Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems
- Export, PA
- Penn Hills, PA
- Murrysville Boro, PA
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)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC03-90SF18495
- Assignee:
- Westinghouse Electric Corp. (Pittsburgh, PA)
- Patent Number(s):
- US 5309487
- OSTI ID:
- 869282
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
steam
generator
tube
rupture
pressurized
water
reactor
passive
safety
systems
effects
ruptures
mitigated
reducing
pressure
primary
loop
diverting
coolant
heat
exchanger
removal
immersed
containment
refueling
storage
tank
response
feed
level
passive heat
passive safety
water level
water reactor
pressurized water
water storage
storage tank
reactor coolant
steam generator
heat exchange
heat exchanger
heat removal
refueling water
safety systems
generator tube
feed water
tube rupture
primary loop
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