TRAC-BD1-Transient Reactor Analysis Code for Boiling Water Systems

The Boiling Water Reactor (BWR) version of the Transient Reactor Analysis Code (TRAC) is being developed at the Idaho National Engineering Laboratory (INEL) to provide an advanced best-estimate predictive capability for the analysis of postulated accidents in BWRs. The TRAC-BD1 program provides the loss-of-coolant accident (LOCA) analysis capability for BWRs and for many BWR related thermal hydraulic experimental facilities. This code features a three-dimensional treatment of the BWR pressure vessel; a detailed model of a BWR fuel bundle including multirod, multibundle, radiation heat transfer, leakage path modeling capability, flow-regime-dependent constitutive equation treatment, reflood tracking capability for both falling films, and bottom flood quench fronts, and consistent treatment of the entire accident sequence. The BWR component models in TRAC-BDI will be described and comparisons with data presented. Application of the code to a BWR6 LOCA is also presented