Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems
The effects of steam generator tube ruptures in a pressurized water reactor are mitigated by reducing the pressure in the primary loop by diverting reactor coolant through the heat exchanger of a passive heat removal system immersed in the in containment refueling water storage tank in response to a high feed water level in the steam generator. Reactor coolant inventory is maintained by also in response to high steam generator level introducing coolant into the primary loop from core make-up tanks at the pressure in the reactor coolant system pressurizer. The high steam generator level is also used to isolate the start-up feed water system and the chemical and volume control system to prevent flooding into the steam header. 2 figures.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
- DOE Contract Number:
- AC03-90SF18495
- Assignee:
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
- Patent Number(s):
- US 5309487; A
- Application Number:
- PPN: US 7-903683
- OSTI ID:
- 7201345
- Resource Relation:
- Patent File Date: 24 Jun 1992
- Country of Publication:
- United States
- Language:
- English
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Nuclear reactor with makeup water assist from residual heat removal system
Nuclear reactor with makeup water assist from residual heat removal system
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
STEAM GENERATORS
MITIGATION
RUPTURES
AUXILIARY WATER SYSTEMS
ENGINEERED SAFETY SYSTEMS
PRIMARY COOLANT CIRCUITS
ACCIDENTS
AUXILIARY SYSTEMS
BOILERS
COOLING SYSTEMS
ENERGY SYSTEMS
ENRICHED URANIUM REACTORS
FAILURES
POWER REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled