TRAC-PF1/MOD2 code manual: Programmer's guide

Technical Report · Wed Jul 01 00:00:00 EDT 1992

OSTI ID:7239099

Guffee, L A ^[1]; Woodruff, S B; Steinke, R G; Spore, J W ^[2]

---

1. Science Applications International Corp., Albuquerque, NM (United States)
2. Los Alamos National Lab., NM (United States)

The Transient Reactor Analysis Code (TRAC) was developed to provide best-estimate predictions of postulated accidents of light-water reactors. The TRAC-PF1/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. This manual is the third volume of a four-volume set of documentation on TRAC-PF1/MOD2. This guide was developed to assist the TRAC programmer and contains information on the TRAC code and data structure, the TRAC calculational sequence, memory management, and various machine configurations supported by TRAC.

• 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: 7239099
• Report Number(s): NUREG/CR-5673-Vol.3; LA--12031-M-Vol.3; ON: TI92018594
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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 ARCHITECTURE
COMPUTER CODES
DOCUMENT TYPES
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MANUALS
MECHANICS
POWER REACTORS
PROGRAMMING
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
T CODES
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS