Improved swelling resistance for PCA austenitic stainless steel under HFIR irradiation through microstructural control
Six microstructural variants of Prime Candidate Alloy (PCA) were evaluated for swelling resistance during HFIR irradiation, together with several heats of type 316 stainless steel (316). Swelling was negligible in all the steels at 300/sup 0/C after approx. 44 dpa. At 500 to 600/sup 0/C 25%-cold-worked PCA showed better void swelling resistance than type 316 at approx. 44 dpa. There was less swelling variability among alloys at 400/sup 0/C, but again 25%-cold-worked PCA was the best. Microstructurally, swelling resistance correlated with development of fine, stable bubbles whereas high swelling was due to coarser distributions of bubbles becoming unstable and converting to voids (bias-driven cavities).
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5434799
- Report Number(s):
- CONF-830942-65; ON: DE84003203
- Country of Publication:
- United States
- Language:
- English
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ALLOYS
AUSTENITIC STEELS
BARYON REACTIONS
BUBBLES
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
DATA
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HFIR REACTOR
HIGH TEMPERATURE
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NICKEL ALLOYS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SWELLING
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THERMONUCLEAR REACTOR MATERIALS
VOIDS
WATER COOLED REACTORS
WATER MODERATED REACTORS