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Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTRÉE

Akitoshi Hotta, Takafumi Anegawa, Takashi Hara, Hisashi Ninokata

Nuclear Technology / Volume 142 / Number 3 / June 2003 / Pages 205-229

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT03-A3384

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.