BWR (Boiling Water Reactor) Refill-Reflood Program Task 4.7 - Model Development Basic Models for the BWR Version of TRAC (Transient Reactor Analysis Code).

摘要

TRAC (Transient Reactor Analysis Code) is a computer code for best estimate analysis of the thermal hydraulic conditions in a reactor system. The constitutive correlations for shear and heat transfer developed for the Boiling Water Reactor (BWR) version of TRAC are described. A universal flow regime map has been developed to tie the regimes for shear and the heat transfer into a consistent package. New models in the areas of interfacial shear, interfacial heat transfer and thermalradiation have been introduced. Improvements have also been made to the constitutive correlations and the numerical methods. All the models have been implemented into the GE version TRACB02 and extensively tested against data.