Fusion Materials Sciences Program

1
Fusion Materials Sciences Program

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

2
Key RD 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)

3
Descriptions of Materials RD 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)

4
Descriptions of Materials RD thrusts (contd)

• 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)

5
Current Spending on RD 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)

6
Characterization of RD thrusts to VLT missions
7
US fusion materials ITER-relevant RD

• 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)

8
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 RD
  (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