IMPROVEMENTS IN OR RELATING TO NUCLEAR REACTOR POWERED STEAM GENERATING SYSTEMS
Patent
·
OSTI ID:4777654
A reactor-steam generator system is designed with means for emergency removal of shutdown heat from the core when pumping power is not available for circulating the coolant. The system is provided with a steam generator at a higher level than the core for convection flow of the coolant. The steam generator is supplied with water and is arranged to feed steam to a steam drum to maintain the convection flow, and a circuit is provided for removing steam from the drum so that the steam can be moved by convection through a heat sink and back to the drum. A valve is provided in the circuit for closing when temperature or pressure in the drum falls to prevent the (organic) coolant from solidifying. The system and means for emergency cooling are described with reference to a ship reactor cooled with a terphenyl coolant. (D.L.C.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-16-031319
- OSTI ID:
- 4777654
- Report Number(s):
- GB 906096
- Country of Publication:
- United Kingdom
- Language:
- English
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