Emergency heat removal system for a nuclear reactor
Abstract
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.
- Inventors:
-
- Potomac, MD
- Issue Date:
- OSTI Identifier:
- 862457
- Patent Number(s):
- 3935063
- Assignee:
- United States of America as represented by United States Energy (Washington, DC)
- Patent Classifications (CPCs):
-
F - MECHANICAL ENGINEERING F28 - HEAT EXCHANGE IN GENERAL F28D - HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 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/
Citation Formats
Dunckel, Thomas L. Emergency heat removal system for a nuclear reactor. United States: N. p., 1976.
Web.
Dunckel, Thomas L. Emergency heat removal system for a nuclear reactor. United States.
Dunckel, Thomas L. Thu .
"Emergency heat removal system for a nuclear reactor". United States. https://www.osti.gov/servlets/purl/862457.
@article{osti_862457,
title = {Emergency heat removal system for a nuclear reactor},
author = {Dunckel, Thomas L},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Jan 01 00:00:00 EST 1976},
month = {Thu Jan 01 00:00:00 EST 1976}
}
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.