Research of estimation method of thermal aging embrittlement on cast austenitic stainless steel
Creators
- 1. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tsuruga, Fukui (Japan)
Description
Thermal embrittlement of cast austenitic stainless steel components from the decommissioned advanced thermal prototype reactor Fugen has been characterized. Cast stainless steel materials were obtained from recirculation pump casing. The actual time at temperature for the materials was 138,000 h at 275degC. The 'Fugen' material show modest decrease in Charpy-impact properties and a small increase in micro-Vickers hardness in ferrite phase because of thermal aging at relatively low service temperatures. The fracture toughness prediction method (H3T model) predicts slightly lower values for Charpy-impact energy obtained from the Fugen material. The results from microstructural analysis suggest that the prediction method have the potential to provide higher accuracy by considerations of the activation energy for embrittlement at low service temperatures. (author)
Additional details
Additional titles
- Original title (Japanese)
- Nippon hozen gakkai dai-10-kai gakujutsu koenkai yoshishu
Publishing Information
- Imprint Title
- Proceedings of the 10th annual meeting of Japan Society of Maintenology
- Imprint Pagination
- 750 p.
- Journal Page Range
- p. 488-492
Conference
- Title
- 10. annual meeting of Japan Society of Maintenology
- Dates
- 24-26 Jul 2013
- Place
- Suita, Osaka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 46089821
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACTIVATION ENERGY; AGING; AUSTENITIC STEELS; CASTING; CHARPY TEST; EMBRITTLEMENT; FRACTURE PROPERTIES; JATR REACTOR; PREDICTION EQUATIONS; STAINLESS STEELS
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; DESTRUCTIVE TESTING; ENERGY; EQUATIONS; FABRICATION; HEAVY WATER MODERATED REACTORS; HIGH ALLOY STEELS; HWLWR TYPE REACTORS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; NATURAL URANIUM REACTORS; PLUTONIUM REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; STEELS; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS
Optional Information
- Notes
- 11 refs., 6 figs., 1 tab. Imprint:Nippon hozen gakkai dai-10-kai gakujutsu koenkai yoshishu