American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 61 / Number 2

Qualification of a RETRAN-02 Model for Boiling Water Reactor Transient Analysis

Michael E. Garrett, Samuel L. Forkner, T. A. Keys, George W. Perry, M. Wesley Waddell, Jr.

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

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.