Analysis of Leak Propagation for Dblselections of MONJU Steam Generators

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H.Tanab*; Miyake, Osamu*; M.hori*; Y.Ohmor*; Daigo, Y.*; Sato, Minoru*; T.Takah*

H.Tanab*; Miyake, Osamu*; M.hori*; Y.Ohmor*; Daigo, Y.*; Sato, Minoru*; T.Takah*

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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.