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Development of level-1 PSA method applicable to Japan Sodium-cooled Fast Reactor

ナトリウム冷却高速炉のためのレベル1PSA手法の開発

栗坂 健一; 堺 公明; 山野 秀将; 藤田 聡*; 皆川 佳祐*; 山口 彰*; 高田 孝*

Kurisaka, Kenichi; Sakai, Takaaki; Yamano, Hidemasa; Fujita, Satoshi*; Minagawa, Keisuke*; Yamaguchi, Akira*; Takata, Takashi*

本論文は、ナトリウム冷却型高速炉JSFRに適用可能なレベル1PSA手法の開発について記述する。本研究は、(1)内的事象について受動的安全特性、(2)外的事象(地震)について高速炉用免震システムの新評価手法の開発を目標としている。内的事象評価に関して、原子炉停止失敗による炉心損傷の頻度の評価を実施し、受動的原子炉停止の失敗をイベントツリーモデルにて考慮した。高速炉特有の機器故障率を既存の高速炉の運転経験をもとにプラント間のばらつきを考慮できる階層ベイズ法を適用して評価した。不確実さ解析の結果、主炉停止系と後備炉停止系間での確率パラメータの相関性についての想定が炉心損傷頻度の平均値へ感度を有することがわかった。地震については、免震システムの地震応答解析と感度解析を実施した。その結果、積層ゴムの非線形性が建物と内部機器の応答へ影響することを確認した。

This paper describes a study to develop the level-1 probabilistic safety assessment (PSA) method that is applicable to the Japan Sodium-cooled Fast Reactor (JSFR). This study aims to provide a new evaluation method of (1) passive safety architectures related to internal events and (2) an advanced seismic isolation system related to a seismic event as a representative external event in Japan. Regarding the internal events evaluation, a quantitative analysis on the frequency of the core damage caused by reactor shutdown failure was conducted. A failure in passive reactor shutdown was taken into account in the event tree model. The failure rate of sodium-cooled fast reactor (SFR) specific components was evaluated based on the operating experience in existing SFRs by applying the Hierarchical Bayesian Method, which can consider a plant-to-plant variability. By conducting an uncertainty analysis, it was found that the assumption about the correlation of the probability parameters between the main and backup reactor shutdown systems is sensitive to the mean value of the frequency of the core damage caused by reactor shutdown failure. As for the seismic event evaluation, seismic response analysis and sensitivity analysis of a seismic isolation system were carried out. As a result, it was confirmed that nonlinear properties of rubber bearings have influence on response of the building and inner equipment.

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パーセンタイル:51.32

分野:Nuclear Science & Technology

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