Deformation behavior around grain boundaries for SCC propagation in hardened low-carbon austenitic stainless steel by micro hardness test
- 1. National Inst. for Materials Science (NIMS), Ibaraki (Japan)
- 2. Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
- 3. Japan Nuclear Energy Safety Organization (JNES), Tokyo (Japan)
Description
Stress corrosion cracking (SCC) was found in shroud and PLR piping made of low-carbon austenitic stainless steels in Japanese BWR plants. The intergranular type (IG) SCC propagated in hardened heat affected zones (HAZ) around welds. Strength behavior and local plastic deformation for a low-carbon austenitic stainless steel 316L, rolled at the reductions in area of 10, 30% at room temperature to simulate the hardened HAZ, were measured by a micro-hardness test machine and observed by atomic force microscopy (AFM), respectively. The tensile deformation at yield point (0.2% plastic strain) had given to the work-hardened 316L to simulate the plastic zone at the crack tip. It is suggested that one of the IGSCC propagation mechanism for 316L was related with the intergranular strength behavior and local plastic deformation around grain boundaries. (author)
Additional details
Publishing Information
- Publisher
- Canadian Nuclear Society
- Imprint Place
- Toronto, Ontario (Canada)
- ISBN
- 0-919784-89-5
- Imprint Title
- 13th International conference on environmental degradation of materials in nuclear power systems
- Imprint Pagination
- 388 Megabytes
- Journal Page Range
- [15 p.]
Conference
- Title
- 13. International conference on environmental degradation of materials in nuclear power systems
- Dates
- 19-23 Aug 2007
- Place
- Whistler, BC (Canada)
INIS
- Country of Publication
- Canada
- Country of Input or Organization
- Canada
- INIS RN
- 39116913
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AUSTENITIC STEELS; BWR TYPE REACTORS; CRACK PROPAGATION; CRACKING; DEFORMATION; INTERGRANULAR CORROSION; PIPES; SHROUDS; STAINLESS STEEL-316L; STRAIN HARDENING; STRESS CORROSION; WELDED JOINTS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; COOLING SYSTEMS; CORROSION; CORROSION RESISTANT ALLOYS; DECOMPOSITION; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HARDENING; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; JOINTS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; PYROLYSIS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEELS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs., 4 tabs., 12 figs.