Effect of Microstructure on Failure Behavior of Light Water Reactor Coolant Piping under Severe Accident Conditions
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概要
- 論文の詳細を見る
In a severe accident of light water reactors, the reactor coolant system (RCS) piping might be subjected to thermal loads caused by the decay heat of the deposited fission products and the heat transfer from the hot gases, with an internal pressure in some accident sequences. Tests on the RCS piping failure were performed along with high temperature tensile and creep rupture tests including metallography to investigate the failure behavior. The prediction of the 0.2% proof stress by Arrhenius equation is in good agreement with the measured stress above 800°C for served RCS piping materials. The modified Nortons Law for the short term creep rupture model agrees with the experimental values between 800 and 1, 150°C for type 316 stainless steel. The microstructural change was discussed with the effect of the very rapid formation and resolution of the precipitation on the strength at high temperature. The result of the piping failure tests which simulated the severe accident conditions, i.e., in short-term at high-temperature, could support the plastic limit load prediction of the flow stress model using the 0.2% proof stress.
- 社団法人 日本原子力学会の論文
- 1999-10-25
著者
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Hidaka A
Japan Atomic Energy Res. Inst. Ibaraki
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Hidaka Akihide
Department Of Reactor Safety Research Japan Atomic Energy Researth Institute
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Maruyama Y
Japan Atomic Energy Res. Inst. Ibaraki
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Maruyama Yu
Department Of Plastic And Reconstructive Surgery Toho University Hospital
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Maruyama Yu
Department Of Orthodontics And Dentofacial Orthopedics Graduate School Of Dentistry Osaka University
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SUGIMOTO Jun
Department of Molecular Biology, Ryukyu University School of Medicine
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Kudo T
Clariant Corp. Nj Usa
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HARADA Yuhei
Department of Reactor Safety Research, Japan Atomic Energy Researth Institute
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MAEDA Akio
Department of Reactor Safety Research, Japan Atomic Energy Researth Institute
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SHIBAZAKI Hiroaki
Department of Reactor Safety Research, Japan Atomic Energy Researth Institute
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KUDO Tamotsu
Department of Reactor Safety Research, Japan Atomic Energy Researth Institute
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HASHIMOTO Kazuichiro
Department of Reactor Safety Research, Japan Atomic Energy Researth Institute
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Kudo Tamotsu
Department Of Reactor Safety Research Japan Atomic Energy Researth Institute
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Maeda Akio
Department Of Reactor Safety Research Japan Atomic Energy Researth Institute
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Harada Yuhei
Department Of Reactor Safety Research Japan Atomic Energy Researth Institute
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Sugimoto J
Japan Atomic Energy Res. Inst.
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Sugimoto Jun
Department Of Chemistry School Of Science Kitasato University
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Shibazaki Hiroaki
Department Of Reactor Safety Research Japan Atomic Energy Researth Institute
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Maeda Akio
Department Of Biophysics Graduate School Of Science Kyoto University
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Hashimoto K
Interdisciplinary Graduate School Of Science And Engineering Kinki University
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Hashimoto Kengo
Interdisciplinary Graduate School Of Science And Engineering Kinki University
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