Pressurized water nuclear reactor system with hot leg vortex mitigator
- Monroeville, PA
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.
- Research Organization:
- WESTINGHOUSE ELECTRIC CORP
- DOE Contract Number:
- AC03-86SF16038
- Assignee:
- Westinghouse Electric Corp. (Pittsburgh, PA)
- Patent Number(s):
- US 4957693
- OSTI ID:
- 867527
- Country of Publication:
- United States
- Language:
- English
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