enea status of fusion project

Fusion and Technology for Nuclear Safety and Security Department (FSN)

ASME and Nuclear Fusion Project ASME Certification 360 WorkshopMarch 20 – 21, 2018 – Rome, Italy

ENEA status of FUSION Project

Titolo della presentazione - Luogo e data 2

ENEA, the Italian Agency for New technology,Energy and Environment, is a nationalresearch organisation whose main business isthe development of new technologies.The agency which has a staff of approximately3000 employees, more than the half of themscientists is present throughout Italy, operating 9major research centers and a number of smallerfacilities.ENEA-FSN is the department dedicated toFusion and Technology for Nuclear Safety andSecurity

ENEA Fusion Technology Development

Frascati

Brasimone

Titolo della presentazione - Luogo e data

3


ITER

This image cannot currently be displayed.

IFMIF

3

ENEA is strongly committed on the mostrelevant project worldwide on fusion nuclearenergy:

DEMO Project (EUROFUSION)

ITER IO Project (F4E)

IFMIF (Broader Approach)

DEMO


Fusion Projects

4ENEA Fusion Technology Development


WCLL Breeding Blanket Design

5

Objective is to deliver feasible and integrated concept design of the WCLL BB for DEMO Plant at the Concept Design Review meeting

WCLL BB has to withstand severe operating conditions, ensuring (1) 3H self-sufficiency, (2) n-shielding and (3) coolant temperatures for an efficient power conversion cycle

WCLL BB features: (1) water as coolant; (2) Pb-15.7Li as breeder, n-mult and carrier; (3) Eurofer97 as structural material

Breeding blanket Establishing rationale and developing solutions

of WCLL BB 2015 design

WCLL BB 2015

Analyses of the design solutions and feedbacks

CFD

Finite Element

TMMCNP

Improvement of the design and exploiting alternative solutions

Toroidal

450

IB m

odul

e80

0 O

b m

odul

e

Back supporting structure

WCLL BB 2016

Analyses of the NEW

design solutions




6

Design activities involve different technical competences CAD Thermal-hydraulics MHD Thermo-mechanics Neutronics Water chemistry Coolant compatibility with materials

Industrial support by NNL (UK) Cooperation with ASIPP (China)

Baffle plate

BendPbLi Inlet PbLi Outlet Stiffeners

PbLi flow path

Water Pipes

Elementary breeding cell

Radial-poloidal cut of the EOM central cell

Outer sector radial toroidal cut

Breeding zone and lateral PbLi manifold view

* Based on up-to-dated WPBoP PHTS

Breeding Blanket




7

Nu number as a function of the magnetic field intensity, expressed as the dimensionless Hartmann number

Exploiting TH and MHD performances by SYS-TH and CFD codes

Detailed temperaturemap in structuresand fluids

Optimizing T fieldand Breeding Zonewater cooling layout

Tungsten

FW

PbLi

BZ and FW water coolant

Stiffeners and tubes

CFD solid and fluid domains

Details of BZ and FW coolant, and Eurofer structures.

Case 2Power [MW] 3.46 Mflow [kg/s] 1.529

2] 0.5 in [°C] 285

Tin [°C] 325

Wate

r tem

pera

ture

[°C]

Length [m]

FW coolant

Position

Wat

er te

mpe

ratu

re [°

C]

BZ coolant

Group 1

Group 4 Group 2

Group 3

Group 5

BZ COOLANT INLET

Water and stiffeners temperature distribution




8

Evaluating neutronic performances by Montecarlo analyses

Component TBR %

Breeding Blanket 1.137 99.07

Back Plate 0.003 0.03

Manifold -- --

Total 1.140

Outboard midplane: n damage EUROFER/SS316 TBR contribution of BB modules

WCLL BB 2016 MCNP model – MMS approach: effect of detailed modeling

TBR1.127

TBR1.140

Inboard midplane: n damage EUROFER/SS316




9

Isotropic deformation amplification factor = 20

IBR and IBL rotate clockwise due tothe opposite rotation of OBC,subjected to an higher EM torque

Deformation mainly driven byvertical and radial EM torquesand by radial and toroidal EMforces

IBLIBR

OBROBC

OBL

WCLL BB 20° standard sectorPerforming TM analyses of small component and large scale systems



Lithium Lead Eutectic Technology

10

ENEA is the coordinator of the LLE Technologies in EUROFUSION, which is organized as follow:

LLE Loop Design & Analyses (ENEA, CVR)

MHD Analyses and code validation (KIT, CIEMAT)

Corrosion (ENEA, KIT, CIEMAT, CVR)

Coolant Chemistry & Purification (ENEA, CVR)

ENEA is involved also in Tritium Technologies:

Consolidated model T transport in Breeding Unit for HCLL and WCLL

Tritium Extraction from LLE (with H)

Permeation Against Vacuum (PAV)

Vacuum Siever Tray (VST)




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Goals:

Design LLE loops and investigate critical Breeding Blankets LLE technical issues:

Conceptual design of LLE breeder loops concepts auxiliary systems: thermo-hydraulics &

numerical analysis and procedure to be adopted for normal and abnormal operations (LOCA

and LOFA in/ex Vessel)

Integration LLE loops in tokamak building

Investigation on corrosion of EUROFER with LLE and development of protection coatings (anti-

corrosion and Anti-permeation coatings)

Investigation of MHD issues and performing of related R&D (modelling and experimental activity),

taking into account also tritium transport, buoyancy effect, etc..

Irradiation behavior of LLE/EUROFER/coating;

Control/Purification of LLE from radioactive transmutation products




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LLE loops integration in Tokamak building

Cryogenicsystem/horizontal tank

NeutralbeamHeat transfer system AREVA GmbH –

Paul-Gossen-Straße 100 –91052 Erlangen, Germany




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Antipermeation/corrosion PLD coating developed by IIT/ENEA

Permeation Tests performed on PLD coating:

Hydrogen permeation through PLD coated samples at 823 K and 923 K, Hydrogen partial

pressure 100mbar.

PLD process

LLE corrosion after 1000h, 550°C

PERI II facility (ENEA)

NO corrosion



Coating laboratory

Corrosion TestsAlumina ( Al2O3 ) ceramic coatings consists of an amorphous matrix of alumina withnano-crystalline inclusions and is obtained by means of Pulsed Laser Deposition(PLD) in the laboratories at IIT.

Material compatibility with operative fluid is one of the most critical issue in the design of Nuclear Facility. In order tosolve the problem of corrosion/permeation/MHD effect protective coating were developed for each kind of application.The technologies investigated are: PLD Al2O3 coating ALD Al2O3 coating Thermal Spray: Detonation Spray techniques

E = 193,8 ± 9,9 GPaυ = 0,295 ± 0,025H = 10 ± 1 GPa

Al2O3 coating - Pulsed Laser Deposition (PLD)

1.000 h @ 550 °C in staticPb-16Li


Coating laboratory Permeation Reduction Factor (PRF) ALD coating

Internal side of Pipes Complex geometry Preliminary coating was produced and

characterize

Permeation Reduction Factor :

At 823K and 100mBar of Hydrogen

6*10^3

Detonation gun can be used to manufacturecoating on component of relevant dimensionsuch as grids or the core support plate, forwhich the performance requirements are not asstringent as in the case of fuel cladding.

Thermal Spray

Coating can be performed on: Plates: up to 590x590mm Cylinder: max Length:

1000mm, max diameter590mm, min diameter:customs



Metallographic and Control Lab

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Scanning Electron Microscopy Philips XL 20

Fluorescent Spectrometer X, Advant XP – ARL - Thermo Optek

Ray X Diffractometer - Philips X Pert–Pro

Optical microscopy Neophot30: 1X - 1000X Zoom

3D (X- Y- Z) metrologic measure COORD 3 ARES 1000, accurancy 1micon



WCLL Safety Analysis: in-box LOCA

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Objectives: to address the safety issues connected with PbLi/water interaction in WCLL BBin-box LOCA:• developing a reliable numerical tool for deterministic safety analysis of WCLL BB

in-box LOCA (SIMMER code for fusion application)• applying a standard code validation methodology to SIMMER code• designing and implementing a new experimental campaign in LIFUS5/Mod3 addressed to

code validation

Storage tanks Water injection valves S1_B reaction vessel



WCLL Safety Analysis: in-box LOCA

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Establishing a Standard METHODOLOGY FOR CODE VALIDATION

LIFUS5 SIMMER-III/-IV nodalization



WCLL Balance Of Plant

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Objectives

to perform power conversion studies for a Water Primary Heat TransferSystem and a Power Conversion System. The reference configurationincludes the integration of an Energy Storage System (working with HITEC) tocope with the pulse operation of DEMO

to perform R&D studies (experimental and numerical) about PbLi/water steamgenerators

Numerical tools. RELAP5/Mod3.3 versionmodified with water, HITEC and PbLi fluidproprieties

Experimental infrastructure. CIRCE facility@ CR Brasimone



WCLL Balance Of Plant

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Reference DEMO operation power pulse 2 h dwell time 30 min

Breeding Zone Primary Heat Transfer System

First Wall Primary Heat Transfer System

Vacuum Vessel and Divertor Systems

Energy Storage System

Power Conversion System



Early Neutron Source: DONES

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The design of DONES (DEMO-Oriented Neutron Source) is being implemented by the WPENS project inthe framework of the EUROfusion Consortium and in close collaboration with F4E


Scope: to design an accelerator-based neutronsource (DONES) able to produce fusion-likeneutrons with:• enough intensity to allow accelerated testing

(as compared to DEMO lifetime)• Irradiation volume large enough to allow the

characterization of the macroscopic propertiesof the materials of interest required for theengineering design of DEMO (and the PowerPlant)

Based on IFMIF design but with some significantly simplifying differences:

• Only one D+ accelerator (40 MeV, 125 mA) • Only one irradiated module (High Flux Test Module)• Irradiated module and radioactive wastes transferred to an external facility



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Logistics & Maintenance (incl. coordination)• Preparation of the Maintenance Management Plan (MMP)• Definition of flow of materials and components (materials, handling procedures and

equipment)• Implementation of the maintenance strategy for DONES components through logistics

simulation

Remote Handling (incl. coordination)• RH System Integrated Analysis• RH for the Lithium Systems • RH for the Test Systems • RH for the Accelerator Systems• RH Engineering Design Integration• Decommissioning• RH Testing and validation

Management of PLA & PS design activities• Management of Project-Level Analyses (safety, neutronics, RAMI,…)• Management of Buildings & Plant Systems activities




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Li Dump Tank

EMP

Target Assembly

Dump Tank

D+ beams

Ti Trap Cold trapY Trap

Impurity Control System

Lithium

Cooling water

from /to Conventional

Facilities

EMP

Quench tank

Pump

Secondary Heat

Exchanger

Dump Tank

Pump

Tertiary Heat

Exchanger

Purification

Monitoring

Heat removal system

Primary Heat

Exchanger

Secondary loop Tertiary loop

Main Li loop

Target System

Li Dump Tank

EMP

Target Assembly

Dump TankDump Tank

D+ beams

Ti Trap Cold trapY Trap

Impurity Control System

Lithium

Cooling water

from /to Conventional

Facilities

EMP

Quench tank

Quench tank

Pump

Secondary Heat

Exchanger

Secondary Heat

Exchanger

Dump TankDump Tank

Pump

Tertiary Heat

Exchanger

Purification

Monitoring

Heat removal system

Primary Heat

Exchanger

Secondary loop Tertiary loop

Main Li loop

Target System

Important support fromLIFUS-6 validation results

Lithium systems design (incl. coordination)• TA design• Main Li loop design • Impurity Control System design• Ancillary systems design & Integrated analyses



Advanced Steel

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Y. Dai and oth., Journal of Nuclear Materials 415 (2011) 306–310

Blanket Operation @ 280°C - EUROFER for low T applicationsAs low as possible DBTT (Ductile to Brittle Transition Temperature)

Shift of DBTT under irradiation (displacement cascade and Helium generation)



Advanced Steel

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Effective pinning of the precipitates on the dislocationsintroduced by hot rolling

S. Hollner and oth./ Journal of Nuclear Materials 405 (2010) 101–108

Thermo-Mechanical Treatments to improve the high temperature properties

Blanket Operation @ 600°C – EUROFER for high T applicationsGoal: Steel with highest possible operating temperature Reference EUROFER: sm>100 MPa, T > 550 °C, price 50 k€/tonOperating Temperature Tmax=650°CStrength at 650°C: tensile: σy>100 Mpa; creep: tR,min=20000 h (50000 h), σ>100 MpaFatigue LCF: 650°C, Nf>10000; thermal: Tmax=650°C, Tmin=100-300°C, Nf>10000 Fracture Toughness; Charpy: DBTTunirr< -80°C (KLST specimen)


Advanced Steel

26

Alloy design of creep resistant martensiticsteels (Thermocalc, Jmat-Pro)Optimization of the thermomechanicaltreatments (SEM and hardnessmeasurements to tune Grain Size andsolubilization of carbides)Tensile tests (improvement of hightemperature properties)Creep testsImpact tests (Charpy ISO-V and KLST)SANS (Small Angle Neutron Scattering)measurements to correlate the distribution ofthe precipitates to the improvement in termsof high temperature mechanical properties



ITER Activities



Engineering Design of HCLL and HCPB TBMs

28

Completion of the Conceptual Design and the Preliminary Design of Helium Cooling System PbLi loop Coolant Purification System Tritium Removal System & Tritium Extraction System

Consolidation of technical interfaces with ITERRadiation protection, releases during maintenance, accident analyses

Port Cell #16 of ITER: TRS, Pb-Li loop, HCS



Design of TBM Ancillary Systems

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This activity deals with the design on European TBM ancillaries (Cooling and Tritium systems) and theirintegration in ITER

ENEA coordinates a consortium with KIT and other partners as subcontractors (TPI, Wigner, CV-Rez,Palermo University, CREATE)

278

Helium Cooling System Layout in CVCSENEA Fusion Technology Development


Design of TBM Ancillary Systems

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Lead Lithium Eutectic Loop Integration in ITER



TRIEX/TRIEX IIInvestigation on Tritium Extraction Systems for Pb-16Li blankets with different Technologies:

Gas Liquid Contactor, Permeator Ageist Vacuum, Vacuum Sieve Tray candidates for DEMO and ITER Reactor

TRIEX Operative Conditions- Processed fluid: Pb-16Li- Design Pressure: 0.8 MPa (g)- Design Temperature: 530 °C- Max mass flow rate: 4.5 kg/s- Stripping gas: Ar, Ar+H2- Pb-16Li inventory in the loop: 105 l- H2/D2 partial pressure: 1-3000 Pa

GLC – Test SectionPAV –DEMO/ITERTest Section



Coolant Purification System Qualification

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HYDREX facility aiming at qualifying the Coolant Purification System of HCLL/HCPB TBM

Q2 Oxidation : BASF catalystPURISTAR® R3-11G is a robustcopper catalyst for the removal ofoxygen from gases and liquids.CuO + H2 → Cu + H2OAn outstanding attribute of this catalystis the stability of its matrix, enablingexcellent regenerability, and long-termoperation at temperatures as high as275 °C.

Reducing bed: SAES St909/Al

PTSA => Q2O AdsorptionSYLOBEAD® MS 564 C molecular sieve Type 3°

SYLOBEAD® MS C 544 molecular sieve Type X

MOLSIVTM TE 143R molecular sieve Type 4°

MOLSIVTM PSA O2 HP molecular sieve Type X



Safety: HCLL In-TBM LOCA

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The object is to experimentally investigate, supported by numerical tool (RELAP5-3D), the pressurization of LLE loop due toHCLL in-TBM LOCA .

Pressurization and the compression wave propagation into the LLE loop in case of injection of helium at 80 bar,400°C due to the rupture of a cooling plates.

Demonstrate capability of RELAP5-3D © to model single and two-phase (two fluid) wave propagation (fasttransients in liquid metal loop)

THALLIUM test section

THALLIUM DESIGN PARAMETERS

PbLi volume 150 lt

PbLi temperature 400 °C

He injection pressure 80 bar

He injection mass flow 0,1-0,4 kg/s

Design pressure 80 bar

Pressure trend in the first 150 s



HCLL in-TBM LOCA

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0 5 10 15 20 25 30 35 400

10

20

30

40

50

60

70

Time [s]

Pres

sure

[bar

]

Experiment 1Experiment 2RELAP5-3D

RELAP5-3D ANALYSES



Broader Approach



EVEDA Lithium Test Loop Activities

36

Design and delivering of the online monitoring system for non metallic impurity in Lithium (Ni)Implementation and suppling of the cavitation detection system (CASBA 2000 )Participation to the experimental test campaign

In addition ENEA developed the Li channel profile of the TA Flow stability successfully tested in the ELTLunder IFMIF working conditions

Resistivity meter

Resistivity meter



Lithium Technology

37

ENEA developed hot trap based on the use of a Titanium sponge Operating Temperature(during the purification)

600°C

Total Internal Volume ∼ 21 L

Volume filled by Lithium(during the purification)

∼ 15 L

Getter type Ti sponge in grains

Loaded getter amount* ∼ 11 Kg

Li Purification Offline- before charging the loop

The best result in the world: 14 ± 2 wppm of N



Lithium Technology

38

LiFUS6 is the facility designed and constructed to investigate the erosion & corrosion phenomenaunder IFMIF working conditions ( up to 350°C at Li flowing at 16 m/s)

T max 350°C Li speed 16 m/s (in the test section) Hot and Cold traps for H,C,O and N Purification of N offline at T> 550°C Resistivity meter for the online monitoring of N content Li sampling system for offline analysis

IFMIF requirements: 1 µm/y for the TA in the channel side 50 µm/30ys for piping

Experiments have demonstrated that the erosion & corrosionrate is well below the reference value of 1 µm/y



European Target Assembly for IFMIF

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The EU TA ( Bayonet Concept) designed by ENEA :Engineering mechanical design

Nuclear analysis

Thermomechanical analysis in collaboration with the University of Palermo

Structural analysis in collaboration with the University of Pisa

Life time assessment of the removable back plate

Engineering design of the support system of the TA

Engineering design of the RHE and tooling for its refurbishment

Engineering design and prototyping of the Fast Disconnecting System



European Target Assembly for IFMIF

40ENEA Fusion Technology Development

The EU TA was designed to: simplify the maintenance operations reduce the material for disposal

It is based on the bayonet concept: provided with a removable backplate; connected with the Li loop and the duct beam by

means of fast disconnecting systems (FDSs) provided of metallic sealing systems


Fusion Research Infrastructures



CEF1 and CEF2 Water Loops

Innovative Nuclear Systems Technology Development

an heat exchanger, two centrifugal pumps which can be operated in series or inparallel, the test section and the return line to the pressurized tank.In the same experimental hall is installed a gas/water circuit, called D&D circuit, toperform experimental simulations of draining & drying procedures.

CEF1 and CEF2 experimental hall

CEF1 and CEF2 design parameters

CEF1 and CEF2 are twin independent water loops for thermo-hydraulic characterizations of water cooled components. Eachof ones, consists of:

Parameter Value Unit

Processed fluid Demineralized water

Tank design pressure 0.5 MPa

Piping design pressure 2.5 MPa

Loop design temperature 140 °C

Pump max. flowrate 2 x 70 kg/s

Pump max head 2 x 1.2 MPa

TS max inlet pressure 2.5 MPa

Electrical heater power 2 x 60 kW

ENEA Fusion Technology DevelopmentITER FW mock-ups assembled in the glove box connected to CEF2


Divertor Refurbishment Platform (DRP)

43

Development of the RM procedures for the refurbishment of ITER Divertor Cassette

• Design and procurement of RHE for theassembly of the latest ITER DivertorCassette design

• Development of assembly procedures ofthe three Targets(Inner, Outer and DOME)

• validation and optimization of therefurbishment process, including cuttingand welding of the cooling pipes



IELLLO: Integrated European Lead Lithium LOop

44

• Lead Lithium Eutectic (16 at.% of Li and 84 at.% of Pb)• Pressure range: 1-6 bar• Temperature range: 350-550°C

• from 350 to 430 °C in the counter-current pipe in pipe heat exchanger (economizer)

• up to 550 °C in the electrical heater• down to 470 °C in the outer shell of the economizer• 350 °C after the air cooler

• Mass flow rate range-: 1.28-2.41 kg/s• Instrumentation:

• an absolute pressure transducer (0-10 bar) and 5 differential pressure transducers (to be installed)

• a Vortex flow meter (1.0-2.4 kg/s)• a Coriolis flow meter (to be installed)• a thermal flow meter (to be installed)• level sensors and cover gas pressure gauges in the tanks



HE-FUS3 Experimental Facility

45

HE-FUS3 facility is designed to study the cooling circuit of HCPB-HCLL TBMs in ITER. It is able to carry out experiments upto scale 1:1. The loop can perform the characterisation of the TBS in the following operation modes:

Long term isothermal cooling flowSlow thermal cycling flowFast cold thermal shock flowLOCA/LOFA simulation

HE-FUS3 Operative considtions:Max T: 550 °CMax P: 8.1 MPaMax He mass flow-rate:1.4 kg/s

Total Installed power: 1.5 MWMax heating removal capacity: 1.3 MW

ITER Turbocirculator

Max compressor speed: 40.000 rpm

Max flow rate: 1.4 kg/s



EBBTF - European Breeding Blanket Test Facility

Testing of relevant components of the HCPB/HCLL blanket concepts Experimental platform used for modelling tool development and validations

IELLLO (LM loop)He-FUS 3 (He loop)

IELLLO Operative Conditions- Processed fluid: Pb-16Li- Design Temperature: 550°C- Design Pressure: 0.5 MPa- Max LM flow rate: 3.0 kg/s- LM Inventory: 500 l- Max Heating Power: 60 kW

He-Fus 3 Operative Conditions - Processed fluid: He- Design Temperature: 530 °C- Design Pressure: 8 MPa- Max He mass flow-rate: 0.35 kg/s-Max heating power: 210 kW



Tritium laboratory

47

PERI II VIVALDI

Test Section

for Q permeation measurement through blanket structural materials in gas phase for Q permeation measurement through

blanket structural materials in presence of Pb-16Li

SOLE

for Q solubility (Sieverts’ constant) measurement in Pb-16Li



Mechanical Testing Laboratory

48

Electromechanical Machine Zwick Proline Z050DESCRIPTIONMedium size machine, with two columns structure and movable crosshead with electronic positioning system and mechanical system for clamping. The machine is equipped with an electronic system for acquisition and control (closed loop control). Load cell: 50 KN / crosshead min. speed: 0,0005mm/min / crosshead max. speed : 600 mm/min.

COMBINED EQUIPMENT• Resistance furnace up to 1100°C• Room Temperature axial extensometer • High Temperature axial extensometer • Room Temperature bending tests equipment-196°C tests equipmentTESTS• Room Temperature and High Temperature tensile tests

according to ASTM E8/E8M-11; ASTM E21-09; EN ISO 6892-1; Recent publications: NME, under review: Pilloni an oth.:Development of innovative materials for DEMO Water Cooledblanket/ Cristalli and oth.:Development of innovative materialsfor DEMO high operating temperature blanket options

• 3 or 4 points bending tests• Fatigue tests

3 points Bending tests:



Mechanical Testing LaboratoryHydraulic Presses MTS The 4 presses are equipped with a hydraulic piston, a load cell on the lower side, a hydraulic brake system for crosshead positioning and a hydraulic system for clamping. The control system can carry out several tests like fatigue and creep-fatigue tests.FEATURES OF THE PRESSES• Max pressure: 200 bar• Load cells: 100 kN (2 machines) / 500 kN (1 machine); Max.

compression load: 9000 kN (1 machine) • Max piston stroke:± 100 mm (2 machines) / ± 75 mm (1 machine) /

± 50 mm (1 machine) • Max crosshead stroke: 850mm (2 machines) /1200 mm (1

machine) • Max testing frequency:10 Hz (2 machines) /2 Hz(1 machine) /0,1

Hz (1 machine) • Space between the columns: 500 mm (2 machines) /750 mm(1

machine) /1000 X 1000 mm^2 (1 machine) TESTS• Uniaxial standard tests, Slow Strain Rate Tensile Tests• LCF and Creep-Fatigue tests according to ASTM E 2714-09• The machines can carry out tests in hostile enviroments, uni or biaxial,

like fretting tests in Lead at 550°C, dynamic fiction tests in vacuum at cryogenic temperatures. Cryogenic (-196 °C) tests facilities.

Fretting tests in lead(GETMAT Project)

ITER keys testing(moltenNitro-gen)

Creep fatigue campaign (MATTER Project; publication JPSA; C. Cristalli and oth.)



Mechanical Testing Laboratory

DESCRIPTIONn° 4 30 kN Creep Tests Machines (lever ratio 1:15)n° 4 20 kN Creep Tests Machines (lever ratio 1:10)

TESTS according to ASTM E139-11; Stress Rupture Tests, Creep Rupture Tests, Creep Tests

COMBINED EQUIPMENT• Auto-levelling arm device (to keep the levelling arm

always horizontal)• Each frame instrumented with a couple of LVDT (linear

voltage displacement transducer) to monitor the strain-time behaviour and plot the creep curve

• N°8 High temperature Resistance Furnaces up to 1000°C (3 zones P.I.D. controlled)

• Thermostatized Tests; Environment Temperature within ± 3°C according to ASTM E139-11

• Temperature and Elongation acquiring custom system

Creep Machines



DTTDivertor Tokamak

Test Facility



DTT


DTT (Divertor Tokamak Test) facility is dedicated to qualify power exhaust

solution for DEMO

EUROPEAN ROADMAP


DTT



DTT


Tokamak section view


ENEA (also through the Experimental Engineering Division in Brasimone)is strongly committed on the most relevant project worldwide on fusionnuclear energy

DEMO Project (EUROFUSION)

ITER IO Project (F4E)

IFMIF (Broader Approach)

DTT

ENEA, thanks to one of the most relevant fleet of experimental facilitiesworldwide, numerical skills, design capabilities, technological know-how,plays an important role in Europe and in the world on the fusiontechnology development



Marco [email protected]

Titolo della Presentazione – Luogo e dataENEA Fusion Technology Development

enea status of fusion project

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