Failure propagation analysis of LMFBR steam generator tube; Analysis of SWAT-3 runs 14 and 15 by LEAP II code

*; Miyake, Osamu; Daigo, Yoshimichi; *

PNC TN941 82-100, 48 Pages, 1982/04

PNC-TN941-82-100.pdf:0.81MB

The Computer code LEAP II had been developed in order to analize failure propagation phenomena by the sodium-water reaction in the steam generator of LMFBR. Here reported is verification analysis of the LEAP code by using Runs 14 and 15 test results of Steam Generator Safety Test Facility (SWAT-3). The main results are as follows: (1)As the results of parametric survey, the effects of the significant parameters such as time mesh, jet division number, etc. to the code were understood. (2)In comparison with the test results of Runs 14 and 15 of SWAT-3, the LEAP code can estimate the phenomena conservatively enough.