. Velasco, A. Tarancon 18. A study of radial tracer transport in a turbulent transport code.

G. Sánchez Burillo, B. Ph. van Milligen, A. Thyagaraja 19. Plasma performance and confinement in the TJ-II stellarator with lithium-coated walls.

F. Tabarés and TJ-II team

20. Bicoherence and confinement transitions in TJ-II.

B.Ph. van Milligen, T. Kalhoff, M.A. Pedrosa, C. Hidalgo. in Contr. Fusion and Plasma Phys. (Proc. 35th Eur. Conf. Hersonissos, 2008), Vol. 32D, European Physical Society (2008), P2-021

21. ECH power dependence of electron heat diffusion in ECH plasmas of the TJ-II

stellarator. V.I. Vargas, D. López-Bruna, J. García, A. Fernández, A. Cappa, J. Herranz, F. Castejón

22. Non-diffusive effects in ion collisional transport in TJ-II.

J.L. Velasco, F. Castejón, A. Tarancón 23. An Investigation on the Mechanisms for Differential Poloidal Rotation of Proton and

Impurities in the TJ-II Stellarator. B. Zurro, A. Baciero, V. Tribaldos, D. Jiménez-Rey

19th International Conference on Spectral Line Shapes, 15-20. Junio, 2008. Valladolid


1. An Overview of Rotation and Ion Temperature. Measurements of Impurities and

Hydrogen by Passive Emission Spectroscopy in the TJ-II Stellarator A. Baciero, B. Zurro, D. Rapisarda, V.Tribaldos, D. Jiménez-Rey and the TJ-II team

Remote participation Workshop. 23rd – 24th June 2008. Padova (Italy) 1. On-line diagnostic monitoring in JET

J. Vega, K. Kneupner, R. Castro, G. de Arcas, E. Barrera, J. W. Farthing, A. Fonseca, S. Griph, P. Heesterman, O. Hemming, D. Kinna, R. Lane, J. M. López, A. Murari, A. Pereira, A. Portas, M. Rainford, M. Ruiz, C. Tidy, M. Wheatley. FALTA

11th European Particle Accelerator Conference (EPAC). Genova, Italia. Junio 23-27, 2008. http://www.epac08.org/ 1. IFMIF-EVEDA Accelerator: Beam Dump Design.

B. Brañas, D. Iglesias, F. Arranz, J. Gómez , C. Oliver, G. Barrera, A. Ibarra 2. RF power system for the IFMIF-EVEDA prototype accelerator.

I. Kirpitchev, P. Méndez, M. Weber, A. Ibarra, M.A. Falagán, M. Desmons, A. Mosnier. 3. Radiological Hazards Assessment for the Beam Dump of High Intensity Deuteron

Accelerators. D. López, M. García, J. Sanz, F. Ogando, P. Salvan

4. The IFMIF-EVEDA Accelerator Activities.

Mosnier, A. Ibarra, A. Facco. 5. High energy beam transport line for the IFMIF-EVEDA Accelerator.

C. Oliver, B. Brañas, A. Ibarra, I. Podadera, N. Chauvin, A. Mosnier, P. Nghiem, D. Uriot.

6. A diagnostics plate for the IFMIF-EVEDA Accelerator.

I. Podadera, B. Brañas, J.M. Carmona, A. Ibarra, C. Oliver, PY Beauvais, J. Marroncle, A. Mosnier.

7th symposium "SiO2 , advanced dielectrics and related devices". Saint-Etienne, 30 junio-2 julio, 2008. http://sio2-2008.univ-st-etienne.fr/ 1. Vacuum ultraviolet excitation of the 2.7 eV emission band in neutron irradiated silica.

M. León, P. Martín, R.Vila, J. Molla, and A.Ibarra


http://www.epac08.org/

http://sio2-2008.univ-st-etienne.fr/

19th Europhysics Conference on teh Atomic and Molecular Physics of Ionized Gases (ESCMPIG) Granada. Julio 2008 1. Characterization of Minory Species in Reactive Plasma by Cryotrap-Assisted Mass

Spectrometry F.L.Tabarés and J.A. Ferreira

SEWG Meeting JET 22-23 July 2008 http://130.183.3.16/efda/__page__list__det.php?articleID=375&sectionID=47&openMenu=menu3outline 1. Nitrogen Injection Experiments in JETand extrapolation to ITER.

F.L. Tabarés 2. Injection of hydrocarbon molecular beams in TJ-II

F.L. Tabarés 7th International Workshop on Strong Microwaves in Plasmas. Nizhny Novgorod (Russia) Julio- Agosto 2008. http://www.smp.sci-nnov.ru/ 1. New possibilities of small reflected modulated signal influence on the gyrotron output

radiation. A.Fernández, N.Khartchev et al

2. Recent results of the TJ-II EC heating systems.

JM.Fontdecaba, A.Fernández, A.Cappa et al. HB 2008. 42nd ICFA Advanced Beam Dynamics Workshop on High-Intensity, High-Brightness Hadron Beams. Tennessee, EE.UU., 25-29 Agosto, 2008. http://neutrons.ornl.gov/workshops/hb2008/ 1. HEBT Diagnostics for Commissioning, Control and Characterization of the IFMIF-

EVEDA Accelerator. I. Podadera

Electroceramics XI. Manchester, UK. Agosto 31- Septiembre 4, 2008. https://www.meeting.co.uk/confercare/electroceramicsxi/index.htm 1. On the Electrical Conductivity of a Biphasic Lithium Silicate

T. Hernández, E. Chinarro, B.Moreno, J.R. Jurado, A. Moroño and E.R. Hodgson 16th Internacional Conference on Ion Beam Modification of Materials (IBMM). Dresden, Alemania. Agosto 31- Septiembre 5, 2008. http://www.ibmm2008.org/frs_index_html.asp


http://130.183.3.16/efda/__page__list__det.php?articleID=375&sectionID=47&openMenu=menu3outline

http://130.183.3.16/efda/__page__list__det.php?articleID=375&sectionID=47&openMenu=menu3outline

http://www.smp.sci-nnov.ru/

http://neutrons.ornl.gov/workshops/hb2008/

https://www.meeting.co.uk/confercare/electroceramicsxi/index.htm

http://www.ibmm2008.org/frs_index_html.asp

1. A complete chemical and structural characterization of the damaged region of a carbon

implanted alumina. M. González, R. Román, C. Maffiotte, J. González-Casablanca, R. Perez and D. Hole.

13th EU-US TTF Workshop. 1-4 Septiembre. Copenage, Dinamarca. http://risoe.dtu.dk/Conferences/~/media/Risoe_dk/Conferences/EUUS_TTF/Documents/Final_Announcement_13th%20%20EU_fin%20%202.ashx 1. On the statistical properties of radial correlation lengths in tokamaks and stellarators

T. Estrada, E. Blanco, T. Happel and C. Hidalgo, L. Cupido, A. Fonseca, L Guimarais, M. E. Manso

2. Long-distance correlations of fluctuations during sheared flows development in TJ-II

edge plasma. M.A. Pedrosa, C. Hidalgo, I. Calvo, D. Carralero, C. Silva, B. A. Carreras and the TJ-II team

3. Tracers as plasma diagnostic

G. Sanchez-Burillo, B.Ph. van Milligen, A. Thyagaraja and C. Hidalgo 1st IFMIF Workshop. 11, 12 y 13 de septiembre, FZK, Karlsruhe, Alemania 1. HEBT (9 MeV) and Beam Dump (WBS 4.8.0). Status mid 2008. Work Programme 2009.

B. Brañas, D. Iglesias ,C. Oliver 2. Beam Instrumentation (WBS 4.9.0). Technical issues.

J.M. Carmona, I. Podadera 3. Liquid Breeder Validation Test Module: Status and Workprogramme 2009

N. Casal 4. Requirements for the Test Cell imposed by different types of experiments in TRM

N. Casal 5. RF Power System (WBS 4.10.0). Status mid 2008, possible industrial breakdown. Work

Program 2009 P. Méndez, I. Kirpitchev, A. Ibarra, M. Weber

6. RF Power System (WBS 4.10.0). Technical issues

P. Méndez, I. Kirpitchev, A. Ibarra, M. Weber 7. Detailed objectives of Validation activities: Validation tests of Test Facilities and their

integration J. Mollá and Project Team


http://risoe.dtu.dk/Conferences/%7E/media/Risoe_dk/Conferences/EUUS_TTF/Documents/Final_Announcement_13th%20%20EU_fin%20%202.ashx

http://risoe.dtu.dk/Conferences/%7E/media/Risoe_dk/Conferences/EUUS_TTF/Documents/Final_Announcement_13th%20%20EU_fin%20%202.ashx

8. Interface between D+ Beam, Lithium Target and Test Modules. Introduction on the elaboration of a methodology J. Mollá, F. Groeschel.. Ch. Vermare.

9. HEBT (9 MeV) and Beam Dump (WBS 4.8.0). Status of the design of the HEBT,

including bending magnets loss. Status of the design of the Beam Dump C. Oliver et al.

10. Beam Instrumentation (WBS 4.9.0). Status mid 2008. Work Program 2009

I. Podadera, J.M Carmona 11. Overview of the Flow Chart of HFTM Rigs and specimens. A proposal

V. Queral, A. García, A. Ibarra 12. Proposals for the Test Cell conceptual design & RH

V.Queral, A. García, A. Ibarra 13. Remote Handling systems for Test Facilities. Status and Workprogramme 2009

V. Queral, A. García, A. Ibarra 14. Radiation diagnostics: fission ionization chambers Status and Workprogramme 2009

D. Rapisarda

15. Radiation diagnostics: calculations required for the design of the fission chambers

D. Rapisarda 25th Symposium on Fusion Technology (SOFT). Rostock, Alemania. Septiembre 15-19, 2008 http://www.ipp.mpg.de/eng/for/veranstaltungen/soft2008/ 1. Design of a Beam Dump for the IFMIF-EVEDA Accelerator

B. Brañas, D. Iglesias, C. Oliver, F. Arranz, G. Barrera, J. Martínez, J. Figarola, A. Ibarra, J. Sanz

2. Comparison of neutron and gamma irradiation effects on fused silica monitored by

electron paramagnetic resonance D. Bravo, J.C. Lagomacini, M. León, P. Martín, A. Martín, F.J. López, A. Ibarra

3. Tritium permeation experiment at IFMIF Medium Flux Test Module

N. Casal, A. García, A. Ibarra, F. Mota, D. Rapisarda, V. Queral 4. Data distribution architecture based on standard real time protocol

R. Castro, J. Vega, A. Pereira, A. Portas. 5. The magnetics diagnostic set for ITER

R.Chavan, G.Chitarin, R.S.Delogu, A.Encheva, A.Gallo, E.Hodgson, L.C.Ingesson, A.Le-Luyer, J.B.Lister, Ph.Moreau, J-M.Moret, S.Peruzzo, J.Roméro, D.Testa, M.Toussaint, G.Vayakis, R. Vila.


http://www.ipp.mpg.de/eng/for/veranstaltungen/soft2008/

6. Performance of the TJ-II ECRH system with the new -80 kV 50 A high voltage power

supply A.Fernández, J.M.de la Fuente, D.Ganuza, I.Kirpitchev et al

7. Radiation resistant bolometers with Al2O3 and AlN substrates, anodized aluminium

support frames, and improved electrical contacts M. Gonzalez and E. R. Hodgson

8. Configuration and supervision of advanced distributed data acquisition and processing

systems for long pulse experiments using JINI technology J. González, M. Ruiz, E. Barrera, J. M. López, G. de Arcas, J. Vega.

9. Effects of irradiation conditions and environment on the reflectivity of different steel

mirrors for ITER diagnostic systems T. Hernandez, P. Martin, P. Fernandez and E.R. Hodgson CF:1P606

10. TechnoFusion: The Spanish National Centre for Fusion Technologies

A. Ibarra, J.M. Perlado. 11. Neutron irradiation effects on optical absorption of KU1 and KS-4V quartz glasses and

Infrasil 301 M. León, P. Martín, R. Vila, J. Molla and A. Ibarra

12. Design of an overhead crane for the ITER NB cell Remote Handling Maintenance

operations M. Liniers, M. Medrano,G. Taubmann, L. Brochet, ,X. Sarasola, J. Botija, J. Alonso, C. Damián

13. Electrical and optical surface degradation of silica due to superficial He implantation

J. Manzano, A. Moroño, and E.R. Hodgson

14. Commercial dielectric coated mirrors for ITER diagnostic applications

P. Martin, T. Hernandez, and E.R. Hodgson CF: 1P603

15. IFMIF Target assembly: enhancement of the remote handling strategy for the

replaceable backplate bayonet concept G. Miccichè, P. Agostini, A. Ibarra, A. Garcia, V.Queral

16. IFMIF test facilities: Main challenges for final engineering design phase

J. Molla and K. Nakamura 17. BA materials activities: Radiation induced electrical degradation of HP SiC

A. Moroño, R. Vila, T. Hernández, J. Manzano and E.R. Hodgson 18. Status of the IFMIF/EVEDA accelerator

A. Mosnier, A. Ibarra, A. Facco


19. Recent Developments in Data Mining and Soft Computing for JET with a view on ITER

A.Murari, J.Vega, G.Vagliasindi, J.A.Alonso, D.Alves, R.Coelho, S.DeFiore, J.Farthing, C.Hidalgo, G.A.Rattá, and JET-EFDA Contributors

20. Automated recognition system for ELM classification in JET

N. Duro, R. Dormido, J. Vega, S. Dormido-Canto, G. Farias, J. Sánchez, H. Vargas, A. Murari and JET-EFDA Contributors.

21. A real-time current driving control system for the TJ-II

A. de la Peña, L. Pacios, F. Lapayese, R. Carrasco 22. Thermal and mechanical analysis of the ITER plasma-position reflectometry antennas

G. Perez, T. Estrada, G. Vayakis, C. Walter

23. Feasibility study of the cut and weld operations by RH on the cooling pipes of ITER NB

components O. Piñeiro, C. Fernández, M. Medrano, M. Liniers, J. Botija, J. Alonso, X. Sarasola, C. Damiani

24. Proposal of an improved design of IFMIF Test Cell components for enhanced handling

and reliability V. Queral, A. García, G. Miccichè, A. Ibarra, N. Casals, F. Mota, D. Rapisarda

25. Feasibility of a neutron diagnostic for the IFMIF - Test Cell

D. Rapisarda, A. García, A. Ibarra, N. Casal, V. Queral, F. Mota, J. M. Gómez, O. Cabellos, J. Sanz

26. Developing the IFMIF RAM planning

C. Tapia, J. Dies, A. Calvo, J.C. Rivas, A. Ibarra 27. Overview of intelligent data retrieval methods for waveforms and images in massive

fusion databases J. Vega, A. Murari, A. Pereira, A. Portas, G. A. Rattá, R. Castro and JET-EFDA Contributors.

28. A TIEMF model and some implications for ITER magnetic diagnostics

R. Vila and E.R. Hodgson Workshop on Advanced Plasma Technology. Fiesa. Slovenia. 17-19 Septiembre, 2008 http://www.midem-drustvo.si/conf2008/MIDEM-conf2008.htm 1. Optimization of non-oxidative plasma techniques for tritium control in ITER

F.L.Tabarés and F.L. Tabarés


http://www.midem-drustvo.si/conf2008/MIDEM-conf2008.htm

2. Characterization of Helium Plasma Created in an Asymmetric DC Normal Glow Discharge with a Single Langmuir Probe J.A. Ferreira, F.L. Tabarés et al

8th International FLINS Conference 21st – 24th September 2008. Madrid (Spain) (http://www.mat.ucm.es/congresos/flins2008/). 1. Design of an advanced intelligent instrument with waveform recognition based on the

ITMS platform G. de Arcas, J. M. López, M. Ruiz, E. Barrera, J. Nieto, J. Veja, G. A. Rattá, A. Murari.

2. New Information Processing Methods for Control in Magnetically Confinement Nuclear

Fusion A. Murari, J. Vega, G. de Arcas, G. Vagliasindi.

3. Optimized search strategies to improve structural pattern recognition techniques

A. Pereira, J. Vega, A. Portas, R. Castro, A. Murari and JET-EFDA Contributors. 4. Development of learning systems with data tours techniques for fusion databases

J. Vega, G. A. Rattá, P. castro, A. Murari and JET-EFDA Contributors. 18th Topical Meeting on the Technology of Fusion Energy (TOFE). San Francisco, EE.UU. Septiembre 28- Octubre 2, 2008 http://www.18th-tofe.com/ 1. European Contributions to the ITER Licensing

W. Gulden, A. Bengaouer, B. Brañas, W. Breitlung, L. di Pace, E. Di Pietro et al. 2. EVEDA radiological protection studies concerning to the beam dump preliminary design

J. Sanz, M. García, D. López, P. Sauvan, F. Ogando, B. Brañas

3. First IFMIF-EVEDA Radioprotection Studies for the Preliminary Design of the

Accelerator Beam Dump J. Sanz, M. García, F. Ogando, A. Mayoral, D. López, P. Sauvan, B.Brañas

22nd IAEA Conference, 13-18 Octubre 2008, Geneva http://www-pub.iaea.org/MTCD/Meetings/Announcements.asp?ConfID=165 1. Kinetic simulation of heating and collisional transport in a 3D tokamak

A. Bustos, F. Castejón, I. A.Fernández, V. Martín-Mayor, A. Tarancón, J.L. Velasco 2. Flux-expansion divertor studies in TJ-II

F. Castejón, A. López-Fraguas, A. Tarancón, J. L. Velasco, J. Guasp, F. Tabarés, M. A. Pedrosa, E. de la Cal, and M. A. Ochando


http://www.mat.ucm.es/congresos/flins2008/

http://www.18th-tofe.com/

http://www-pub.iaea.org/MTCD/Meetings/Announcements.asp?ConfID=165

3. Characterization of the perpendicular rotation velocity of the turbulence by reflectometry in the stellarator TJ-II T. Estrada, T. Happel, L. Guimarais, E. Blanco, C. Hidalgo, L. Cupido, and M.E. Manso

4. Multi-scale physics during shear flow development in the TJ-II stellarator

C. Hidalgo, M.A. Pedrosa, C. Silva, B. van Milligen, J.A. Alonso, D. Carralero, B.A. Carreras, E. de la Cal, T. Kalhoff, J.L. de Pablos

5. European ITER Site Studies: Lessons learns in Safety and Licensing

J. Izquierdo, E. di Pietro, W. Gulden, ..., B. Brañas, T Pinna et al. 6. Footprint of the Magnetic Configuration in ECH Plasmas of the TJ-I I Flexible Heliac

D. López-Bruna, J. A. Romero, A. López-Fraguas, E. Ascasíbar, R. Jiménez-Gómez, M. Ochando, J. Herranz, F. Medina, M. A. Pedrosa, T. Estrada, T. Kalhoff, F. Castejón, V. I. Vargas, L. Pacios, A. de la Peña, F. Lapayese, J. Alonso, R. Carrasco,

7. Effect of Magnetic Field Ripple on ECCD in Heliotron-J

K.Nagasaki, G.Motojima,..........., A.Fernández, A.Cappa et al 8. Overview of TJ-II experiments

J. Sánchez and the TJ-II Team International Workshop on Computational Algebraic Topology within Image Context, Sevilla, 3-5 de noviembre de 2008 1. Topological characterization of flow structures in plasma turbulence

B. A. Carreras, I. Llerena, L. Garcia, and I. Calvo. 1st Meeting of the EFDA H&CD Topical Group CCNB (Coordinating Committee on Neutral Beams). Padua 24-25 Nov 2008 1. Study of Electrostatic Residual Ion Dump for NB injector of ITER

L. Rossi and F. Castejón. Presented by M. Liniers 2. Development of modular parallel code for the study of current drive and momentum

transfer of the ITER Neutral Beams F. Castejón and M. Tereshchenko. Presented by M. Liniers

18th Internacional Toki Conference (ITC18), 9-12 diciembre, 2008. Ceratopia Toki, Gifu, Tok Gifu, Japón. http://itc.nifs.ac.jp/ 1. Kinetic simulation of heating and collisional transport in a 3D tokamak

A. Bustos, F. Castejón, I. A.Fernández, V. Martín-Mayor, A. Tarancón, J.L. Velasco


http://itc.nifs.ac.jp/

2. The Lithium Stellarator Experiment: TJ-II as a benchmark F.L. Tabarés and the TJ-II Team

ABI Workshop on Transverse and Longitudinal Emittance Diagnostics Bad Kreuznach (11th December 2008) http://adweb.desy.de/mdi/CARE/Bad_Kreuznach/ABI_Workshop_2008.html 1. Profile measurement systems for IFMIF-EVEDA

Autores: J. M. Carmona, J. Marroncle


http://adweb.desy.de/mdi/CARE/Bad_Kreuznach/ABI_Workshop_2008.html

4. Ph. D. Thesis and Advanced Studies Diplomas

Caracterización y Análisis de Iones en Plasmas de TJ-II mediante Espectroscopía Activa de Recombinación por Intercambio de Carga. J. M. Carmona Torres. Dto.: Kieran Joseph McCarthy 2008 Métodos Químicos de Limpieza e Inhibición de Codepósitos en Dispositivos de Fusión Jose A. Ferreira Somoza Ingeniero Químico por la Universidad de Santiago de Compostela Director: Francisco Tabarés Vazquez Procesos Colisionales entre Iones Multicargados y Atomos Neutros para el Diagnóstico de Plasma a distintas temperaturas en el TJ-II Francisco Guzmán Fulgencio Director de Tesis: Luis Errea/ F.L. Tabarés Departamento de Química Cuántica, UAM. Dec. 2008 Velocity Shear Layer investigations by reflectometry and design of a doppler reflectometer system T. Happel Director: T. Estrada Dpto de Física, Univ. Carlos III de Madrid. September, 2008. La alúmina como material aislante en la fusión termonuclear. Efecto de la incorporación de carbono en las propiedades físicas" Raquel Román Chacón Directores: María González Viada y Teresa Hernández Díaz Universidad de lectura: Universidad Carlos III de Madrid (Campus de Leganés). Departamento de Física. Instituto Álvaro Alonso Barba February 2008 Ion Kinetic Transport in Stellarators José Luis Velasco Garasa Director: Francisco Castejón Magaña Departamento de Física Teórica de la Facultad de Ciencias Físicas. Universidad de Zaragoza. Codirector: Alfonso Tarancón Lafita. Transporte local en plasmas ECRH de un dispositivo Heliac de confinamiento magnético V. I. Vargas Blanco Director: D. López-Bruna Universidad Complutense de Madrid, Facultad de Ciencias Físicas. June, 2008 Caracterización de materiales luminiscentes y sus aplicaciones al estudio de iones rápidos perdidos en el stellarator TJ-II D. Jiménez-Rey Física de los Materiales, Facultad de Ciencias. Universidad Nacional de Educación a Distancia, UNED



Laboratorio Nacional de Fusión por Confinamiento Magnético, (Euratom-CIEMAT). Director: Dr. Bernardo Zurro Hernández, Dr. Alfonso Baciero Adrados, Dra. María Shaw December 2008