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Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTRÉE
Volume 142 · Number 3 · June 2003 · Pages 205-229
Technical Paper · Fission Reactors
Akitoshi Hotta, Takafumi Anegawa, Takashi Hara, Hisashi Ninokata
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The three-dimensional plant simulator TRAC/BF1-ENTRÉE was validated based on a one-pump trip test. Trends in major plant process parameters and three-dimensional power distributions were studied with regard to in-core flow reduction, insertion of control blades, and neutron spectrum mismatch. An improved moderator direct heating model was proposed by separately modeling the neutron slowing down and the gamma-ray absorption mechanism. The delayed heat conduction caused by the gamma heating in metallic regions was implemented. Sensitivities of water level and three-dimensional power were studied by varying the core power history, the dryer loss coefficient, and the neutron kinetics solution approach.
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