In this study, we develop new indices that evaluate the response capability — response margin and response reliability — of a nuclear power plant in case of occurrence of a severe accident by considering the ability of the nuclear power plant to recover system safety functions, which may have been affected by the accident, to the minimum safety values. Further, we demonstrate a specific evaluation procedure for our proposed indices. While performing the evaluation, we consider margins with respect to a minimum safety function level and a time constraint along with their temporal changes. Additionally, for a simplified fast reactor (FR) plant model, we conduct a trial assessment of the recovery capacity of the system to ensure system safety based on the concept of new indices. Further, the applicability of the response reliability evaluation method to FR plants is discussed based on the viewpoints of reflecting the characteristics of each reactor type.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5146-3
PROCEEDINGS PAPER
Evaluation Method of Response Reliability During an Accident and its Applicability to Fast Reactor Plants
Masaaki Suzuki,
Masaaki Suzuki
Tokyo University of Science, Noda, Japan
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Kazuyuki Demachi,
Kazuyuki Demachi
University of Tokyo, Tokyo, Japan
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Shigeru Takaya,
Shigeru Takaya
Japan Atomic Energy Agency, O-arai, Japan
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Yoshitaka Chikazawa
Yoshitaka Chikazawa
Japan Atomic Energy Agency, O-arai, Japan
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Masaaki Suzuki
Tokyo University of Science, Noda, Japan
Kazuyuki Demachi
University of Tokyo, Tokyo, Japan
Shigeru Takaya
Japan Atomic Energy Agency, O-arai, Japan
Yoshitaka Chikazawa
Japan Atomic Energy Agency, O-arai, Japan
Paper No:
ICONE26-82567, V004T06A046; 8 pages
Published Online:
October 24, 2018
Citation
Suzuki, M, Demachi, K, Takaya, S, & Chikazawa, Y. "Evaluation Method of Response Reliability During an Accident and its Applicability to Fast Reactor Plants." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation. London, England. July 22–26, 2018. V004T06A046. ASME. https://doi.org/10.1115/ICONE26-82567
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