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Title: Pressurized water nuclear reactor system with hot leg vortex mitigator

Abstract

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.

Inventors:
Publication Date:
OSTI Identifier:
6345494
Patent Number(s):
US 4957693; A
Application Number:
PPN: US s 7-293160; TRN: 90-037658
Assignee:
Westinghouse Electric Corp., Pittsburgh, PA (USA)
Resource Type:
Patent
Resource Relation:
Patent File Date: 3 Jan 1989
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HEAT RECOVERY EQUIPMENT; PWR TYPE REACTORS; HEAT EXTRACTION; DUCTS; FLUID FLOW; PIPES; PRESSURE VESSELS; STEAM GENERATORS; BOILERS; CONTAINERS; EQUIPMENT; REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210200* - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Lau, L K.S. Pressurized water nuclear reactor system with hot leg vortex mitigator. United States: N. p., 1990. Web.
Lau, L K.S. Pressurized water nuclear reactor system with hot leg vortex mitigator. United States.
Lau, L K.S. Tue . "Pressurized water nuclear reactor system with hot leg vortex mitigator". United States.
@article{osti_6345494,
title = {Pressurized water nuclear reactor system with hot leg vortex mitigator},
author = {Lau, L K.S.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {9}
}