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二神 敏; 久保 重信; Sofu, T.*
no journal, ,
我が国が主導して構築した系統別SDGについて、GIF-RSWGとして、IAEAによるレビューを受けて改訂した状況を報告する。
柴田 明裕*; 久保 重信
no journal, ,
日本のタンク型SFRの概念検討状況として、我が国が主導して構築したナトリウム冷却高速炉の安全設計クライテリア及び安全設計ガイドラインに適合する設計アプローチを報告する。
深野 義隆; 久保 重信
no journal, ,
In Japan, in order to realize the design, construction, and operation of the Joyo and the Monju, safety research for SFRs has been conducted, and the technical basis for the safety evaluation of SFRs has been developed. In order to understand the characteristics of the reactor core and cooling system unique to SFR and various phenomena during accidents, a set of numerical tools for safety analysis has been developed and applied to the safety evaluation of Joyo and Monju, and established the basis of the safety evaluation technology for SFRs including the plant dynamics analysis method, data on integrity and failure limits of fuel and reactor structure, sodium combustion analysis method, sodium-water reaction analysis method for water leak in steam generator, evaluation method for CDA and PRA. This paper describes the current status of experimental studies and development of numerical tools for SFRs in Japan and the future research plan.