Cooling system for a nuclear reactor
Abstract
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.
- Inventors:
- Issue Date:
- Research Org.:
- GA Technologies, Inc., San Diego, CA (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 864163
- Patent Number(s):
- 4322268
- Application Number:
- 05/892821
- Assignee:
- The United States of America as represented by the United States Department of Energy (Washington, DC)
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
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
- DOE Contract Number:
- AT03-76SF71023
- Resource Type:
- Patent
- Resource Relation:
- Patent File Date: 1978 Apr 03
- Country of Publication:
- United States
- Language:
- English
- Subject:
- cooling; nuclear; reactor; gas-cooled; disclosed; primary; loop; adapted; pass; coolant; gas; core; associated; steam; generator; duct; main; circulator; therein; auxiliary; communication; selectively; heat; exchanger; circulators; installed; common; vertical; cavity; vessel; return; communicates; intersects; junction; located; flow; diverter; valve; operative; effect; loops; coolant gas; steam generator; reactor vessel; heat exchange; nuclear reactor; heat exchanger; reactor core; coolant flow; cooled nuclear; auxiliary cooling; auxiliary heat; vertical cavity; primary cooling; pass coolant; gas-cooled nuclear; flow diverter; pass cool; diverter valve; /376/976/
Citation Formats
Amtmann, Hans H. Cooling system for a nuclear reactor. United States: N. p., 1982.
Web.
Amtmann, Hans H. Cooling system for a nuclear reactor. United States.
Amtmann, Hans H. Fri .
"Cooling system for a nuclear reactor". United States. https://www.osti.gov/servlets/purl/864163.
@article{osti_864163,
title = {Cooling system for a nuclear reactor},
author = {Amtmann, Hans H.},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1982},
month = {Fri Jan 01 00:00:00 EST 1982}
}