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Title: Passive decay heat removal system for water-cooled nuclear reactors

Abstract

This document describes passive decay-heat removal system for a water-cooled nuclear reactor which employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated evaporator located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it will become exposed to steam. Vapor produced in the evaporator passes upward to the condenser above the normal water level. In operation, condensation in the condenser removes heat from the system, and the condensed liquid is returned to the evaporator. The system is disposed such that during normal reactor operations where the water level is at its usual position, very little heat will be removed from the system, but during emergency, low water level conditions, substantial amounts of decay heat will be removed.

Inventors:
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (United States)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
5029746
Patent Number(s):
PATENTS-US-A7596155
Application Number:
ON: DE92016381; PPN: US 7-596155
Assignee:
Dept. of Energy ORNL; EDB-92-124129
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Patent Application
Resource Relation:
Patent File Date: 10 Oct 1990
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; AFTER-HEAT REMOVAL; PWR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; INVENTIONS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210100 - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Forseberg, C.W.. Passive decay heat removal system for water-cooled nuclear reactors. United States: N. p., 1990. Web.
Forseberg, C.W.. Passive decay heat removal system for water-cooled nuclear reactors. United States.
Forseberg, C.W.. Mon . "Passive decay heat removal system for water-cooled nuclear reactors". United States. https://www.osti.gov/servlets/purl/5029746.
@article{osti_5029746,
title = {Passive decay heat removal system for water-cooled nuclear reactors},
author = {Forseberg, C.W.},
abstractNote = {This document describes passive decay-heat removal system for a water-cooled nuclear reactor which employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated evaporator located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it will become exposed to steam. Vapor produced in the evaporator passes upward to the condenser above the normal water level. In operation, condensation in the condenser removes heat from the system, and the condensed liquid is returned to the evaporator. The system is disposed such that during normal reactor operations where the water level is at its usual position, very little heat will be removed from the system, but during emergency, low water level conditions, substantial amounts of decay heat will be removed.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1990},
month = {Mon Jan 01 00:00:00 EST 1990}
}

Patent Application:

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