Microstructural evolution of austenitic stainless steels irradiated in spectrally tailored experiment in ORR at 400deg C
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
- 2. Oak Ridge National Lab., TN (United States)
Description
Several different heats of austenitic stainless steel, including Japanese-PCA(JPCA), were irradiated in the spectrally tailored ORR experiment at 400deg C to 7.4 dpa. The levels of helium generated were 155 appm for JPCA (16Ni, 30 wppm B) and 102 appm for standard type 316 steel (13Ni). The mean He:dpa ratio throughout the irradiation falls between 15 and 20 appm He/dpa, which is close to the He/dpa values expected for fusion. Swelling was measured by transmission electron microscopy and by precision immersion densitometry. All the CW alloys showed swelling that was at or below the detection limit of the densitometer (0.1%). No measurable swelling was detected in the SA JPCA alloy, while the highest value of 0.8% was observed in the SA high-purity alloy. One Ti-modified steel with low C also showed a relatively high swelling value of 0.5%, while standard type 316 steel showed only 0.15% swelling. TEM observation gave consistent but slightly larger values of swelling. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 191-194
- Journal Issue
- pt.B
- Journal Page Range
- p. 712-716.
- 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
- 24031525
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AUSTENITIC STEELS; BUBBLE GROWTH; CARBIDES; CAVITIES; CHEMICAL COMPOSITION; DENSITY; EXPERIMENTAL DATA; HELIUM; MICROSTRUCTURE; ORR REACTOR; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; STAINLESS STEELS; STEEL-CR17NI12MO3; SWELLING; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTOR MATERIAL; TRANSMISSION ELECTRON MICROSCO
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CARBON COMPOUNDS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STE; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; DEFORMATION; ELECTRON MICROSCOPY; ELEMENTS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MICROSCOPY; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NONMETALS; NUMERICAL DATA; PHYSICAL PROPERTIES; RADIATION EFFECTS; RARE GASES; REACTORS; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; WATER COOLED REACTORS; WATER MODERATED REACTORS