Stress corrosion cracking and intergranular corrosion of neutron irradiated austenitic stainless steels
Creators
- 1. Nuclear Engineering Lab., Toshiba Corp., Yokohama (Japan)
- 2. Nuclear Energy Div., Toshiba Corp., Yokohama (Japan)
- 3. Research Inst. for Iron, Steel and other Metals, Tohoku Univ., Oorai, Ibaraki (Japan)
Description
The effects of irradiation on stress corrosion cracking (SCC) and intergranular corrosion (IGC) susceptibilty were investigated in solution-treated Fe-19Cr-9Ni-Mn alloys and JPCA irradiated to 5.3x1024 n/m2 (E> 1 MeV) at 573 K. In Fe-19Cr-9Ni-Mn alloys, the irradiation enhanced IGC in boiling HNO3 + Cr6+ solution when the alloys contained phoshorus and silicon and induced SCC in all the alloys with strain rate tensile tests in 571 K water containing 32 ppm oxygen. With increasing phosphorus and silicon contents, IGC was promoted but IGSCC was suppressed after irradiation. The results indicated that these elements are not the main contributors to irradiation-assistend SCC, although they affect SCC behavior. The Japanese Prime Candidate Alloy (JPCA) had better SCC resistance than Fe-19Cr-9Ni-Mn alloys under the present irradiation condition. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 191-194
- Journal Issue
- pt.B
- Journal Page Range
- p. 1007-1011.
- 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
- 24031569
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AUSTENITIC STEELS; CHROMIUM IONS; CHROMIUM-NICKEL STEELS; CORROSION; ELONGATION; EXPERIMENTAL DATA; FISSION NEUTRONS; FRACTOGRAPHY; GRAIN BOUNDARIES; JMTR REACTOR; NEUTRON FLUENCE; NITRIC ACID; OPTICAL MICROSCOPY; PHOSPHORUS ADDITIONS; PHYSICAL RADIATION EFFECTS; SCANNING ELECTRON MICROSCOPY; SILICON ADDITIONS; STAINLESS STEELS; STRAIN RATE; STRESS CORROSION; TEMPERATURE RANGE 0400-1000 K; TENSILE PROPERTIES; THERMONUCLEAR REACTOR MATERIAL; WEIGHT; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CHARGED PARTICLES; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CRYSTAL STRUCTURE; DATA; DEFORMATION; ELECTRON MICROSCOPY; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; INFORMATION; INORGANIC ACIDS; INORGANIC COMPOUNDS; IONS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; MICROSCOPY; MICROSTRUCTURE; NEUTRONS; NICKEL ALLOYS; NITROGEN COMPOUNDS; NUCLEONS; NUMERICAL DATA; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; TEST FACILITIES; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS