並列タイトル等Analysis of Leak Propagation for Dblselections of MONJU Steam Generators
一般注記Analyses of leak propagation have been performed in order to support the selection of a design basis leak (DBL) for sodium-water reaction accidents in steam generators of the Japanese prototype fast breeder reactor, MONJU. For the purpose of estimating the possible maximum leak rate due to the failure propagation, a computer code, (LEAP) (Leak Enlargement and propagation), has been developed. This code analyzes the failure propagation process taking account of data from sodium-water reaction experiments throughout the world. This paper describes the model and structure of the LEAP code, a validation study, and results of the LEAP calculation for the MONJU steam generators and it has been concluded that the sodium-water reaction accidents can be terminated before the leak rate exceeds the DBL (one plus three DEG's) with the present detection system and safety devices.
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一次資料へのリンクURL/PNC-TN943-81-02.pdf (fulltext)
連携機関・データベース国立情報学研究所 : 学術機関リポジトリデータベース(IRDB)(機関リポジトリ)
提供元機関・データベース日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System