我系在ANE发表论文Simulation and uncertainty analysis of main steam line break accident on an integral test facility
Ye Yang, Jun Yang, Chengcheng Deng, Mamoru Ishii
Annals of Nuclear Energy, Volume 144, 1 September 2020, 107565
Abstract
In order to investigate the performance of a Generation III BWR safety system, an Integral test facility was
designed and conducted, and several integral tests were performed. The best estimate safety analysis of Main Steam Line Break (MSLB) accident using RELAP5/MOD3.3 and RELAP/SCDAPSIM/MOD3.4 (from now on referred as RELAP/SCDAP3.4) was performed. By comparing the simulation results with the test results, the prediction capability of the RELAP5/MOD3.3 and the RELAP/SCDAP3.4 was compared and analyzed.
The RELAP/SCDAP3.4 code was selected to perform the uncertainty study. According to the Phenomenon Identification and Ranking Table, 12 input treatable parameters and 29 source code coefficients were selected with imposed uncertainty distribution to conduct uncertainty analysis. The 95/95 uncertainty band of the minimum core collapsed level were obtained and analyzed. In addition, the contribution weight of input treatable parameters and source code coefficients for the minimum core collapsed level were identified with the Spearman rank correlation coefficient.
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