Radiation effects on grain boundary chemistry relevant to stress corrosion cracking of stainless steels
Creators
- 1. Pacific Northwest Lab., Richland, WA (United States)
Description
Calculated grain boundary microchemistries are related to the potential for irradiation-assisted stress corrosion cracking (IASCC) for the proposed International Thermonuclear Experimental Reactor (ITER) conditions of irradiation temperature and dose. Radiation-induced segregation predictions are calibrated to measured segregation at temperatures above 250deg C and are then used to extrapolate to expected segregation behavior for ITER temperatures of 50 to 100deg C. Chromium depletion and impurity enrichment is predicted to occur for ITER conditions. Although the predicted segregation is less than that observed for light-water reactor conditions (LWR) experience with cracking in nonirradiation environments suggest that cracking may still occur because of possible differences in stress and environment. Experiments are required to verify the predicted ITER microchemistries and to demonstrate that the microchemistries will not promote cracking for specific ITER conditions. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 191-194
- Journal Issue
- pt.B
- Journal Page Range
- p. 1002-1006.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 5. international conference on fusion reactor materials (ICFRM-5).
- Dates
- 17-22 Nov 1991.
- Place
- Clearwater, FL (United States).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 24031568
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CHEMICAL COMPOSITION; GRAIN BOUNDARIES; IMPURITIES; ION BEAMS; ITER TOKAMAK; KIRKENDALL EFFECT; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; SEGREGATION; STAINLESS STEELS; STRESS CORROSION; STRESSES; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; THEORETICAL DATA; THERMONUCLEAR REACTOR MATERIAL
- Descriptors DEC
- ALLOYS; BEAMS; CARBON ADDITIONS; CHEMICAL REACTIONS; CLOSED PLASMA DEVICES; CORROSION; CRYSTAL STRUCTURE; DATA; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MICROSTRUCTURE; NUMERICAL DATA; RADIATION EFFECTS; STEELS; TEMPERATURE RANGE; THERMONUCLEAR DEVICES; TOKAMAK DEVICES