This paper describes the formulation of material characteristics of austenitic stainless steels at extremely high temperature which meets in some kinds of severe accidents of nuclear power plants. After the severe accident in Fukushima dai-ichi nuclear power plants, it has been supposed to be very important not only to prevent the occurrence of abnormal conditions, i.e. from the first to the third layer safety, but also to prevent the expansion of the accident conditions, i.e. the fourth layer safety[1] [2]. In order to evaluate the structural integrity under the severe accident condition, material characteristics which can be used in the numerical analyses, such as finite element analysis, were required [3] [4]. However, there were no material characteristics applicable to the structural integrity assessment at extremely high temperature. Therefore, a series of tensile and creep tests was performed for austenitic stainless at extremely high temperature which meets in some kinds of severe accidents of nuclear power plants, namely up to 1000 °C. Based on the acquired data from the tests, monotonic stress-strain equation and creep rupture equation applicable to the structural analysis at extremely high temperature, up to 1000 °C were formulated. As a result, these formulae make it possible to conduct the structural integrity assessment using numerical analysis techniques, such as finite element method.
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ASME 2017 Pressure Vessels and Piping Conference
July 16–20, 2017
Waikoloa, Hawaii, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5795-3
PROCEEDINGS PAPER
The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature
Kenta Shimomura,
Kenta Shimomura
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Takashi Onizawa,
Takashi Onizawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Shoichi Kato,
Shoichi Kato
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Masanori Ando,
Masanori Ando
Japan Atomic Energy Agency, Tsuruga, Fukui, Japan
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Takashi Wakai
Takashi Wakai
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Kenta Shimomura
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Takashi Onizawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Shoichi Kato
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Masanori Ando
Japan Atomic Energy Agency, Tsuruga, Fukui, Japan
Takashi Wakai
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Paper No:
PVP2017-65666, V03BT03A006; 9 pages
Published Online:
October 26, 2017
Citation
Shimomura, K, Onizawa, T, Kato, S, Ando, M, & Wakai, T. "The Formulation of Material Characteristics of Austenitic Stainless Steels at Extremely High Temperature." Proceedings of the ASME 2017 Pressure Vessels and Piping Conference. Volume 3B: Design and Analysis. Waikoloa, Hawaii, USA. July 16–20, 2017. V03BT03A006. ASME. https://doi.org/10.1115/PVP2017-65666
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