Emergency heat removal system for a nuclear reactor
Patent
·
OSTI ID:862457
- Potomac, MD
A heat removal system for nuclear reactors serving as a supplement to an Emergency Core Cooling System (ECCS) during a Loss of Coolant Accident (LOCA) comprises a plurality of heat pipes having one end in heat transfer relationship with either the reactor pressure vessel, the core support grid structure or other in-core components and the opposite end located in heat transfer relationship with a heat exchanger having heat transfer fluid therein. The heat exchanger is located external to the pressure vessel whereby excessive core heat is transferred from the above reactor components and dissipated within the heat exchanger fluid.
- Assignee:
- United States of America as represented by United States Energy (Washington, DC)
- Patent Number(s):
- US 3935063
- OSTI ID:
- 862457
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
emergency
heat
removal
nuclear
reactor
reactors
serving
supplement
core
cooling
eccs
loss
coolant
accident
loca
comprises
plurality
pipes
transfer
relationship
pressure
vessel
support
grid
structure
in-core
components
opposite
located
exchanger
fluid
therein
external
whereby
excessive
transferred
dissipated
core component
transfer relationship
transfer fluid
nuclear reactors
reactor pressure
heat pipe
pressure vessel
heat exchange
nuclear reactor
heat exchanger
heat transfer
heat removal
heat pipes
support grid
reactor components
core support
reactor component
grid structure
core components
emergency core
core heat
core cooling
transfer relation
coolant accident
/376/165/976/
heat
removal
nuclear
reactor
reactors
serving
supplement
core
cooling
eccs
loss
coolant
accident
loca
comprises
plurality
pipes
transfer
relationship
pressure
vessel
support
grid
structure
in-core
components
opposite
located
exchanger
fluid
therein
external
whereby
excessive
transferred
dissipated
core component
transfer relationship
transfer fluid
nuclear reactors
reactor pressure
heat pipe
pressure vessel
heat exchange
nuclear reactor
heat exchanger
heat transfer
heat removal
heat pipes
support grid
reactor components
core support
reactor component
grid structure
core components
emergency core
core heat
core cooling
transfer relation
coolant accident
/376/165/976/