ART--A PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM- 704
Open Access
- 1 November 1959
- report
- Published by Office of Scientific and Technical Information (OSTI)
Abstract
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)Keywords
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