Analysis of Leak Propagation for Dblselections of MONJU Steam Generators

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

PNC TN943 81-02, 25 Pages, 1981/01

PNC-TN943-81-02.pdf:0.59MB

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.