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Title: Methodology, status, and plans for development and assessment of the TRAC code

Abstract

The Transient Reactor Analysis Code (TRAC) is a state-of-the-art, best-estimate, transient system analysis computer code for analyzing geometrically complex multidimensional thermal hydraulic systems, primarily nuclear reactor power plants. TRAC is used by government and industry organizations for design and safety analysis, phenomenological studies, operational transient analysis, evaluating emergency operating procedures, simulator support and operator training, and for assessment of data involving basic experiments, separate effects tests, and plant operations. TRAC will calculate one- and three-dimensional (rectilinear and cylindrical coordinates) fluid flow involving gas, liquid, and mixture states. Although TRAC has many capabilities, it also has limitations. Some limitations arise from its implementation, dating from the 1970s. Rapid advances in hardware and software engineering highlight TRAC`s inefficiencies; however, other limitations relate to the level of scientific knowledge regarding two-phase flow physics. These limitations will continue until such time as the fundamental understanding of two-phase flows is extended. Presently, several development activities are either in progress or soon to begin that will fundamentally improve TRAC. Foremost among these are reimplementation of the current TRAC data structures in Fortran 90 and the integrated development of closure packages for large-break loss-of-coolant accident applications.

Authors:
; ;
Publication Date:
Research Org.:
Los Alamos National Lab., NM (United States)
Sponsoring Org.:
Nuclear Regulatory Commission, Washington, DC (United States); USDOE, Washington, DC (United States)
OSTI Identifier:
434475
Report Number(s):
LA-UR-96-2090; CONF-961192-2
ON: DE96014044; TRN: 98:008258
DOE Contract Number:  
W-7405-ENG-36
Resource Type:
Conference
Resource Relation:
Conference: Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements, Annapolis, MD (United States), 5-8 Nov 1996; Other Information: PBD: 1996
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; 99 MATHEMATICS, COMPUTERS, INFORMATION SCIENCE, MANAGEMENT, LAW, MISCELLANEOUS; TRANSIENTS; T CODES; PWR TYPE REACTORS; SYSTEMS ANALYSIS; HEAT TRANSFER; HYDRAULICS; NUCLEAR POWER PLANTS; LOSS OF COOLANT

Citation Formats

Boyack, B.E., Nelson, R.A., and Jolly-Woodruff, S. Methodology, status, and plans for development and assessment of the TRAC code. United States: N. p., 1996. Web.
Boyack, B.E., Nelson, R.A., & Jolly-Woodruff, S. Methodology, status, and plans for development and assessment of the TRAC code. United States.
Boyack, B.E., Nelson, R.A., and Jolly-Woodruff, S. Tue . "Methodology, status, and plans for development and assessment of the TRAC code". United States. doi:. https://www.osti.gov/servlets/purl/434475.
@article{osti_434475,
title = {Methodology, status, and plans for development and assessment of the TRAC code},
author = {Boyack, B.E. and Nelson, R.A. and Jolly-Woodruff, S.},
abstractNote = {The Transient Reactor Analysis Code (TRAC) is a state-of-the-art, best-estimate, transient system analysis computer code for analyzing geometrically complex multidimensional thermal hydraulic systems, primarily nuclear reactor power plants. TRAC is used by government and industry organizations for design and safety analysis, phenomenological studies, operational transient analysis, evaluating emergency operating procedures, simulator support and operator training, and for assessment of data involving basic experiments, separate effects tests, and plant operations. TRAC will calculate one- and three-dimensional (rectilinear and cylindrical coordinates) fluid flow involving gas, liquid, and mixture states. Although TRAC has many capabilities, it also has limitations. Some limitations arise from its implementation, dating from the 1970s. Rapid advances in hardware and software engineering highlight TRAC`s inefficiencies; however, other limitations relate to the level of scientific knowledge regarding two-phase flow physics. These limitations will continue until such time as the fundamental understanding of two-phase flows is extended. Presently, several development activities are either in progress or soon to begin that will fundamentally improve TRAC. Foremost among these are reimplementation of the current TRAC data structures in Fortran 90 and the integrated development of closure packages for large-break loss-of-coolant accident applications.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Dec 31 00:00:00 EST 1996},
month = {Tue Dec 31 00:00:00 EST 1996}
}

Conference:
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