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Containment response analysis in TRAC-BD1/MOD1. [BWR]
D.D. Taylor, M. M. Giles, W.L. Weaver
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Abstract
The Boiling Water Reactor (BWR) version of the Transient Reactor Analysis Code (TRAC) is under development at the Idaho National Engineering Laboratory (INEL) to provide an advanced best-estimate predictive capability for the analysis of postulated accidents in BWR's. The code now incorporates a containment thermodynamic response option whereby time-dependent fluid temperatures and pressures in the containment are estimated in order to supply boundary conditions for the primary cooling loop calculation. Implementation and details of the containment model are described. Comparisons of the TRAC predictions of containment fluid temperature and pressure response with data from three blowdown test facilities are presented.