Conference Proceedings Paper
Simulation of Boiling Water Reactor One-Pump Trip Transient by SIMULATE-3K
NURETH-14 - 2011 September 25-30
Kenichiro Nozaki (TEPCO Systems)
Akitoshi Hotta (TEPCO Systems)
Shinya Kosaka (TEPCO Systems)
Shoichi Suehiro (TEPCO Systems)
Daisuke Fujiwara (TEPCO Systems)
Shinya Mizokami (Tokyo Electric Power Company, Inc.)
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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