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.
- Research Organization:
- GA Technologies, Inc., San Diego, CA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AT03-76SF71023
- Assignee:
- The United States of America as represented by the United States Department of Energy (Washington, DC)
- Patent Number(s):
- 4,322,268
- Application Number:
- 05/892821
- OSTI ID:
- 864163
- Resource Relation:
- Patent File Date: 1978 Apr 03
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
nuclear
reactor
gas-cooled
disclosed
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adapted
pass
coolant
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core
associated
steam
generator
duct
main
circulator
therein
auxiliary
communication
selectively
heat
exchanger
circulators
installed
common
vertical
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vessel
return
communicates
intersects
junction
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flow
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valve
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effect
loops
coolant gas
steam generator
reactor vessel
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nuclear reactor
heat exchanger
reactor core
coolant flow
cooled nuclear
auxiliary cooling
auxiliary heat
vertical cavity
primary cooling
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gas-cooled nuclear
flow diverter
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