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U.S. Department of Energy
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SIMULATION OF PROMPT-CRITICAL EXCURSIONS IN WATER-MODERATED REACTORS

Technical Report ·
OSTI ID:4142285

A methed for calculating the behavior of water-cooled reactors during prompt-critical excursions by means of an analog computer was developed. Results were obtained for a plate type zirconium clad core and for the SPERT I core. The results of the SPERT analysis were in goed agreement with the experimental data. (auth)

Research Organization:
Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
DOE Contract Number:
AT(11-1)-GEN-14
NSA Number:
NSA-15-003622
OSTI ID:
4142285
Report Number(s):
WAPD-T-1059
Country of Publication:
United States
Language:
English