TRAC independent assessment for PWR analysis

LANL is developing the Transient Reactor Analysis Code (TRAC) for application to PWRs. Goal was to analyze large-break loss-of-coolant accidents (LOCAs), and the TRAC-P1A and TRAC-PD2 codes primarily addressed the large-break LOCA. The TRAC-PF1 code contained modifications which enhanced the computational speed of the code and improved its application to small-break LOCAs. The TRAC-PF1/MOD1 code added improved steam-generator modeling, a turbine component, and a control system together with modified constitutive relations to model the balance of plant on the secondary side and to extend the applications to non-LOCA transients. During the past year we assessed TRAC-PD2, TRAC-PF1, and TRAC-PF1/MOD1, using LOFT and Semiscale experiments