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U.S. Department of Energy
Office of Scientific and Technical Information

DECAY HEAT REMOVAL SYSTEM FOR LIQUID-COOLED NUCLEAR REACTORS

Patent ·
OSTI ID:4086815
The nuclear reactor described is provided with a closed primary main circuit for the generation of power and a separate closed emergency circuit for the dissipation of reactor decay heat. The emergency circuit comprises a pressurizer disposed above the level of the core structure an emergency heat exchanger, and valved ducting connecting the pressurizer, and the emergency heat exchanger in a closed circuit with the core structure. The pressurizer is provided with an overflow pipe so that natural circulation is established in the emergency circuit on cessation of normal coolant circulation because of a volume expansion of the reactor coolant. (Gmelin Inst.)
Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-18-009599
OSTI ID:
4086815
Report Number(s):
DE 1156516
Country of Publication:
Germany
Language:
English