Interfacing systems loss-of-coolant accident in Oconee-1 pressurized water reactor
The primary system of a pressurized water reactor (PWR) operates at a relatively high pressure (15.5 MPa, 2250 psia) and consists of piping and components designed to withstand these pressures. The low-pressure-injection system (LPIS) connects to the primary system but possesses low-pressure piping passing outside the containment. Therefore, a potential exists for a loss-of-coolant accident (LOCA) outside the containment and concurrent damage to systems needed to cope with this problem. The emergency core-cooling system (ECCS) is assumed to be available for this event. A set of calculations were performed using the TRAC-PF1 code and a model of the Oconee-1 PWR to investigate the consequences of, and possible operator actions for, such an accident scenario.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6451588
- Report Number(s):
- LA-UR-84-3284; CONF-8410142-21; ON: DE85000175
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ECCS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
HPCI
LOSS OF COOLANT
OCONEE-1 REACTOR
OPERATION
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR OPERATION
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS