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Title: ART-04--A MODIFICATION OF THE ART PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM-704

Abstract

Several recent modifications of the ART program for the study of the behavior of a nuclear reactor during various thermal transients are described. The program requires a 32,000-word IBM-704 computer with six tape units. The major modifications are provision for a slip flow model and for void reactivity contribution. (auth)

Authors:
;
Publication Date:
Research Org.:
Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
OSTI Identifier:
4135755
Report Number(s):
WAPD-TM-202
NSA Number:
NSA-14-025018
DOE Contract Number:
AT-11-1-GEN-14
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-60
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; COMPUTERS; PROGRAMMING; REACTIVITY; REACTORS; RECORDING SYSTEMS; THERMODYNAMICS; TRANSIENTS; VARIATIONS; ZONES

Citation Formats

Meyer, J.E., and Peterson, W.D. ART-04--A MODIFICATION OF THE ART PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM-704. United States: N. p., 1960. Web. doi:10.2172/4135755.
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Meyer, J.E., & Peterson, W.D. ART-04--A MODIFICATION OF THE ART PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM-704. United States. doi:10.2172/4135755.
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Meyer, J.E., and Peterson, W.D. Fri . "ART-04--A MODIFICATION OF THE ART PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM-704". United States. doi:10.2172/4135755. https://www.osti.gov/servlets/purl/4135755.
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@article{osti_4135755,
title = {ART-04--A MODIFICATION OF THE ART PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM-704},
author = {Meyer, J.E. and Peterson, W.D.},
abstractNote = {Several recent modifications of the ART program for the study of the behavior of a nuclear reactor during various thermal transients are described. The program requires a 32,000-word IBM-704 computer with six tape units. The major modifications are provision for a slip flow model and for void reactivity contribution. (auth)},
doi = {10.2172/4135755},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jul 01 00:00:00 EDT 1960},
month = {Fri Jul 01 00:00:00 EDT 1960}
}
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Technical Report:
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DOI:  10.2172/4135755
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    A description is given of a program by which the behavior of a nuclear reactor during various thermal transients may be studied. The program is written for a 32,000-word IBM-704 computer with six tape units. It is designed to predict the behavior of a water-cooled and moderated reactor with flat plate fuel elements during transients which are slower than a prompt excursion and during which the reactor flow. inlet temperature, and control rod motion may be specified as a function of time. (auth)

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