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Title: 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:
 [1]
  1. 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):
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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 = {1976},
month = {1}
}

Patent:

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