Budget (w/o overheads) Total Allocated Resources Hardware (EC/k) - - PowerPoint PPT Presentation

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T HE E UROPEAN R&D P ROGRAMME ON D IVERTOR A RMOR MATERIALS AND T ECHNOLOGY S TATUS AND S TRATEGY M. Rieth , S. Antusch, J. Hoffmann, M. Klimenkov, J. Reiser, S. Brezinsek, W. Biel, J. Coenen, J. Linke, Ch. Linsmeier, A. Litnovsky, Th.

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SLIDE 1

THE EUROPEAN R&D PROGRAMME ON DIVERTOR ARMOR MATERIALS AND TECHNOLOGY – STATUS AND STRATEGY

  • M. Rieth, S. Antusch, J. Hoffmann, M. Klimenkov, J. Reiser, S. Brezinsek, W. Biel,
  • J. Coenen, J. Linke, Ch. Linsmeier, A. Litnovsky, Th. Loewenhoff, G. Pintsuk,
  • B. Unterberg, M. Wirtz, H. Greuner, A. Kallenbach, R. Neu, J. Riesch, J.H. You,
  • T. Barrett, F. Domptail, S. Dudarev, M. Fursdon, M. Gilbert, A. Galatanu, L.M. Garrison,
  • Y. Katoh, L.L. Snead, D. Armstrong, S. Roberts
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SLIDE 2

Budget (w/o overheads)

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

500 1000 1500 2000 2500 1 2 3 4 5

Hardware (EC/k€)

Total Allocated 2014‐18 2300 2400 2500 2600 2700 1 2 3 4 5

Manpower (EC/k€)

Total Allocated 2014‐18

Total Allocated Resources

273 lab ppy 30 ind ppy 8.74 M€ hw

today

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SLIDE 3

Overall Objectives 2014-2018

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Fill gaps in the database and develop design codes for the

baseline materials

  • Development of new materials to mitigate requirements of

advanced DEMO component designs

  • Demonstration of the production of such materials in processes

scalable to industrial standards

  • Characterization of the properties of such materials
  • Develop models for neutron radiation effects, specifically

microstructural evolution and embrittlement, in iron alloys, steels, tungsten, and degradation of functional materials

  • Perform neutron irradiation experiments

focus of this presentation: armour

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SLIDE 4

Overview of HHF Materials

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

W (PIM) W PLANSEE (rolled) Ductile @ 200 °C Fracture W‐2Y2O3 W‐1TiC W‐2La2O3

W Alloys (by PIM)

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SLIDE 5

Overview of HHF Materials

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

W CuCrZr

Cu Cu Cu Cu W WW

Cu/CuCrZr‐W Pipes/Laminates

Composites

Cu/CuCrZr‐W‐fiber Pipes W‐W‐fiber Blocks

CuCrZr

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SLIDE 6

Overview of HHF Materials

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

W‐Cu/CuCrZr Composite

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SLIDE 7

Overview of HHF Materials

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

Material Characterisation

  • microstructure, chemical analysis
  • physics: heat conductivity (diffusivity & heat capacity)
  • strength: tensile, bending (3 pt., 4 pt.)
  • toughness: bending (fracture mechanics, DBTT, strain rate effect)
  • HHF tests

mockup (JUDITH & GLADIS) thermal shock (several FZJ facilities) 4 mm 4 mm

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SLIDE 8

Divertor assessment methodology

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • A suitable method of divertor PFC

assessment is a significant issue to be resolved

– Current nuclear design codes neither consider multi-layer/multi-material structures nor stress due to manufacturing – Instead of “design by analysis”, ITER have used “design by experiments” including intensive HHF testing

  • Bespoke criteria based on elasto-

plastic analyses are currently under development in EUROfusion

  • The immediate need to facilitate

PFC design optimisation was a standardised analysis procedure using linear elastic code rules

Typical Mock‐Up Thermal analysis Stress analysis

1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

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SLIDE 9

Standard thermo-mechanical analysis

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • “Monoblock Elastic Analysis Procedure” - “MEAP”
  • Coherent/consistent analyses across EU DIV project
  • Reserve factors (margin to failure) to 5 Rules are

calculated, enabling ranking of design concepts

  • 2 structural rules, which are valid despite the

considerable residual stress field, and 3 thermal rules

  • 10 MW/m2 surface heat flux is used for analyses
  • NOT a method for “absolute” failure assessment!

MEAP rule Rule details Rule #1 Ratchetting (3Sm)  first check, runaway ratchetting is not expected in reality *. Requires material Sm data. Rule #2 Fatigue – following IC3132.3.1*. Requires material cyclic ‐ and ‐n data. Rule #3 For a CuCrZr pipe, maximum temperature <300°C to avoid creep/softening under irradiation. Minimum temperature > 150°C to limit embrittlement. Rule #4 Maximum wall heat flux < device Critical Heat Flux (burnout) Rule #5 Maximum tungsten armour temperature <1800°C , to limit recrystallisation

* Reference: ITER Structural Design Criteria for In‐vessel Components, ITER G‐74‐MA‐8‐01‐05‐28‐W‐0.2, 2012.

1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

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SLIDE 10

Outline

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • How to develop divertor materials without knowing the critical

limits, which are closely connected to the design, which in turn is under development, too?

  • What are the relevant properties for divertor armour materials?
  • Do we perform appropriate assessment tests?
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SLIDE 11

Load Analysis, Basic Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Thermal
  • ff‐normal

20 MW/m2

#1 #2 #10000 2 fpy normal

10 MW/m2

t HF

0.2‐1 GW/m2 ELM

15 MW/m2 (30s), small monoblock 23 mm x 22 mm x 4 mm, D15 mm

water cooling, 200 °C

  • M. Li, IPP

10 MW/m2 + 0.4 GW/m2 (1ms on, 50ms off) ITER type monoblock 28 mm x 28 mm x 12 mm, D17 mm

1800

Temperature (°C)

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SLIDE 12

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Mechanical, elastic

normal t HF

10 MW/m2

10s

path

‐1200 +1200

path (mm) Temperature (°C) Stress (MPa) Yield Limit (MPa) Sxx plastic deformation under compression

Load Analysis, Basic Properties

+740 MPa ‐670 MPa Stress

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SLIDE 13

Load Analysis, Basic Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Mechanical, plastic

normal t HF

10 MW/m2

10s 20s

Plastic Deformation (10 s)

3.1E‐3

  • Pl. Strain

1.1E‐3 2.1E‐3

Secondary Stresses (20 s)

365 MPa ‐110 MPa Stress 200 MPa

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SLIDE 14

Load Analysis, Basic Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Mechanical, plastic

normal t HF

10 MW/m2

10s 20s

  • Max. Stress during cooling
  • Strain rate: 10‐3/s – 10‐2/s
  • 150 °C < DBTT <250 °C
  • T > 300 °C

 ductile regime  no brittle fratcure

  • Mechanical, dynamic
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SLIDE 15

Load Analysis, Basic Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Thermal: Tsurf = 1790‐2112 °C

 Recrystallisation (Rxx)

  • ff‐normal

t HF

20 MW/m2

10s 20s

  • Dynamical: DBTT 250‐350 °C (W‐Rxx)

ductile‐brittle regime

  • Fracture Mechanics
  • KIc = 5‐8 MPa m1/2 (W‐Rxx)
  • critical crack length = 16‐40 µm
  • grain size: min. 50 µm, max. >300 µm

ductile/brittle crack formation likely

  • Mechanical
  • plastic surface deformation > 1%

during heating

  • secondary surface tensile stresses

after cooling down: > 710 MPa

710 MPa ‐973 MPa Stress ‐500 MPa

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SLIDE 16

Load Analysis, Basic Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Thermal

normal t HF

10 MW/m2

1ms 50ms

0.2 GW/m2

time

300 1500

path (mm) Temperature (°C)

  • Mechanical

strain rates > 1/s

‐200 350

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SLIDE 17

Load Analysis, Basic Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

normal t HF

10 MW/m2

1ms 50ms

0.2‐1.0 GW/m2

210 MW/m2, 1 ms 10 MW/m2, 51 ms

  • Mechanical  Surface Area

 only a thin layer (500 µm) is loaded with high strain rates (> 1/s) at 1000‐1400 °C  plastic surface deformation under tensile and compression without immediate damage  Tmax: 0.2 GW/m2 – 1400°C, 0.4 GW/m2 – 1750°C, 0.6 GW/m2 – 2100°C, 0.8 GW/m2 – 2500°C, 1 GW/m2 – 2900°C (1 mm surface layer with 1‐5% deformation)  Recrystallisation

785 MPa ‐385 MPa Stress 760 MPa ‐350 MPa Stress

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SLIDE 18

Load Analysis, Basic Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • 10 MW pulse + 1 GW/1 ms  stress after cooling down to 300 °C

off‐normal events could be more demanding compared to ELM discharges 20 MW/m2 pulse on and off

710 MPa ‐973 MPa Stress ‐500 MPa 704 MPa ‐313 MPa Stress

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SLIDE 19

First Conclusions

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Comparison with experiment: ITER mockup, 300 x 20 MW/m2 pulses

lower operating temperature (pulse off period) is decisive HHF mockup tests modification (cooling temperature, in‐situ crack detection, ...) relevant material properties for this particulare case: Recryst.‐Temp. & static DBTT (W‐Rxx) & initial cracks

6‐7.5 mm

  • Critical operating point for cracking

>1700°C t Surface Temperature

20 MW/m2 compression

10s 20s <100°C DBTT

0 MW/m2 tensile stress

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SLIDE 20

Additional Material Properties

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Fatigue

#1 #2 #10000 2 fpy normal

10 MW/m2

t HF

0.2‐1 GW/m2 ELM

t stress t T

  • Normal pulse operation would correspond to asymetric Low Cycle

Thermal Fatigue conditions

  • but ELM discharges correspond to high strain rate, high

temperature, High Cycle Thermal (Shock) Fatigue this is not covered by usual material tests (LCF, LCTF, HCF, etc.) current thermal shock tests need (slight) modification (?)

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SLIDE 21

Changing Conditions During Operation

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Microstructure o Recrystallisation
  • Cyclic plastic deformation

 Strength, DBTT, toughness, ductility and fatigue properties will vary during operation

  • Geometry
  • Erosion of armour surface due to PSI (max.

2‐3 mm/fpy ?, depending on T)  Temperature and load will vary with time

  • Irradiation
  • Continuous increase of damage (2 dpa/fpy in

striking point, 4 dpa/fpy elsewhere)

  • Damage strongly depends on temperature and

neutron spectrum  Inhomogeneous variation of material properties  Strength, DBTT, toughness, ductility, thermal conductivity, fatigue properties, microstructure, density (swelling), erosion rate?, others?

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SLIDE 22

Irradiation Defects

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

Void Formation (Swelling) Transmutation into Rhenium

  • About 0.5‐1% Rhenium/fpy

 Embrittlement, loss of conductivity, …  Extend unknown (no experiments with appropriate n‐spectrum available)

  • Max. at 600‐900°C

 Embrittlement, loss

  • f conductivity, …
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SLIDE 23

Outlook: Preliminary Answers

23

1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • How to develop divertor materials without knowing the critical

limits, which are closely connected to the design, which in turn is under development, too?

  • What are the relevant properties for divertor armour materials?
  • Do we perform appropriate assessment tests?
  • Close cooperation with divertor community with the goal to

minimize number of concepts, geometries, operating and boundary conditions, …

  • ??? There is no simple answer. It depends on too many issues …
  • In principle, yes ‐ but …

(1) Variation of monoblock tests would be interesting: cooling temperature, crack detection, … (2) Thermal shock tests should be re‐assessed for possible extension improved material assessment

  • However, the relevance of tests is closely connected to the
  • design. Different concepts might require different tests.
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SLIDE 24

Finally ...

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • Tungsten (armour) is not the only material involved
  • There are interfaces (e.g. W‐Cu, CuCrZr‐Cu)  Composites
  • There are structural parts
  • There are additional boundary conditions …

Each additional material requires separate assessment for microstructural change, geometry, and irradiation damage !!! WPMAT strategy: iterative approach (interaction with divertor & plasma community) Development of a broad variety of different HHF materials & composites WITHOUT predefined target properties

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SLIDE 25

Thank you !

1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

25

Partners: and joined universities

Disclaimer: „This work has been carried out within the framework

  • f the EUROfusion Consortium

and has received funding from the Euratom research and training programme 2014‐2018 under grant agreement No 633053. The views and opinions expressed therein do not necessarily reflect those of the European Commission.“

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SLIDE 26

Additional Slides

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
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SLIDE 27

Mass production of W parts and W alloys development

1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

27

Achievements in HHFM

Monoblocks with various shapes Samples for ASDEX Upgrade Langmuir probes for WEST

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SLIDE 28

HHF Tests in JUDITH: PLANSEE pure tungsten according to ITER specifications (‟IGP”) compared to PIM W alloys

PIM: W-2La2O3 PIM: W PIM: W-2Y2O3

longitudinal transversal recrystallized # T [°C] Pabs [GW/m2] Δt [ms] Eabs [MJ/m2] FHF [MW/m2*s1/2] # shots °C 1000 0.38 1 0.38 12 1000

100 µm 100 µm 100 µm 100 µm 100 µm 100 µm

1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

28

Achievements in HHFM

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SLIDE 29

„Self-Castellation in ITER“

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy
  • ff‐normal

t HF

20 MW/m2

10s 20s

uncracked monoblock cracked monoblock

crack from top to interlayer (free surface)

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SLIDE 30

Irradiation Defects

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1st IAEA Technical Meeting on Divertor Concepts | IAEA HQ | VIC | Vienna | 29.09.-2.10.2015

  • M. Rieth et al.: EUROfusion WPMAT HHFM - Status & Strategy

Tungsten Tungsten‐5% Rhenium (in solid solution)

  • J. Linke, FZJ