Material transport analysis for accident-induced flow in nuclear facilities

Technical Report · Sat Oct 01 04:00:00 EDT 1983

DOI:https://doi.org/10.2172/5405574· OSTI ID:5405574

Martin, R A; Tang, P K; Harper, A P; Novat, J D; Gregory, W S

This report is a summary of the material transport modeling procedures developed to support a family of accident analysis computer codes. The material transport modeling areas include transport initiation, convection, interaction, depletion, and filtration. Except for material interaction, these areas are developed in modular form in three Los Alamos National Laboratory computer codes: TORAC, EXPAC, and FIRAC. This family of codes was developed to provide improved methods of tornado, explosion, and fire accident consequence assessment, respectively, for the nuclear industry. Although the codes were designed to estimate accident-induced gas-dynamic, thermal, and material transport transient phenomena in nuclear fuel cycle facility ventilation systems, they are applicable to other faciliites as well. Sample problems using TORAC have been provided to illustrate the current material transport capabilities for a simple system under tornado-induced accident conditions. Some suggestions for future improvements to some of these material transport models also are discussed.

• Research Organization: Los Alamos National Lab., NM (USA)
• Sponsoring Organization: US NRC
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5405574
• Report Number(s): NUREG/CR-3527; LA-9913-MS; ON: DE84004260
• Country of Publication: United States
• Language: English

Related Subjects

050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
NUCLEAR FACILITIES
RADIOACTIVITY TRANSPORT
RISK ASSESSMENT