GASFLOW: The theoretical model to analyze accidents in nuclear containments, confinements, and facility buildings

Conference · Sat May 01 00:00:00 EDT 1993

OSTI ID:10158833

Travis, J R ^[1]; Wilson, T L ^[2]

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

This report documents the governing physical equations for GASFLOW, a finite-volume computer code for solving transient, three-dimensional, compressible, Navier-Stokes equations for multiple gas species. The code is designed to be a best-estimate tool for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments, confinements, and other facility buildings. An analysis with GASFLOW will result in time-dependent gas-species concentrations throughout the structure analyzed, and in the event of combustion the pressure and temperature loadings on the walls and internal structures. GASFLOW can model geometrically complex containment systems with multiple compartments and internal structures. It can calculate gas behavior of low-speed buoyancy-driven flows, of diffusion-dominated flows, and during deflagrations. The code can model condensation heat transfer to walls and internal structures by natural and forced convection; chemical kinetics of combustion of hydrogen or hydrocarbons fuels; and fluid turbulence. Heat conduction within walls and structures is considered one-dimensional.

• Research Organization: Los Alamos National Lab., NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 10158833
• Report Number(s): LA-UR-93-1183; CONF-930651-2; N-6-93-R115; ON: DE93012625
• Resource Relation: Conference: 4. international conference on simulation methods in nuclear engineering,Montreal (Canada),2-4 Jun 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
WATER MODERATED REACTORS
REACTOR ACCIDENTS
CONTAINMENT SYSTEMS
G CODES
REACTOR VESSELS
MATHEMATICAL MODELS
COMPUTER CALCULATIONS
TRANSIENTS
NAVIER-STOKES EQUATIONS
GAS FLOW
HYDRAULICS
COMBUSTION
220900
210100
210200
990200
REACTOR SAFETY
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
MATHEMATICS AND COMPUTERS