Pressurized water nuclear reactor system with hot leg vortex mit

Details Pressurized water nuclear reactor system with hot leg vortex mit Pressurized water nuclear reactor system with hot leg vortex mit

1989-01-03

1990-09-18

Wasil, Daniel D.

Induced nuclear reactions: processes, systems, and elements

Reactor protection or damage prevention

Auxiliary heat removal structure

376352, C21C 900

Patent

active

049576933

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.

REFERENCES:
patent: 4064001 (1977-12-01), Duncan
patent: 4187147 (1980-02-01), Braun et al.
patent: 4280796 (1981-07-01), Reinsch
patent: 4643871 (1987-02-01), Fajeau
patent: 4753771 (1988-06-01), Conway et al.
patent: 4769209 (1988-09-01), Tower et al.

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