Passive residual heat removal system for nuclear power plant
An enclosed reservoir is sized and located in relation to the steam generator of a pressurized water nuclear reactor power plant so that upon a loss of feedwater flow to the steam generator, a gravity induced supplementary flow into the steam generator is automatically initiated to dissipate the residual heat generated in the reactor. The height of the reservoir is the same as the distance between upper and lower design limits on steam generator feedwater level. The top of the steam generator is fluidly connected to the top of the reservoir to equalize the pressure therebetween. The gravity induced flow from the reservoir to the steam generator produces a water level in the steam generator that stays within the upper and lower design limits.
- Assignee:
- Combustion Engineering Inc
- Patent Number(s):
- US 4239596
- Application Number:
- TRN: 81-013891
- OSTI ID:
- 6331853
- Resource Relation:
- Patent File Date: Filed date 16 Dec 1977
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AFTER-HEAT REMOVAL
PWR TYPE REACTORS
LOSS OF FLOW
NUCLEAR POWER PLANTS
PIPES
REACTOR SHUTDOWN
STEAM GENERATORS
ACCIDENTS
BOILERS
NUCLEAR FACILITIES
POWER PLANTS
REACTOR ACCIDENTS
REACTORS
REMOVAL
SHUTDOWNS
THERMAL POWER PLANTS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220200* - Nuclear Reactor Technology- Components & Accessories
220900 - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled