This paper describes the material strength standard of 316FR stainless steel in the design code for fast reactors of 2012 edition published by the Japan Society of Mechanical Engineers. 316FR stainless steel is to be used for a reactor vessel and internals for the Japan Sodium Cooled Fast Reactor (JSFR). 316FR was developed in Japan by optimizing chemical composition within the specifications of SUS316 in the Japanese Industrial Standard which is equivalent to Type 316 stainless steel. The optimization was performed from the viewpoint of maximizing the creep resistance under fast breeder conditions. Application of 316FR stainless steel to JSFR needs the material strength standard. Therefore, the authors developed the material strength standard. The material strength standard involved allowable limits such as S0, Sm, Su, Sy, SR and St and so on, environment effects such as irradiation effects and sodium effects. In addition, material characteristic equations (Creep rupture equation, creep strain equation and equation of best fit curve for low-cycle fatigue life and so on) necessary for the allowable limits were involved. This paper describes the contents of the material strength standard.
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ASME 2013 Pressure Vessels and Piping Conference
July 14–18, 2013
Paris, France
Conference Sponsors:
- Pressure Vessels and Piping Division
- Nondestructive Evaluation Engineering Division
ISBN:
978-0-7918-5564-5
PROCEEDINGS PAPER
Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel
Takashi Onizawa,
Takashi Onizawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Yuji Nagae,
Yuji Nagae
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Shigeru Takaya,
Shigeru Takaya
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Tai Asayama
Tai Asayama
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
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Takashi Onizawa
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Yuji Nagae
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Shigeru Takaya
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Tai Asayama
Japan Atomic Energy Agency, Oarai, Ibaraki, Japan
Paper No:
PVP2013-97608, V01BT01A034; 8 pages
Published Online:
January 17, 2014
Citation
Onizawa, T, Nagae, Y, Takaya, S, & Asayama, T. "Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel." Proceedings of the ASME 2013 Pressure Vessels and Piping Conference. Volume 1B: Codes and Standards. Paris, France. July 14–18, 2013. V01BT01A034. ASME. https://doi.org/10.1115/PVP2013-97608
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