TRAC-PF1/MOD2 code manual
- Los Alamos National Lab., NM (United States)
The Transient Reactor Analysis Code (TRAC) was developed to provide advanced best-estimate predictions of postulated accidents in light-water reactors. The TRACPFl/MOD2 program provides this capability for pressurized water reactors and for many thermal-hydraulic test facilities. The code features either a one- or a three-dimensional treatment of the pressure vessel and its associated internals, a two-fluid nonequilibrium hydrodynamics model with a noncondensable gas field and solute tracking, flow-regime-dependent constitutive equation treatment, optional reflood tracking capability for bottom-flood and falling-film quench fronts, and consistent treatment of entire accident sequences including the generation of consistent initial conditions. The stability-enhancing two-step numerical algorithm is used in both the one- and three-dimensional hydrodynamics and permits violation of the material Courant condition. This technique permits large time steps and, hence, reduced running time for slow transients. In addition to the components contained in previous TRAC versions, TRAC-PFl/MOD2 includes a heat-structure component that allows the user to accurately model complicated geometries. An improved reflood model based on mechanistic and defensible models has been added. The new code also contains improved constituative models and additions and refinements for several components. This guide describes the components and control systems used in TRAC and gives detailed information the user needs to prepare an input deck and carry out simulations using TRAC-PFl/MOD2.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7308522
- Report Number(s):
- NUREG/CR-5673-Vol.2; LA--12031-M-Vol.2; ON: TI92019222
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRAC-PF1/MOD2 code manual: Programmer's guide
TRAC-PF1/MOD2 code manual: Programmer`s guide. Volume 3
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
DOCUMENT TYPES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MANUALS
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS