Influence of annealing on grain boundary segregation of neutron irradiated type 316L stainless steel
Creators
- 1. Nippon Nuclear Fuel Development Co., Ltd., Oarai, Ibaraki (Japan)
Description
Type 316L stainless steel was neutron irradiated (8x1025 n/m2, E>1MeV) and annealed at 673 K - 973 K for 1 hour. After the annealing, intergranular fracture ratio measurement by SSRT, grain boundary analysis by FE-TEM with EDS and simulation of grain boundary Cr depletion healing were performed in order to consider an effect of segregation healing on IASCC. The intergranular fracture ratio was healed to 0% by annealing above 723 K, but the healing of grain boundary Cr depletion of 723 K annealed specimen was not recognized by EDS analysis. Considering about the EDS analysis result and analysis probe diameter, concentration profiles were calculated. As a result, it was considered that grain boundary segregation which depleted to about 8 mass% by neutron irradiation, healed to about 12 mass% by annealing at 723 K, so that IASCC susceptibility was decreased. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of 2009 international congress on advances in nuclear power plants
- Imprint Pagination
- [2572 p.]
- Journal Page Range
- [8 p.]
- Report number
- INIS-JP--123
Conference
- Title
- 2009 international congress on advances in nuclear power plants
- Acronym
- ICAPP2009
- Dates
- 10-14 May 2009
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43084344
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; BWR TYPE REACTORS; CRACKS; GRAIN BOUNDARIES; ION MICROSCOPY; NEUTRONS; RADIATION EFFECTS; SEGREGATION; STAINLESS STEEL-316L; STRESS CORROSION
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BARYONS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION; CORROSION RESISTANT ALLOYS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAT TREATMENTS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MICROSCOPY; MICROSTRUCTURE; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NUCLEONS; POWER REACTORS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: FinalPaper, Paper ID: 9422.pdf; 14 refs., 12 figs., 1 tab.