Microstructural development of titanium-modified austenitic stainless steel under neutron irradiation in HFIR up to 57 dpa
The Japanese prime candidate alloy (JPCA), a titanium modified austenitic stainless steel, has shown good performance after irradiation in HFIR up to 34 dpa at 300 C to 600 C, but considerable void swelling develops in solution annealed (SA) JPCA after irradiation 57 dpa at 500 C. However, cold worked (CW) or cold worked and aged (CW+A) JPCA still demonstrates good performance after similar irradiation. Swelling resistance appears to strongly depend on the behavior of fine titanium-rich MC precipitates. This paper describes the microstructural evolution process observed in the JPCA steel during HFIR irradiation. The onset of rapid void swelling was related to MC precipitate dissolution, and the instability of the MC was interpreted in terms of a model involving the build of and effects of a solute segregation zone in the matrix surrounding the precipitate particle. 8 refs., 9 figs., 3 tabs.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6927166
- Report Number(s):
- CONF-880613-15; ON: DE88013248
- Country of Publication:
- United States
- Language:
- English
Similar Records
Microstructural development of PCAs irradiated in HFIR at 300 to 400/sup 0/C
Void-precipitate association during neutron irradiation of austenitic stainless steel
Related Subjects
360102 -- Metals & Alloys-- Structure & Phase Studies
360106* -- Metals & Alloys-- Radiation Effects
AGING
ALLOYS
AUSTENITIC STEELS
BUBBLES
CHEMICAL COMPOSITION
COLD WORKING
CRYSTAL STRUCTURE
FABRICATION
HEAT TREATMENTS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS WORKING
MICROSTRUCTURE
PHASE STABILITY
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SEGREGATION
STABILITY
STEELS
SWELLING
TITANIUM ADDITIONS
TITANIUM ALLOYS
VOIDS