Loss of offsite power in pressurized water reactors: a combined probabilistic and thermal-hydraulic analysis
Conference
·
OSTI ID:5530183
The Pressurized Water Reactor (PWR) loss of offsite power initiating event was studied at the Idaho National Engineering Laboratory as a part of the US Nuclear Regulatory Commission's (NRC) Severe Accident Sequence Analysis Program. An event tree was developed and used as a basis for investigating high risk accident sequences initiated by a loss of offsite power. Specific high risk sequences for further study were determined by assigning probabilities to events within the tree. The thermal-hydraulic responses of three PWRs of different vendors were calculated for these high risk sequences using the RELAP4/MOD7 computer code. Actions to mitigate the consequences of certain sequences were identified and the critical times for their implementation were determined. 2 refs., 6 figs., 2 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5530183
- Report Number(s):
- EGG-M-01281; CONF-810905-33; ON: TI85013803
- Country of Publication:
- United States
- Language:
- English
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