Analysis of a steamline break event with overcooling for a typical B and W reactor
Conference
·
OSTI ID:6376920
A streamline break event with primary system overcooling has been analyzed with the IRT computer code. The reactor analyzed is a typical Babcock and Wilcox plant. Oconee was used as a reference. The objective of this analysis is to provide the required temperature and pressure responses for input to reactor vessel analysis.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6376920
- Report Number(s):
- BNL-NUREG-29833; CONF-811103-39; ON: TI85003646
- Country of Publication:
- United States
- Language:
- English
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HEAT TRANSFER
HYDRAULICS
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