E.Diegele,IFMIF Necessity and Status of Preparation.pdf

IFMIF 

Necessity and Status of Preparation 

Presented by Eberhard Diegele, F4E 

International Workshop, MFE Road Mapping in the ITER Era 

8th 8 September 2011 Princeton 

th September 2011, Princeton 

This contribution and any comments during the workshop 

do not necessarily represent the opinion or the policy of the EC or F4E 

Slide 1

Elements of of a a Strategy Strategy for Materials R&D – 

for the next Two Decades (I) 

RAFM steels „only“ choice for TBM (alternative options with high 

risk) 

– Development mission driven. Technology part of the programme 

– Full characterisation of RAFM steels in the next decade (for TBM use). 

– „Code „ q qualification“ required q up p to some dpa p [RCC [RCC-MRx/SDC]. 

[ MRx/SDC]. ] 

– Irradiation campaigns in fission reactors („Material Test Reactors“). 

Test materials with fission neutrons from nuclear reactors: 

• Adequate flux flux. 

• BUT 

• Energy spectrum: not adequate, high energy tail missing. 

• Insufficient H and He production by transmutation. 

2 

of 26 slides

Elements of a Strategy for Materials R&D – 

for f ffor th the next t Two T Decades D d (II) 

(II) 

Construct and and start start operation of a 14 MeV neutron facility facility (IFMIF) 

• Adequate flux, 

• Fusion typical irradiation temperatures 

• At “h “homogeneous” ” t test t conditions diti throughout th h t a sample sample. l 

• Stable irradiation conditions (T) (#) 


is „mandatory“ to generate engineering data for DEMO design rules for 

E End d of f Life Lif conditions. diti 

is useful in testing materials and sub sub-components components prior to approval for 

application in power plants. DEMO will provide the endurance component 

tests. 

Is a most valuable source for verifications of multi-scale multi scale modelling predictions. 

Code qualify q y material: 

Property f (T, Tirrad, fluence, environment, load-stress-strain) – This allows to 

together with a code framework transferability to other conditions 

With temperature excursions (annealing of defects) – risk to loose data point 

3 



for the next Two Decades - (III) 

The He issue 

• Fission reactors produce p insufficient rates of He and H 

• Irradiation in fission reactors gives only non non-conservative conservative approach for 

degradation of materials materials. . 

Various tricks tricks or methods used: 

– B and Ni-doped steels in MTR: ~a few appm He/dpa. 

– Fe54 enriched steels in MTR: ~2 appm He/dpa. 

– Mixed spallation-neutron spectrum: ~100 appm He/dpa. 

– (Multi) Ion beam irradiation: up to 10000 appmHe/dpa. 

Different material 

Cost. 1kg 500k$ 

Transmutations 

Transmutations 

pulsed 

10 micro-meter 

• All these experiments experiments p needed to increase knowledge g and understanding g of 

the microstructure. 

• Modelling and understanding of irradiation results under various conditions 

is clearly clearly needed. 

4 



for the next Two Decades - (IV) 

Accompanying programs: 

– Modeling of irradiation effects towards an understanding of 

irradiation damage over the full scale (from quantum physics to 

engineering analyses). 

– “Extrapolation” of dislocation damage from fission data to fusion 

environment. 

– Simulations with predictive capability. 

– Integrated approach with “physics-based” modeling and 

simulations in the meso to macro scale at the interface between 

materials science and technical application (simulating “real 

conditions” and “real components”) will be an key for success. 

5 



for the next Two Decades - (V) 

In parallel: Optimization and further development of RAFM steels 

– For use with DEMO 

In parallel: Optimization and further development of ODS/NCF ODS/NCF-type type 

steels 

In parallel parallel: De Development elopment of „new“/“advanced“ ne “/“ad anced“ materials materials for high 

high 

temperature application. 

Including, both 

Irradiation campaigns in fission reactors (high fluence, ~100 dpa). 

Strong g science based programme p g to accumulate knowledge g and 

understanding of irradiation effects to „design materials“. 

6 


This summary could have been from yesterday 

However, it is from ... 2006 ... 

Long Term Materials Development 

The EU Road Map 

E. Diegele 

EDFA EDFA-CSU CSU Garching 

IEA-Meeting July 10-12, 2006, Tokyo, Japan 

Slide 7 

7 

of ? slides

Fusion Materials Development Path 

Materials Performance/Component specific Loading - Stage- IV 

Demonstrate solution to concept-specific issues 

Performance under complex loading history (T, stress, multi-axial strain 

fields & gradients) & environmental conditions 

Qualified Material, Demonstration of Performance - Stage- III 

Complete database for final design & licensing 

Validate constitutive equations & models 

Demonstrate life time goals (He issue) 

Demonstration of Performance Limits - Stage- II 

Database for conceptual design 

Demonstrate proof-of-principle solutions, design methodology 

Evaluation-modification cycle to optimize performance 

Materials Screening & Materials “Design”` - Stage- I 

Identify candidate alloy composition, compatibility, irradiation stability, 

proof of principle for fabrication and joining technologies -Validation Validation of 

models and tools (microstructure) 

Slide 8

Fusion Materials Development Path 

Facilities needed 

Performance under component specific loading Stage IV 

„FNT(S)F“ FNT(S)F“ CTF 

Not any facility existing 

IFMIF and FNSF are complimentary in an 

INTERNATIONAL Road Map or approach 

Qualified materials materials, full demonstration of performance Stage III 

14 MeV neutrons or fusion specific n-spectra >>> IFMIF 

Demonstration of performance limits Stage II 

Materials “Design” R&D Stage I 

To some limited extend ITER-TBM 

Fi Fission i reactors t (MTR of f next t generation ti like lik JJules-Horowitz) l H it ) 

Complementary Modelling essential 

(IFMIF) 

Fission reactors (MTR) 

Multi-ion-beam irradiation facilitiers 

Slide 9

Strategy on the address 

fusion neutron irradiation effects 

Experimental understanding 

Dislocation damage, He effects, H effects, etc. 

Neutron irradiation (fission) Ion beam irradiation) 

SSTT 

Mechanical property data 

Tensile 

Hardnes 

s(Hv) 

Nano 

hardness 

(Hm) 

Microstructure data 

TEM 

Mechanical understanding 

Theory of 

Irradiation effect 

Mechanical Microstructure 

property 

model 

evolution 

model 

Structure S ucuedeo deformation a o 

model 

Toughness 

CCreep 

Fatigue 

correlation 

Interpretatio 

SEM 

Residu 

e 

Others 

Theoretical prediction 

(Misc) 

n of 

mechanical 

properties 

Evaluation of 

fusion neutron 

irradiation effects 

Microstructure evolution 

Etc. 

IFMIF irradiation 

on mechanical 

property 

DEMO 

Blanket 

H. Tanigawa, Vienna Dec 2011, IAEA, modified 

Design 

Computational Simulation 

Irradiation fields correlation (dpa/s, PKA) 

Point defect migration, agglomeration 

Slide 10

Rick Kurtz, 7 th Sept Princeton 

Slide 11

Long History – Recall from... 


Slide 12

Long History – Recall from... 


Slide 13

Indicate that slides was provided 

by this group of authors 

IFMIF in the Context of Materials Research 

AA. Möslang Möslang, NN. Baluc Baluc, E. E Diegele, Diegele UU. Fischer Fischer, RR. Heidinger Heidinger, AA. Ibarra Ibarra, PP. 

Garin, V. Massout, G. Miccichè, A. Mosnier, P. Vladimirov 

Authors on behalf of the fusion materials and IFMIF community 

KIT – University of the State of Baden-Wuerttemberg and 

National Laboratory of the Helmholtz Association www.kit.edu

15 

Perspectives for fusion 

Conception Construction Exploitation Application of results 

Accomppanying 

Programmme 

in 

Physicss 

and in 

Techn nology 

ITER (1/2 GW th) 

Materials, Intense n-source 

Environment and Safety 

DEMO (2-3 GW th) 

FPP (1.5 GW e) 

0 10 20 30 40 50 Years 

Large 

scale prroduction 

of electrricity 

A. Möslang et al.

High Performance Materials for Energy 

First Reactors 

Current Reactors 

Advanced Reactors 

Future Systems 

1-3 1 3 dpa < 200 dpa < 200 dpa 

1950 1970 1990 2010 2030 2050 

ITER IFMIF 

Strategic Missions: 

• Electricity, Hydrogen, Heat 

• Contribute to lower greenhouse gas 

emission 1-3 dpa 

Specific challenges for fusion: 

• Short development path 

• More demanding loading conditions 

16 

20-40/year 

DEMO, Fusion Reactor 

< 150 dpa 

A. Möslang et al.

Main missions of an intense neutron source in 

roadmaps to fusion power 

Qualification of candidate materials, in terms of generation of 

engineering data for design design, licensing and safe operation of a fusion 

DEMO reactor, up to about full lifetime of anticipated use of DEMO 

Completion, calibration and validation of databases (today mainly 

generated from fission reactors and particle accelerators) 

Advanced material irradiation (towards power plant application) 

Promote Promote, verify or confirm selection processes 

Validation of fundamental understanding of radiation response of 

materials hand in hand with computational material science 

Science-related modeling of irradiation effects should be validated and 

benchmarked at length-scale and time-scale relevant for engineering 

application 

Experiments performed in IFMIF would validate assumptions or adjust 

parameters

TOP Level Requirements for an Intense Neutron Source 

Neutron spectrum 

Should simulate the first wall neutron spectrum of a fusion reactor as closely as 

possible p in terms of PKA spectrum, p , important p transmutation reactions, , and ggas 

production (He, H) 

Neutron fluence accumulation 

Up to 120 dpa dpaNRT in

TOP Level Requirements for an Intense Neutron Source 

Neutron spectrum 

Should simulate the first wall neutron spectrum of a fusion reactor as closely as 

possible p in terms of PKA spectrum, p , important p transmutation reactions, , and ggas 

production (He, H) 

Neutron fluence accumulation 

Up to 120 dpa dpaNRT in

Fusion Power Plants: Material Challenges beyond ITER 

20 

Blanket: ≤30 dpa/yr, 2.5MW/m 2 

Reduced Activation Structural Materials: 

- RAFM Steels (EUROFER) 300-550 °C 

- EUROFER-ODS 350-650 °C 

-SiCf/SiC for sophisticated concepts 

Functional materials 

- neutron multipliers, breeder ceramics 

Special purpose materials (diagnostic,…) 

Divertor: ≤10 dpa/yr 10-15 MW/m2 Divertor: ≤10 dpa/yr, 10-15 MW/m 

Refractory alloys (e.g. W-ODS) 

DEMOnstration 

Reactor Concept 

850 850-1200 1200 °CC ~600 600 - 1300 °C 

Nano-scaled RAF-ODS Steels 

Power: 130MW 1.30 MWe Plant Efficiency: 37-45% 

350-650 °C 

~250 - 800 °C 

5 m 

A. Möslang et al.

21 

Main Relations between ITER, , IFMIF and DEMO 

ITER 

Deuterium Deuterium-Tritium Tritium 

Test Blanket Modules 

DEMO Design Const. Operation 

IFMIF Const 

Fission Reactor and 

Charged Particle Irradiation 

~30 dpa 70-100 dpa 

Operation Operation 

~10 years 

A. Möslang et al.

Is today IFMIF still the best choice? 

Neutronics: IFMIF vs. the Spallation p source MaRIE (1/8) ( ) 

Total volume of irr. rigs ~ 0.4 l 

1 9 

3 7 

- Matter Radiation Interactions in Extremes - 

The Materials Test Station (MTS) ( ) is a spallation p source 

facility whose prime mission is the irradiation of fuels and 

materials in a fast neutron spectrum. 

Eric Pitcher et al. 

al

IFMIF vs. the Spallation source MaRIE (2/8) 

Neutron spectra Relevant for damage 

and transmutations 

in steels 

1E16 

1 ] 

s -1 MeV -1 

ty [cm -2 neeutron 

fluux 

densit s 

1E15 

1E14 

1E13 

1E12 

1E11 

1E10 

1E9 

MTS sample can #3 

MTS sample can #7 

DEMO first wall 

IFMIF back plate 

IFMIF HFTM 

1E8 

1E-3 0,01 0,1 1 10 100 1000 

neutron energy [MeV]


Di Displacement l t DDamage ffor diff different t rigs i 

-1 ] 

nt [dpa fpy - 

dissplacemen 

5.5 

5.0 

4.5 

4.0 

3.5 

3.0 

2.5 

MaRIE 1 MW 

Neutron 

Proton 

2.0 

0 1 2 3 4 5 6 7 8 9 10 

irradiation rig g # 

Irradiation Rig # 

5 dpa/y


Di Displacement l t DDamage: CComparison i of f ffacilities iliti 

Dammage, 

dpaa/fpy 

60 

50 

40 

30 

20 

10 

0 

acceleration l ti 

No possibility for 

accelerated irradiation 

DEMO FW IFMIF BP IFMIF HFTM MTS #3 MTS #7


HHelium li Production 

P d ti 

appm He/dpa H 

20 

MaRIE , 1 MW 

15 

10 

5 

0 

1 2 3 4 5 6 7 8 9 

irradiation rig # 

DEMO relevant l t 

He/dpa ratio in 

steels. 

IFMIF meets the 

relevant ratio in 

all test modules


Flux/volume considerations 

MTS beam power = 11.8 8 MeV 

IFMIF High flux 

MTS test position 

MTS fuel position 

Volume for 20 dpa/fpy 

IFMIF : ~ 500 cm 3 

MTS: ~ 250 cm 3 

Volume for 30 dpa/fpy 

IFMIF : ~ 360 cm 3 

MTS: ~ 40 cm 3 

Irradiation volume in cm E Pitcher LANL 

3 Irradiation volume in cm E. Pitcher, LANL 

3


Spallation p product p accumulation 

Fraction F [wppm] 

Frraction 

[wwppm] 

10 6 

10 4 10 5 

10 2 

10 3 

10 0 

10 -2 

10 1 

4 

1x10 -4 

10 -6 10 -1 

10 -8 

Eurofer composition irradiated up to 25 dpa (NRT) 

Eurofer composition irradiated up to 25 dpa (NRT) 

Mn 

H He 

MMaRIE RIE sample l can #3 ( (n + p) ) 

MaRIE sample can #3 (n + p) 


V 


HCLL Demo (FW) 

HCLL Demo (FW) 

HFTM 

HFTM 

Cr 

Ti 

B 

BBe N 

Al 

Li C N 

Na 

Al 

F 

Si 

Ne 

Mg 

O 

P 

S Cl Ar 

K Ca 

Sc 

Fe 

P & S !! 

0 

0 10 

10 20 

20 30 40 50 

Atomic 

At Atomic i 

number 

number b 

30 

60 70 80 

RAFM specification on S + P 


Effect of spallation elements on Ductile Brittle Transition 

KV (Jooule) 

12 

10 

8 

6 

4 

2 

O. DANILOVA, D. HAMON, Y. de CARLAN, A. ALAMO 

Effect of Dopping Elements on 

Impact Properties of EM10 

First SPIRE Progress meeting, 

Madrid. June 14-15, 2001 

EM10LCTi 

(ferritic) 

EM10 R 

Em10 Ti 

EM10 LM LMnS S 

EM10 TiPS 

0 

-160 -120 -80 -40 0 40 80 120 160 200 240 280 320 

Temperature (°C) 

Drop of upper shelf 

energy: 

+0.25% Ti 

+0.96% C 

+0.04% S 

-0.5% Mn 

+0.02% P 

Elements like S, P enhance severely the brittleness of Cr-steels

30 

Principle p of IFMIF 

Source 

140 mA D + 

LEBT 

100 keV 

Accelerator 

(125 mA x 2) 

RFQ 

MEBT 

Half Wave Resonator 

Superconducting Linac 

Lithium Target 

25 ±1 mm thick, 15 m/s 

HEBT 

5 MeV 9 14.5 26 40 MeV 

RF Power System 

Beam shape: 

200 x 50 0 mm2 H 

Test Cell 

M 

L 

High (>20 ( 20 dpa/y, 0.5 L) 

2 

Medium (>1 dpa/y, 6 L) 

Low ( 8 L) 

Typical reactions 

7Li(d Li(d,2n) 2n) 7 Be 

6Li(d,n) 7Be 6Li(n,T) 4He A. Möslang et al.

31 

IFMIF: The Accelerator of all records! 

(W) 

m Power 

Beam 

Energy (MeV) 

Unprecedented Unprecedented challenges 

True “Laboratory” Laboratory for studying 

• highest intensity 

physics of High Intensity Beams 

• 

• 

• 

• 

highest space charge 

highest power 

longest RFQ 

Very eyhigh g aavailability aab y&& reliability eab y 

(halo ( formation, core – halo 

interaction, emittance growth, 

sudden particle loss) 

A. Möslang et al.

Current activities: EVEDA 

The Engineering Validation and Engineering Design Activities, 

conducted in the framework of the Broader Approach aim at: 

Providing the Engineering Design of IFMIF 

Validating the key technologies, more particularly 

Th The llow energy part t of f th the accelerator l t ( (very hi high h iintensity, t it D CW b ) 

+ CW beam) 

The lithium facility (flow, purity, diagnostics) 

The high flux modules (temperature regulation, resistance to irradiation) 

Strong priority has been put on Validation Activities, through 

The Accelerator Prototype (Constructed in EU EU,tested tested in Rokkasho Rokkasho, JA) 

The EVEDA Lithium Test Loop (to be tested in Oarai, Japan) 

Two complementary (temperature range) designs of High Flux Test 

MModules d l and d an iin-situ it CCreep ffatigue ti TTest t Module 

M d l

33 

IFMIF: Implementation and Actors of the Project 

IFMIF/EVEDA Integrated Project Team 

Project Leader 

EU Coordinator + FG Leaders JA Coordinator + FG Leaders 

European p Home Team 

Project Team 

In Rokkasho 

Japanese Home Team 

International Fusion Materials Community (Users) 

A. Möslang et al.

Engineering Validation Activities 

Th The Accelerator A l t Prototype 

P t t

35 

Whole Accelerator with Beam Dump 

Injector 

& LEBT 

Radio Frequency 

Quadrupole 

SRF Linac 

Cryomodule 

HEBT 

A. Möslang et al.

36 

International Fusion Energy gy Research Centre 

Administration & 

Computer Simulation & 

DDEMO R&D Buildingg 

Research Building RRemote Experimentation Buildingg DDEMO R&D Buildingg 

IFMIF/EVEDA 

All buildings were completed 

Accelerator Building 

in March 2010 

A. Möslang et al.

37 

Manufacturing g of the injector j 

Ion Source 

Blockhouse at Saclay 

120 kV 

250 mA 

Solenoid 

magnetic measurement High Voltage Power Supply 

A. Möslang et al.

Assembly y of the EVEDA Lithium Test Loop p 

Facility Building 

[40m W , 80m L , 33m H ] 

JAEA Oarai 

• Commissioning 

undergoing d i 

• Start of the 

experiments: 

June 2011 

38 

ELiTe Loop construction completed in November 2010 

A. Möslang et al.

Engineering g g 

Validation Activities 

The High Flux Test Module

40 

High g Flux Test Module current design g 

1 

2 3 4 5 6 7 8 

33,4,5,6: 6 Irradiation Rigs 

1,2,7,8: Companion Rigs 

About 1000 samples 

A. Möslang et al.

41 

HELOKA-LP 

FFull ll scale l helium h li gas coolant l t loop l 

Test section area 

Compressor station 

A. Möslang et al.

IFMIF schedule - Optimistic scenario 

p pp 

EVEDA phase 

Engineering activities 

Validation activities 

IFMIF International Review 

Decision to built IFMIF (that includes to 

built up the international consortium and 

the site decision) 

IFMIF CODA 

Start‐up of international team 

Detailed engineering (site adaptation, 

validation activities results,…) 

IFMIF construction 

IFMIF commissioning and startup 

First data obtained 

2010 2015 2020 2025 2030 

2010 2015 2020 2025 2030 

Ad Advantages t 

• On time for DEMO design 

• Possible some impact on ITER TBM operation 

• Present IFMIF team and expertise is maintained along the time 

Challenge 

• Significant g EU budget g required q during g 

FP8 2014-2020

IFMIF schedule - Reference scenario 

EVEDA phase 











IFMIF construction 



Advantages 

2010 2015 2020 2025 2030 

2010 2015 2020 2025 2030 

• IFMIF close to the time for DEMO (first data of IFMIF at same time 

than ITER DT results) 

• Relatively low EU budget required before 2020 (the Host country can 

offer to support the International Team during some time) 

• Expertise and team developed during EVEDA can be maintained

IFMIF schedule - Pesimistic scenario 

EVEDA phase 











IFMIF construction i 



2010 2015 2020 2025 2030 

2010 2015 2020 2025 2030 

Ad t 

Advantages 

• No EU budget required before 2020 

Problems 

• IFMIF in the critical path of DEMO 

• The expertise developed during the EVEDA phase will be lost

45 

“Hasinger Report”, 2010 


-Prepare CODA 

- Negotiations 

- Complete design 

5-6 calendar years 

Construction 

and 

commissioning 

6 calendar years 

Irradiation+PIE* 

55-10 10 dpa/fpy dpa/fpy, 30% duty cycle 

>15 calendar years ! 

Irradiation+PIE 

*20-55 dpa/fpy 

70% duty cycle 

4 calendar years 

Scenario 1 

DEMO design 

(in-vessel) finished 

*Materials data base: 

~50 dpa for blanket 

CTFs ~20 dpa for divertor 

A. Möslang et al.

46 

Summary and Conclusions 

IFMIF meets fully the mission and the requirements of an intense fusion 

neutron source and is able to deliver timely the major pillars of a materials 

database for construction, licensing and safe operation of a DEMO reactor 

Main Milestones: 

June 2013: Delivery of the Intermediate IFMIF Engineering Design Report 

June 2015: Start of the experiments of the whole Accelerator Prototype 

June 2017: End of the studies in the framework of the BA agreement 

DDec. 2013 2013: EEnd d of f IFMIF EVEDA ffor all ll activities ti iti not t contributing t ib ti tto th the 

Accelerator Prototype 

It is expected p that the Intermediate IFMIF Engineering g g Design g Report p will be 

the basis for an evaluation through for an international review panel. 

Based on that results, siting negotiations could start immediately 

IFMIF needs funding during 2014 2014-2020. 2020 Otherwise Otherwise, 

- IFMIF will be at the critical path for DEMO, and 

- the power of the present team and its competence will be lost 

A. Möslang et al.

E.Diegele,IFMIF Necessity and Status of Preparation.pdf

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