TRAC-PD2: advanced best-estimate computer program for pressurized water reactor loss-of-coolant accident analysis

Technical Report · Wed Apr 01 04:00:00 EST 1981

OSTI ID:5391880

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory to provide an advanced best-estimated predictive capability for the analysis of postulated accidents in light water reactors. The TRAC-PD2 program provides this analysis capability for pressurized water reactors and for many thermal-hydraulic experimental facilities. The code features a three-dimensional treatment of the pressure vessel and its associated internals, two-phase nonequilibrium hydrodynamics models, 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 manual 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 Scientific Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5391880
• Report Number(s): NUREG/CR-2054; LA-8709-MS; ON: TI85015981
• Country of Publication: United States
• Language: English

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ACCIDENTS
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DOCUMENT TYPES
LOSS OF COOLANT
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