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

Abstract

A pressurized water nuclear reactor system includes a vortex mitigator in the form of a cylindrical conduit between the hot leg conduit and a first section of residual heat removal conduit, which conduit leads to a pump and a second section of residual heat removal conduit leading back to the reactor pressure vessel. The cylindrical conduit is of such a size that where the hot leg has an inner diameter D.sub.1, the first section has an inner diameter D.sub.2, and the cylindrical conduit or step nozzle has a length L and an inner diameter of D.sub.3 ; D.sub.3 /D.sub.1 is at least 0.55, D.sub.2 is at least 1.9, and L/D.sub.3 is at least 1.44, whereby cavitation of the pump by a vortex formed in the hot leg is prevented.

Inventors:
 [1]
  1. (Monroeville, PA)
Publication Date:
Research Org.:
WESTINGHOUSE ELECTRIC CORP
OSTI Identifier:
867527
Patent Number(s):
US 4957693
Assignee:
Westinghouse Electric Corp. (Pittsburgh, PA) OSTI
DOE Contract Number:  
AC03-86SF16038
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
pressurized; water; nuclear; reactor; hot; leg; vortex; mitigator; form; cylindrical; conduit; section; residual; heat; removal; leads; pump; leading; pressure; vessel; size; inner; diameter; step; nozzle; length; 55; 44; whereby; cavitation; formed; prevented; cylindrical conduit; inner diameter; pressurized water; reactor pressure; pressure vessel; nuclear reactor; residual heat; heat removal; water nuclear; removal conduit; conduit leading; hot leg; vortex mitigator; /376/976/

Citation Formats

Lau, Louis K. S. Pressurized water nuclear reactor system with hot leg vortex mitigator. United States: N. p., 1990. Web.
Lau, Louis K. S. Pressurized water nuclear reactor system with hot leg vortex mitigator. United States.
Lau, Louis K. S. Mon . "Pressurized water nuclear reactor system with hot leg vortex mitigator". United States. https://www.osti.gov/servlets/purl/867527.
@article{osti_867527,
title = {Pressurized water nuclear reactor system with hot leg vortex mitigator},
author = {Lau, Louis K. S.},
abstractNote = {A pressurized water nuclear reactor system includes a vortex mitigator in the form of a cylindrical conduit between the hot leg conduit and a first section of residual heat removal conduit, which conduit leads to a pump and a second section of residual heat removal conduit leading back to the reactor pressure vessel. The cylindrical conduit is of such a size that where the hot leg has an inner diameter D.sub.1, the first section has an inner diameter D.sub.2, and the cylindrical conduit or step nozzle has a length L and an inner diameter of D.sub.3 ; D.sub.3 /D.sub.1 is at least 0.55, D.sub.2 is at least 1.9, and L/D.sub.3 is at least 1.44, whereby cavitation of the pump by a vortex formed in the hot leg is prevented.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1990},
month = {1}
}

Patent:

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