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※ 半角英数字
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核燃料施設性能目標策定にかかわる技術的基盤の検討

Review of technical basis for formulating performance goals for nuclear fuel facilities

安全研究委員会核燃料施設性能目標調査専門部会

Subcommittee of Research on Performance Goals for Nuclear Fuel Facilities

我が国では、核燃料施設に関しても確率論的安全評価(PSA)手法の整備,PSAの実施,運転・保守でのリスク情報活用の試行が積極的に進められている。しかし、リスク情報活用における判断の根拠となる具体的で定量的な基準にかかわる検討はほとんど行われていない。このような状況を踏まえ、日本原子力研究開発機構安全研究センターでは、安全研究委員会の下に核燃料施設性能目標調査専門部会を組織し、核燃料施設の定量的なリスク情報に基づく判断基準等の諸外国の現状を調査し、我が国での性能目標案策定参考となる情報を整理するとともに、基本的な考え方の検討を行った。本報告書は、平成20年度及び21年度での同専門部会で調査,検討した内容をとりまとめ、核燃料施設での性能目標策定手順を提言した。

A lot of efforts have been made recently for researches on development of PSA methodology, its applications, and trials of risk-informed operation and maintenance in nuclear fuel facilities in Japan. Quantitative performance criteria consistent with nuclear safety goals, which is essential for risk-informed decision making, however, have not been discussed yet for those nuclear installations. A subcommittee under the Nuclear Safety Research Committee has been organized by Nuclear Safety Research Center of Japan Atomic Energy Agency to prepare the technical basis and a typical procedure to derive the quantitative performance goals for further discussions by the regulatory bodies to establish the objectives. The activities in 2008 and 2009 fiscal year have been summarized and the procedure to formulate performance goals is proposed in this report carried out by the subcommittee of research on performance goals for nuclear fuel facilities.

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