Microstructural development of PCAs irradiated in HFIR at 300 to 400/sup 0/C

Conference · Tue Dec 31 23:00:00 EST 1985

OSTI ID:5774935

Tanaka, M P; Maziasz, P J; Hishinuma, A; Hamada, S

Microstructural developments were determined on solution-annealed (SA) and cold-worked (CW) JPCA and US PCAs irradiated in the High Flux Isotope Reactor (HFIR) at 300 and 400/sup 0/C. Irradiation produced damage levels of about 10 and 34 dpa and helium concentrations of around 580 and 2500 at. ppM, respectively. High concentrations of fine bubbles and MC precipitates, as well as Frank faulted loops, were observed in both SA and CW PCAs. Mutual stability of the MC particles and associated fine bubbles contributed to the extension of the transient regime of swelling to higher fluence. The irradiation responses of JPCA and US-PCA were similar in the HFIR, despite minor compositional differences (P,B) between the two materials. Useful fusion applications of SA-PCA as well as CW-PCA in the 300/sup 0/C temperature range are suggested from these data.

• Research Organization: Oak Ridge National Lab., TN (USA); Japan Atomic Research Inst., Tokai, Ibaraki. Dept. of Fuels and Materials Research
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5774935
• Report Number(s): CONF-860421-37; ON: DE86010394
• Country of Publication: United States
• Language: English

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ALLOYS
AUSTENITIC STEELS
BUBBLES
CRYSTAL STRUCTURE
ENRICHED URANIUM REACTORS
HFIR REACTOR
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MEDIUM TEMPERATURE
MICROSTRUCTURE
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STEELS
SWELLING
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
THERMONUCLEAR REACTOR MATERIALS
WATER COOLED REACTORS
WATER MODERATED REACTORS