Title of article :
Assessment of the COBRA/RELAP5 code using the LOFT L2-3 large-break loss-of-coolant experiment
Author/Authors :
Jeong، نويسنده , , J.-J.; Sim، نويسنده , , S. K.; Ban، نويسنده , , C. H.; Park، نويسنده , , C. E، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1997
Pages :
12
From page :
1171
To page :
1182
Abstract :
The COBRA/RELAP5 code, a merged version of COBRA-TF and RELAPS/MOD3 SmS, was upgraded with RELAP5/MOD3.2. Using the "inter-process communication" technique, the realistic three-dimensional reactor vessel module of CIBRA-TF was linked with the RELAPS code in the merged code. The three-dimensional capability of COBRA/RELAPS was assessed using the LOFT L2-3 large-break loss-of-coolant accident (LOCA) experimental data. The evaluate the overall performance of the code, relatively fine three-dimensional meshes were used for the reactor vessel, which was simulated by CIBRA-TF, and the other systems were one-dimensionally modeled by RELAP5/MOD3.2. The simulation results showed that COBRA/ RELAPS is a promising tool for analysis of complicated, multidimensional, two-phase flow transients in pressurized water reactors (PWRS).
Journal title :
Annals of Nuclear Energy
Serial Year :
1997
Journal title :
Annals of Nuclear Energy
Record number :
405158
Link To Document :
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