# Presentation: 157121

## Fusion Materials Sciences Program

- Steve Zinkle
- VLT meeting
- DOE-OFES, Germantown, MD
- August 25, 2005

## Key R&D Thrusts over next 5 years for Fusion Materials

- ITER structural materials
- ITER insulator and plasma diagnostics
- Ferritic/martensitic steels for ITER TBM and beyond
- SiC composites for ITER TBM and beyond
- Cross-cutting theory and modeling
- Chemical compatibility
- Higher performance materials development
- Liquid breeder materials (MHD insulator)

## Descriptions of Materials R&D thrusts

- ITER structural materials
- Materials properties handbook authorship/review, CuCrZr irradiated fracture toughness, Cu-Be alloy testing for compression collar, cast stainless steel qualification (Module 18), Cu/Be joining, Cu/SS joining, SC coil jacket material support
- ITER insulator and plasma diagnostics
- ICH insulator radiation-induced degradation in loss tangent and thermal conductivity, ITPA specialists working group on Radiation Effects, fiber optics, mineral insulated cable and 1st mirror degradation mitigation
- Ferritic/martensitic steels for ITER TBM and beyond
- DOE/JAERI program (radiation effects including fusion-relevant He generation on base metal and weldments)
- SiC composites for ITER TBM and beyond
- Development of hermetic low conductivity flow channel insert for ITER TBM
- SiC/SiC structural composites (engineering design-relevant mechanical property tests, radiation effects, crack propagation)

## Descriptions of Materials R&D thrusts (cont’d)

- Cross-cutting theory and modeling
- Physics of radiation hardening and embrittlement; fracture mechanics “Master Curve” testing and analysis, “VISTA” multiscale structural analysis for ITER TBM, etc.
- Chemical compatibility
- Pb-Li compatibility testing of SiC, Ni-base alloys, ferritic/ martensitic steels for ITER TBM and beyond
- Higher performance materials development
- ODS ferritic steels, 3 Cr bainitic steels, ductile Mo alloys.,V alloys with high precipitate densities
- Liquid breeder materials (MHD insulator)
- Jupiter-II research on Li interactions with AlN, Eu2O3 and Y2O3 insulators and V alloy substrate (to be completed April 2007)

## Current Spending on R&D Thrusts

- 120 k$ ITER structural materials
- 520 k$ ITER insulator and plasma diagnostics
- 1840 k$ Ferritic/martensitic steels for ITER TBM & beyond
- 1530 k$ SiC composites for ITER TBM and beyond
- 1909 k$ Cross-cutting theory and modeling
- 150 k$ Chemical compatibility
- 914 K$ Higher performance materials development
- 270 k$ Liquid breeder materials (MHD insulator)
- 70 k$ Neutron source (discontinued after FY05)
- 7323 k$ Total (FY05)

## Characterization of R&D thrusts to VLT missions

|  | ITER Base machine | R&D needed for ITER to be successful (dual use) | ITER as test bed (TBM, etc) | Next generation technology (for current and future machines) | Longer Term R&D |
| --- | --- | --- | --- | --- | --- |
| ITER structural materials | X | X |  |  |  |
| ITER insulator and plasma diagnostics | X | X | X |  | X |
| F/M steels for ITER TBM and beyond |  |  | X | X | X |
| SiC composites for ITER TBM and beyhond |  |  | X | X | X |
| Cross-cutting theory and modeling |  |  | X | X | X |
| Chemical compatibility |  |  | X | X | X |
| Higher performance materials R&D |  |  | X | X | X |
| Liquid breeder materials (MHD insulator) |  |  | X |  | X |

## US fusion materials ITER-relevant R&D

- Critical assessment of data for ITER materials properties handbook
- In-vessel structure and armor materials (Cu alloys, 316SS, superalloys, etc.)
- candidate polymer materials for the vacuum vessel support system
- Fill gaps in existing ITER materials database that are needed for realistic engineering design
- Investigate potential for irradiation assisted stress corrosion cracking in copper alloys
- Allowable dose limits for IC plasma heating feedthrough insulators
- CuCrZr irradiated fracture toughness
- Effect of various plasma facing material bonding techniques on properties
- Identify potential for new degradation phenomena under ITER-relevant conditions
- Various electrical degradation mechanisms in plasma diagnostics during irradiation
- Establish viability of materials systems for proposed ITER test blanket modules
- Low dose neutron effects on properties of various weldments and base materials
- Effects of thermomechanical treatment on the properties of candidate materials after low dose neutron irradiation
- Chemical compatibility of material, coolants and fusion environment (including tritium)

## FY05 ITER Materials activities

- Authorship/critical assessment of ITER materials properties handbook chapters (ITA 74-05US)
-  High strength Cu alloy for compression collar (blanket attachment) and neutron irradiation R&D (ITA 74-07 US)
- ICH insulators radiation-induced degradation in loss tangent and thermal conductivity (ITA 51-08)
- Participate in plasma diagnostics ITPC workshops (watching brief on radiation effects and experimental artifacts)
- Based on ITA 55-03, etc.
- Assessment of superconducting magnet jacket materials
- (related to ITA 11-44-US; assist MIT assessment of JK2LB fracture behavior)
- Module 18 materials consultation (preliminary stages)
- Based on ITA 16-26 work to be performed in FY06