Title of article :
Simulation of boiling water reactor one-pump trip transient by SIMULATE-3K
Author/Authors :
Nozaki، نويسنده , , Kenichiro and Hotta، نويسنده , , Akithoshi and Kosaka، نويسنده , , Sinya and Suehiro، نويسنده , , Shoichi and Fujiwara، نويسنده , , Daisuke and Mizokami، نويسنده , , Sinya، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2013
Pages :
7
From page :
146
To page :
152
Abstract :
To validate models relevant to the transitional in-core 3-D power behavior, the 3-D core kinetics code SIMULATE-3K was applied to an analysis of one-pump trip test performed in a BWR-5 plant which includes large distortion of the power distribution due to the local insertion of control rods. The core boundary conditions required by SIMULATE-3K were calculated by the plant system analysis code RETRAN-3D. It was found that the transitional APRM signal and LPRM signals calculated by SIMULATE-3K agreed well with the measured data. The results showed that the transitional in-core 3-D power behavior can be appropriately predicted by SIMULATE-3K.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2013
Journal title :
Nuclear Engineering and Design Eslah
Record number :
1593590
Link To Document :
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