POWER PLANT USING A STEAM-COOLED NUCLEAR REACTOR
Patent
·
OSTI ID:4660828
A method of providing efficient and economic means for obtaining reheat from nuclear heat is described. A steamcooled steam-moderated reactor produces high-pressure, high-temperature steam. A multi-stage steam turbine partially expands the high-pressure steam, which is then withdrawn and reheated, and then further expanded for producing useful power. The saturated steam is superheated by leading it through tubular passages provided in the fuel assemblies of a nuclear reactor, leading the useful part of the superheated steam into a steam turbine in which it expands to a predetermined intermediate pressure, leading the steam at that reduced pressure from the turbine back into the reactor where it is reheated by flowing through other tubular passages in the fuel assemblies, and returning the reheated steam to the turbine for further expansion. (M.C.G.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-17-042391
- Assignee:
- DTIE; NSA-17-042391
- Patent Number(s):
- US 3108938
- OSTI ID:
- 4660828
- Country of Publication:
- United States
- Language:
- English
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