Microstructural design of PCA austenitic stainless steel for improved resistance to helium embrittlement under HFIR irradiation
Several variants of Prime Candidate Alloy (PCA) with different preirradiation thermal-mechanical treatments were irradiated in HFIR and were evaluated for embrittlement resistance via disk-bend tensile testing. Comparison tests were made on two heats of 20%-cold-worked type 316 stainless steel. None of the alloys were brittle after irradiation at 300 to 400/sup 0/C to approx. 44 dpa and helium levels of 3000 to approx.3600 at. ppm. However, all were quite brittle after similar exposure at 600/sup 0/C. Embrittlement varied with alloy and pretreatment for irradiation to 44 dpa at 500/sup 0/C and to 22 dpa at 600/sup 0/C. Better relative embrittlement resistance among PCA variants was found in alloys which contained prior grain boundary MC carbide particles that remained stable under irradiation.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6364606
- Report Number(s):
- CONF-830942-92; ON: DE85000914
- Country of Publication:
- United States
- Language:
- English
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ALLOYS
AUSTENITIC STEELS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DATA
DESIGN
ELEMENTS
EMBRITTLEMENT
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FLUIDS
GASES
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HELIUM
HFIR REACTOR
HIGH TEMPERATURE
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NICKEL ALLOYS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
RARE GASES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS