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:
-
- Monroeville, PA
- Issue Date:
- Research Org.:
- Westinghouse Electric Corp., Pittsburgh, PA (United States)
- OSTI Identifier:
- 867527
- Patent Number(s):
- 4957693
- Assignee:
- Westinghouse Electric Corp. (Pittsburgh, PA)
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- 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}
}