In a previous study, we proposed an evaluation method of seismic buckling probability of a reactor vessel considering seismic hazard and showed seismic load had the most significant impact on buckling probability among the random variables considered in the evaluation. It means that more rational design of vessels can be realized by taking account of seismic load variation. The load and resistant factor design (LRFD) method enables us to determine design factors corresponding to target reliability by considering variations of random variables and it is used widely in civil engineering. Therefore, in this study, we have developed a draft code case of the rule for preventing buckling of vessels in JSME fast reactor codes based on LRFD. The equation in the draft code case is almost the same as the original but every random variables, seismic load and yield stress, have their own design factors. In addition, mean or median values are used for evaluation instead of design values including conservativeness. This is the first attempt to develop a code case based on reliability evaluation and is expected to lead further implementation of reliability evaluation into JSME fast reactor codes.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5002-2
PROCEEDINGS PAPER
Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD
Shigeru Takaya,
Shigeru Takaya
Japan Atomic Energy Agency, O-arai, Japan
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Tai Asayama,
Tai Asayama
Japan Atomic Energy Agency, O-arai, Japan
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Yoshio Kamishima
Yoshio Kamishima
Mitsubishi FBR Systems, Inc, Tokyo, Japan
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Shigeru Takaya
Japan Atomic Energy Agency, O-arai, Japan
Naoto Sasaki
ASCEND Co. Ltd, O-arai, Japan
Tai Asayama
Japan Atomic Energy Agency, O-arai, Japan
Yoshio Kamishima
Mitsubishi FBR Systems, Inc, Tokyo, Japan
Paper No:
ICONE24-60964, V002T08A010; 10 pages
Published Online:
October 25, 2016
Citation
Takaya, S, Sasaki, N, Asayama, T, & Kamishima, Y. "Implementation of Reliability Evaluation Into JSME Fast Reactor Codes: 2 — Development of a Code Case for Seismic Buckling Evaluation Based on LRFD." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T08A010. ASME. https://doi.org/10.1115/ICONE24-60964
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