TRAC-PF1: an advanced best-estimate computer program for pressurized water reactor analysis

Technical Report · Wed Feb 01 04:00:00 EST 1984

DOI:https://doi.org/10.2172/5120852· OSTI ID:5120852

Liles, D R; Mahaffy, J H

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory to provide advanced best-estimate predictions of postulated accidents in light water reactors. The TRAC-PF1 program provides this capability for pressurized water reactors and for many thermal-hydraulic experimental facilities. The code features either a one-dimensional or a 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 including the generation of consistent initial conditions. This report describes the thermal-hydraulic models and the numerical solution methods used in the code. Detailed programming and user information also are provided.

• Research Organization: Los Alamos National Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5120852
• Report Number(s): NUREG/CR-3567; LA-9944-MS; ON: DE84010538
• Country of Publication: United States
• Language: English

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