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Material Transport Analysis for Accident-Induced Flow in Nuclear Facilities (NUREG/CR-3527)
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Publication Information
Manuscript submitted: September 1983
Date published: October 1983
Prepared for Division of Risk Analysis
Office of Nuclear Regulatory Research
US Nuclear Regulatory Commission
Washington, DC 20555
NRC FIN No. A7029
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Abstract
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 facilities
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.
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