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ART--A PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM- 704

Technical Report ·
DOI:https://doi.org/10.2172/4204418· OSTI ID:4204418
; ; ; ;

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)

Research Organization:
Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
DOE Contract Number:
AT(11-1)-GEN-14
NSA Number:
NSA-14-007090
OSTI ID:
4204418
Report Number(s):
WAPD-TM-156
Country of Publication:
United States
Language:
English

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Related Subjects

COMPUTERS
CONTROL ELEMENTS
EXCURSIONS
FUEL ELEMENTS
MATHEMATICS
MOTION
REACTOR TECHNOLOGY
REACTORS
TEMPERATURE
TRANSIENTS
WATER COOLANT
WATER MODERATOR