Pressurized water nuclear reactor system with hot leg vortex mitigator
This patent describes an improvement in a pressurized water nuclear reactor system having a reactor pressure vessel, at least one steam generator, a hot leg conduit for charging of hot fluid from the reactor pressure vessel to the steam generator, and at least one cold leg conduit for return of cool fluid from the steam generator back to the reactor pressure vessel. The improvement comprises a residual heat removal device wherein: the hot leg has an inside diameter D{sub 1}; a first section of residual heat removal conduit is provided, having an inside diameter D{sub 2}, a first end for receipt of fluid from the hot leg, and a second end; a second section of residual heat removal conduit is provided connected to the reactor pressure vessel; a pump interconnects the second end of the first section of residual heat removal conduit with the second section of residual heat removal conduit; and a step nozzle of an inside diameter D{sub 3} and a length L interconnects the hot leg to the first end of the first section of residual heat removal conduit, with D{sub 3}/D{sub 1} {ge} 0.55, with D{sub 3}/D{sub 2}1.9 and L/D{sub 3} {ge} 1.44.
- Assignee:
- Westinghouse Electric Corp., Pittsburgh, PA (USA)
- Patent Number(s):
- A; US 4957693
- Application Number:
- PPN: US s 7-293160
- OSTI ID:
- 6345494
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BOILERS
CONTAINERS
DUCTS
EQUIPMENT
FLUID FLOW
HEAT EXTRACTION
HEAT RECOVERY EQUIPMENT
PIPES
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
STEAM GENERATORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS