18.06.2009 (dfn,dfna) 25.06.2009 (ifa) (ifin-hh)

IFIN-HH EURATOM - Proiecte IFIN-HH in derulare.18.06.2009 1

18.06.2009(DFN,DFNA)

25.06.2009(IFA)

01.07.2009(IFIN-HH)


1. Informare: Google F4E:


[1. Informare]


2. (Supra)Structura proprunerii - consortii


[ 2. (Supra) Structura proprunerii ] Expertiza consortiului


[ 2. (Supra) Structura proprunerii ] Expertiza proprie


[ 2. (Supra) Structura proprunerii - Expertiza proprie ] Vizibilitate - Website


3. Tematica si Obiectivul Proiectului


[3. Tematica si Obiective ] Responsabilitatile Consortiului


4. Finantarea consortiului


[ 4. Finantarea consortiului ]


Dr. Silviu Olariu (DFN)


Obtinerea unui proiect FP7 / EUROATOM

Elementul principal:

Responsabil contract TU Munchen- IPP Max Planck, Garching


Obtinerea unui proiect FP7 / EUROATOM

VTT –Technical Research Center of FINLANDTEKES (ERG) Estonia

JW 9FT-TEKES/VTT-ERU-2

Partener

JET+ ASDEX

Publicatii

FP7 / EUROATOM

Hydrogen isotope depth profiling in carbon samples from the erosion dominated inner vessel walls of JET, Stan-Sion, C; Behrisch, R; Coad, JP; Kreissig, U; Kubo, F; Lazarev, V; Lindig, S; Mayer, M; Nolte, E; Peacock, A; Rohrer, L; Roth, J, JOURNAL OF NUCLEAR MATERIALS 290 491-495, 2001

TRITIUM DETH DISTRIBUTIONS IN THE VESSEL WALL OF ASDEX UPGRADE.C. Stan-Sion , J. Roth, Int.Conf.on Plasma Surface Interactions in Controlled Fusion Devices, May 27-31, Nagaragawa ConventionCenter, Gifu, Japan (2002)

UPGRADING OF THE ULTRA CLEAN INJECTOR FOR DEPTH PROFILING AT MUNICH AMS FACILITY, C. Stan-Sion, L. Rohrer, P. Hartung , V. Lazarev, R.Luther, E. Nolte, R. Behrisch, J. Roth, Nuclear Inst. and Methods in Physics Research, B192,3 (2002), 331-338

AMS - SENSITIVE TOOL USED AS NUCLEAR SAFEGUARD AND TO DIAGNOSE FUSION EXPERIMENTS, C. Stan-Sion, J. Roth, K. Krieger, M. Enãchescu, K. Ertl, V. Lazarev, H. Reithmeier and E. Nolte, Nuclear Inst. and Methods in Physics Research,-B 259 (1): 694-701 JUN 2007

UNFOLDING PROCEDURE FOR AMS DEPTH PROFILING, Mihaela Enachescu, V. Lazarev and C. Stan-Sion, J. Phys. D: Appl.Phys, Volume 39, Pages 2876-2880 (2006)

TRITIUM AND DEUTERIUM STANDARDS FOR AMS MEASURMENTS, C. Stan-Sion, Mihaela Enachescu, I. Dorobanţu, R. Behrisch and C. Postolache, University Politehnica of Bucharest Scientific Bulletin, Series A: Applied Mathematics and Physics, Volume 66, Number 2-4, Pages 95-102

AMS DEPTH PROFILING USED FOR DIAGNOSE,C. Stan-Sion, O. Constantinescu, M. Dogaru, M. Enachescu, I. Stefanescu, C. Pearsica, 13th Progress in Cryogenics Separation, ICTI, Rm. Valcea, Romania, November 7-9, 2007

AMS DEPTH PROFILING OF TRITIUM AND DEUTERIUM – A NEW AND SENSITIVE TOOL FOR DIAGNOSE IN FUSION EXPERIMENTS, C. Stan-Sion, J. Roth, V. Lazarev, R. Fischer, Mihaela Enachescu, H. Reithmeier and E. Nolte; InternationalConference on Applications of High Precision Atomic & Nuclear Methods, Neptun, Romania, September 2-6, 2002

Notificare EUROATAOM

JW9-NFT-MEC-16/2009


(Supra)Structura proprunerii - consortii


Descrierea proprunerii


Descrierea propunerii

FUSION REACTIONS IN TOKAMAKS

D + D → 3He (0.82 MeV) + n (2.45 MeV) + Energy

D + D → T (1.01 MeV) + H (3.02 MeV) + Energy

More efficient is the recycling reaction:

D + T → He (3.5MeV) + n (14.1MeV) + Energyn + 6Li → T + α

Tritium gas -input is used at JET only!

The ASDEX-Upgrade Tokamak in MunichThe AMS measurements were performed on long term samples (LTS)

made of pyrolithic graphite, installed between the vessel wall protection tiles

JET JET

JETJET

Motivation of AMS studies for fusion experimentsMotivation of AMS studies for fusion experimentsRecently, due to the International Thermonuclear Experimental

Reactor project (ITER), special interest is paid to depth profiling measurements of the Tritium created in

D-D fusion reactions in magnetically confined plasmas.

500MW fusion power

40MW electrical back

to the grid

AMS AMS for for

Fusion Diagnose and radioFusion Diagnose and radio--dosimetrydosimetry in TOKAMAKin TOKAMAK

Diagnose of Improvement of the plasma Diagnose of Improvement of the plasma confinementconfinement

0

5E+12

1E+13

1,5E+13

2E+13

2,5E+13

0 2 4 6 8 10 12 14 16 18 20 22 24

Depth ( µm )

T ( a

tom

s/cm

³ )

Tritium depth profile distribution measured by AMS in carbon long term samples exposed in ASDEX at DD reactions before 1991.

0

2E+14

4E+14

6E+14

8E+14

1E+15

1.2E+15

0 0.5 1 1.5 2 2.5 3 3.5 4 4.5 5

Depth ( µm )T

( ato

ms/

cm³ )

5/8

5/65/5

5/4

5/2

5/3

In 1994 the Completely Detached High Confinement modus (CDH) was invented and applied in Tokamak experiments. Since then the T-depth distributions extend not more than 1µm for the ASDEX-Upgrade and JET fusion experiments.

Diagnose of plasma confinementDiagnose of plasma confinement

0

2E+14

4E+14

6E+14

8E+14

1E+15

1,2E+15

1,4E+15

0 1 2 3 4 5 6 7 8 9 10

depth ( µm )

T ( a

tom

s/cm

³ )

a) T-depth distribution showing a good preserved confinement (campaign 1998-1999);

The new distributions can be separated in a component of surface deposition and in a component peaking at about 0.5 µm (corresponding to ET=30keV) from the surface. The surface deposition is due to tritium ions having energies in the 100eV range, except for a low flux of neutral atoms with energies up to the keV range, which are produced by charge exchange collisions [17] in the 10 keV hot plasma. The peak, if it is not extending deeper than 1µm, corresponds to the tritium ions produced in the fusion reaction, then slowed down by drifting on orbits in the magnetic cage and released with an energy below 30 keV at the end of the discharge period. However, if the peak extends up to larger depth this implies that some irregularities have occurred in the fusion experiment. Such a situation is illustrated in fig.2, by the depth distribution noted with “b”.

b) T-depth distribution indicating irregularities during some of the discharges (campaign 1999-2000).

a

b

Diagnose of interference with NBIDiagnose of interference with NBI

0

0.2

0.4

0.6

0.8

1

1.21

2

3

4

5

6

7

89

10

11

12

13

14

15

162

3

4

5

6

7

89

1011

12

13

14

15

161

NBI

NBIaverage surface distr.

0

0.2

0.4

0.6

0.8

1

1.21

2

3

4

5

6

7

89

10

11

12

13

14

15

162

3

4

5

6

7

89

1011

12

13

14

15

161NBI

NBI

total average distr.

What is Disruption ?What is Disruption ?

The large forces existing inside of the plasma try to keep it

together and rip it apart.

If an instability occurs ( like some displacements inside the vessel or some pronounced impurities) then

PLASMA DISRUPTION destroys the confinement and the energy will be released by impact with the walls.

10-200 MJ /m2 released in 1-10ms

LocalisationLocalisation of Disruptionof Disruption

1,0E+08

1,0E+09

1,0E+10

1,0E+11

1,0E+12

0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16

Toroidal SectorT

( ato

ms/

cm² )

0.00E+00

5.00E+15

1.00E+16

1.50E+16

2.00E+16

0 2 4 6 8 10 12 14 16

Toroidal Sector

Mar

ker T

hick

ness

( at

oms/

cm² ) W

Si

Toroidal distribution of the T-inventory (atoms/cm²) in LTS from ASDEX-Upgrade campaign 1999-2000: a) T–inventory up to 0. 5 µm depth;

RBS

b) T-inventory in the bulk, below 0.5µm.

Rutherford back scattering ( RBS ) measurement of W and Si markers (coated carbon LTS) placed in toroidalpositions of the ASDEX-Upgrade tokamak during the campaign 1999-2000. The horizontal lines indicate the initial thickness of the deposited layers.

AMS ab

Diagnose of Diagnose of ploidalploidal distributiondistribution

Divertor

1.00E+08

1.00E+09

1.00E+10

1.00E+11

1.00E+12

0 1 2 3 4 5 6 7 8 9

Poloidal position

T (a

tom

s/cm

²)

12

3

2

4

3

56

7

8

Diagnose of the DIVERTOR actionDiagnose of the DIVERTOR action

Divertor ASDEX-Upgrade

0.00E+00

4.00E-08

8.00E-08

1.20E-07

1.60E-07

0 200 400 600 800 1000 1200 1400 1600

Position (mm)

T/C

( m

ax. C

onc)

DomeBgr.6

Bgr.2

strike point

Bgr.4oBgr.4u

The confinement region (inner part )of the plasma is surrounded by closed field lines. The last surface with closed lines is called SEPARATRIX. Particles drifting along the

SEPARATRIX are directed onto the DIVERTOR plates and from there are eliminated by vacuum pumping.

In this way the divertor exhausts the flow of energy from the inner part to the walls and removes helium and other impurities resulting from interaction of plasma particles with the

material walls.

1. The spatial distribution of implanted T in the Divertor

2.Energy of the Tritium removed by the DIVERTOR2.Energy of the Tritium removed by the DIVERTOR

Asdex-Divertor Dome

0,0E+00

5,0E+14

1,0E+15

1,5E+15

0 0,5 1 1,5 2 2,5 3 3,5 4

Depth (μm)

atom

s/cm

3

Depth profile of implanted tritium at the horizontal dome baffle tile of ASDEX Upgrade

E = 10 keV

Energy analysis of the Deuterium in the TokamakEnergy analysis of the Deuterium in the Tokamak

The peak at 1,3 µm depth. corresponds to the 100 keVneutral Deuterium injected into the plasma for

supplementary heating since 1999.

1

5E+20

1E+21

2E+21

2E+21

0 0,2 0,4 0,6 0,8 1 1,2 1,4 1,6 1,8 2

Depth ( µm)

D (a

tom

s/cm

³)

A

1E+19

1E+20

1E+21

1E+22

0 0,5 1 1,5 2 2,5 3 3,5 4

Depth ( µm )

D (a

tom

s/cm

³)

B

The D-depth distribution peaks at 0.2µm depth, which corresponds to the maximum penetration of 10 keV deuterium particles from the plasma of

same temperature (100 Mil 0C)

D-depth distributions in carbon LTS from ASDEX-Upgrade. A) campaign 1997-1998, the Deuterium distribution peaks at 0.2 µm depth. No other peaking occurs; B) campaign 1999-2000, the Deuterium distribution peaks at 0.2 µm but also at about 1 µm depth.

AMS Depth Profiling used as Nuclear AMS Depth Profiling used as Nuclear SafeguardSafeguard

AMS measurements provide radio-dosimetric information in the Tokamak based on the precise inventory of the

Tritium deposition.

AMS from neutrons1997-1998 1,3 1017 at 1016 at1998-1999 2,1 1018 at 1017 at1999-2000 3,5 1015 at 1013 at2000-2001 2,5 1019 at 1018 at2001-2004 1,5 1018 at /y 1017 at/y

TOKAMAK TOKAMAK DosimetryDosimetry

ConclusionsConclusions

AMS demonstrated to be a sensitive diagnose tool for Tokamak fusion experiments and is a promising method to provide an useful diagnostic tool in the future ITER project.

18.06.2009 (dfn,dfna) 25.06.2009 (ifa) (ifin-hh)

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