Cooling system for a nuclear reactor
A cooling system for a gas-cooled nuclear reactor is disclosed which includes at least one primary cooling loop adapted to pass coolant gas from the reactor core and an associated steam generator through a duct system having a main circulator therein, and at least one auxiliary cooling loop having communication with the reactor core and adapted to selectively pass coolant gas through an auxiliary heat exchanger and circulator. The main and auxiliary circulators are installed in a common vertical cavity in the reactor vessel, and a common return duct communicates with the reactor core and intersects the common cavity at a junction at which is located a flow diverter valve operative to effect coolant flow through either the primary or auxiliary cooling loops.
- Assignee:
- Dept. Of Energy
- Patent Number(s):
- US 4322268
- OSTI ID:
- 5345264
- Country of Publication:
- United States
- Language:
- English
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210300* -- Power Reactors
Nonbreeding
Graphite Moderated
CONTROL EQUIPMENT
COOLANT LOOPS
COOLANTS
COOLING SYSTEMS
ENERGY SYSTEMS
EQUIPMENT
FLOW REGULATORS
FLUID FLOW
GAS COOLED REACTORS
HEAT EXCHANGERS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTORS
VALVES