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
- Patent Classifications (CPCs):
-
B - PERFORMING OPERATIONS B64 - AIRCRAFT B64C - AEROPLANES
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
- 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 = {Tue Jul 18 00:00:00 EDT 1961},
month = {Tue Jul 18 00:00:00 EDT 1961}
}