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Title: NEUTRONIC REACTOR CORE

Abstract

An improved core for a gas-cooled power reactor which admits gas coolant at high temperatures while affording strong integral supporting structure and efficient moderation of neutrons is described. The multiplicities of fuel elements constituting the critical amassment of fissionable material are supported and confined by a matrix of metallic structure which is interspersed therebetween. Thermal insulation is interposed between substantially all of the metallic matrix and the fuel elements; the insulation then defines the principal conduit system for conducting the coolant gas in heat-transfer relationship with the fuel elements. The metallic matrix itseif comprises a system of ducts through which an externally-cooled hydrogeneous liquid, such as water, is circulated to serve as the principal neutron moderant for the core and conjointly as the principal coolant for the insulated metallic structure. In this way, use of substantially neutron transparent metals, such as aluminum, becomes possible for the supporting structure, despite the high temperatures of the proximate gas. The Aircraft Nuclear Propulsion program's "R-1" reactor design is a preferred embodiment.

Inventors:
;
Issue Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4036096
Patent Number(s):
2992981
Assignee:
U.S. Atomic Energy Commission DTIE; NSA-15-023144
NSA Number:
NSA-15-023144
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-61
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; ABSORPTION; ALUMINUM; FUEL ELEMENTS; GAS COOLANT; HEAT TRANSFER; HIGH TEMPERATURE; MECHANICAL STRUCTURES; MODERATORS; NEUTRONS; PATENT; REACTOR CORE; REACTORS; THERMAL CONDUCTIVITY; WATER MODERATOR

Citation Formats

Thomson, W.B., and Corbin, A. Jr. NEUTRONIC REACTOR CORE. United States: N. p., 1961. Web.
Thomson, W.B., & Corbin, A. Jr. NEUTRONIC REACTOR CORE. United States.
Thomson, W.B., and Corbin, A. Jr. Tue . "NEUTRONIC REACTOR CORE". United States.
@article{osti_4036096,
title = {NEUTRONIC REACTOR CORE},
author = {Thomson, W.B. and Corbin, A. Jr.},
abstractNote = {An improved core for a gas-cooled power reactor which admits gas coolant at high temperatures while affording strong integral supporting structure and efficient moderation of neutrons is described. The multiplicities of fuel elements constituting the critical amassment of fissionable material are supported and confined by a matrix of metallic structure which is interspersed therebetween. Thermal insulation is interposed between substantially all of the metallic matrix and the fuel elements; the insulation then defines the principal conduit system for conducting the coolant gas in heat-transfer relationship with the fuel elements. The metallic matrix itseif comprises a system of ducts through which an externally-cooled hydrogeneous liquid, such as water, is circulated to serve as the principal neutron moderant for the core and conjointly as the principal coolant for the insulated metallic structure. In this way, use of substantially neutron transparent metals, such as aluminum, becomes possible for the supporting structure, despite the high temperatures of the proximate gas. The Aircraft Nuclear Propulsion program's "R-1" reactor design is a preferred embodiment.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1961},
month = {7}
}