RELAP5 analyses and support of Oconee-1 PTS studies
Conference
·
OSTI ID:5624621
The integrity of a reactor vessel during a severe overcooling transient with primary system pressurization is a current safety concern and has been identified as an Unresolved Safety Issue(USI) A-49 by the US Nuclear Regulatory Commission (NRC). Resolution of USI A-49, denoted as Pressurized Thermal Shock (PTS), is being examined by the US NRC sponsored PTS integration study. In support of this study, the Idaho National Engineering Laboratory (INEL) has performed RELAP5/MOD1.5 thermal-hydraulic analyses of selected overcooling transients. These transient analyses were performed for the Oconee-1 pressurized water reactor (PWR), which is Babcock and Wilcox designed nuclear steam supply system.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5624621
- Report Number(s):
- EGG-M-20883; CONF-8310143-44; ON: DE84002164
- Country of Publication:
- United States
- Language:
- English
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Conference
·
Fri Dec 31 23:00:00 EST 1982
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RELAP5 thermal-hydraulic analyses of pressurized thermal shock sequences for the Oconee-1 pressurized water reactor
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OSTI ID:6391416
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