TRAC-PF1 [electronic resource] : an advanced best-estimate computer program for pressurized water reactor analysis
- Published
- Los Alamos, N.M. : Los Alamos National Laboratory, 1984.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 598 : digital, PDF file
- Additional Creators
- Los Alamos National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- 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.
- Report Numbers
- E 1.99:nureg/cr-3567
E 1.99: la-9944-ms
la-9944-ms
nureg/cr-3567 - Subject(s)
- Other Subject(s)
- Note
- Published through SciTech Connect.
02/01/1984.
"nureg/cr-3567"
" la-9944-ms"
"DE84010538"
Liles, D.R.; Mahaffy, J.H. - Funding Information
- W-7405-ENG-36
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