| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 296676 | Nuclear Engineering and Design | 2013 | 7 Pages |
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.
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Authors
Kenichiro Nozaki, Akithoshi Hotta, Sinya Kosaka, Shoichi Suehiro, Daisuke Fujiwara, Sinya Mizokami,