Induced nuclear reactions: processes – systems – and elements – Reactor protection or damage prevention – Auxiliary heat removal structure
Patent
1986-08-13
1988-10-25
Jordan, Charles T.
Induced nuclear reactions: processes, systems, and elements
Reactor protection or damage prevention
Auxiliary heat removal structure
376404, 376461, G21C 1518
Patent
active
047802707
ABSTRACT:
An improved shut-down heat removal system for a liquid metal nuclear reactor of the type having a vessel for holding hot and cold pools of liquid sodium is disclosed herein. Generally, the improved system comprises a redan or barrier within the reactor vessel which allows an auxiliary heat exchanger to become immersed in liquid sodium from the hot pool whenever the reactor pump fails to generate a metal-circulating pressure differential between the hot and cold pools of sodium. This redan also defines an alternative circulation path between the hot and cold pools of sodium in order to equilibrate the distribution of the decay heat from the reactor core. The invention may take the form of a redan or barrier that circumscribes the inner wall of the reactor vessel, thereby defining an annular space therebetween. In this embodiment, the bottom of the annular space communicates with the cold pool of sodium, and the auxiliary heat exchanger is placed in this annular space just above the drawn-down level that the liquid sodium assumes during normal operating conditions. Alternatively, the redan of the invention may include a pair of vertically oriented, concentrically disposed standpipes having a piston member disposed between them that operates somewhat like a pressure-sensitive valve. In both embodiments, the cessation of the pressure differential that is normally created by the reactor pump causes the auxiliary heat exchanger to be immersed in liquid sodium from the hot pool. Additionally, the redan in both embodiments forms a circulation flow path between the hot and cold pools so that the decay heat from the nuclear core is uniformly distributed within the vessel.
REFERENCES:
patent: 4115192 (1978-09-01), Jogand
patent: 4478784 (1984-10-01), Burelbach
Report entitled, "State-of-the-Art Report on Shutdown Heat Removal Systems", dated Jun. 1985, prepared by the Westinghouse Electric Corp. for the Department of Energy.
Report entitled, "Inherent Safety Technology Quarterly Progress Report for Period Ending Oct. 31, 1985", prepared by the Westinghouse Electric Corp. for the U.S. Dept. of Energy and published Dec. 1985.
Hundal Rolv
Sharbaugh John E.
Jordan Charles T.
The United States of America as represented by the United States
Wendtland Richard W.
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