TRAC (Transient Reactor Analysis Code)-PF1/MOD1 Developmental Assessment.

摘要

The Transient Reactor Analysis Code (TRAC) is being developed at Los Alamos National Laboratory to provide advanced best-estimate predictions of postulated accidents in light-water reactors. The TRAC-PF1/MOD1 program provides this capability for pressurized water reactors and for many thermal-hydraulic experimental facilities. The code features either a one- or three-dimensional treatment of the pressure vessel and its associated internals; a two-phase, two-fluid, nonequilibrium hydrodynamics model with a noncondensable gas field; flow-regime-dependent constitutive equation treatment; optional reflood-tracking capability for both bottom flood and falling-film quench fronts; and consistent treatment of entire accident sequences from normal operating conditions through severe transients. A new numerical algorithm is used in the one-dimensional hydrodynamics that permits this portion of the fluid dynamics to violate the material Courant condition. The assessment set consists of six integral effects calculations in the Loss-of-Fluid test and Semiscale facilities.