Home / Publications / Journals / Nuclear Technology / Volume 61 / Number 2
Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 276-295
Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33197
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A boiling water reactor system model for the Browns Ferry Nuclear Plant has been developed to predict reactor behavior during postulated transients and accidents. The model is based on the RETRAN-02 computer program and includes one-dimensional neutron kinetics capabilities. The model can be applied to a wide range of transients but is primarily intended for analyses of the limiting pressurization transients considered for reload core licensing. The model is qualified by comparisons to a number of startup test transients performed at Browns Ferry and to special turbine trip tests conducted at Peach Bottom.