Emergency heat removal system for a nuclear reactor
AssigneeThe United States of America as represented by the United States Energy Research and Development Administration
InventorThomas L. Dunckel
Life of this patent
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Abstract
A heat removal system for nuclear reactors serving as a supplement to an Emergency Core Cooling System (ECCS) during a Loss of Coolant Accident (LOCA) comprises a plurality of heat pipes having one end in heat transfer relationship with either the reactor pressure vessel, the core support grid structure or other in-core components and the opposite end located in heat transfer relationship with a heat exchanger having heat transfer fluid therein. The heat exchanger is located external to the pressure vessel whereby excessive core heat is transferred from the above reactor components and dissipated within the heat exchanger fluid.
Claims5
An apparatus for removing decay heat from a nuclear reactor having a core, pressure vessel, and cooling system comprising:
- a heat exchange reservoir;
- a plurality of heat pipes having a working fluid selected from the group consisting of water, sodium, lithium, bismuth and mercury, the first end of a heat pipe in heat transfer relationship with the nuclear reactor and the second end within the reservoir;
- a fluid storage tank with fluid therein;
- a fluid connecting means between the reservoir and tank having a valve;
- a means to detect core temperatures;
- and a means to activate the connecting means valve upon detecting core temperatures to control the fluid flow between the storage tank and heat exchange reservoir.
Dependencies are inferred from the claim text.