THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME
Abstract
A body is presented for use in a thermal fission reactor comprising a sintered compressed mass of a substance of the group consisting of uranium, thorium, and oxides and carbides of uranium and thorium, enclosed in an envelope of a sintered, compacted, heat-conductive material of the group consisting of beryllium, zirconium, and oxides and carbides of beryllium and zirconium.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4192511
- Patent Number(s):
- 2907705
- Assignee:
- U.S. Atomic Energy Commission
- 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
- NSA Number:
- NSA-14-008261
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-60
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTOR TECHNOLOGY; BERYLLIUM; BERYLLIUM CARBIDES; BERYLLIUM OXIDES; FUEL ELEMENTS; HEAT TRANSFER; REACTORS; SINTERED MATERIALS; THERMAL CONDUCTIVITY; THORIUM; THORIUM CARBIDES; THORIUM OXIDES; URANIUM; URANIUM CARBIDES; URANIUM OXIDES; ZIRCONIUM; ZIRCONIUM CARBIDES; ZIRCONIUM OXIDES
Citation Formats
Blainey, A. THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME. United States: N. p., 1959.
Web.
Blainey, A. THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME. United States.
Blainey, A. Thu .
"THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME". United States.
@article{osti_4192511,
title = {THERMAL FISSION REACTOR COMPOSITIONS AND METHOD OF FABRICATING SAME},
author = {Blainey, A},
abstractNote = {A body is presented for use in a thermal fission reactor comprising a sintered compressed mass of a substance of the group consisting of uranium, thorium, and oxides and carbides of uranium and thorium, enclosed in an envelope of a sintered, compacted, heat-conductive material of the group consisting of beryllium, zirconium, and oxides and carbides of beryllium and zirconium.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Oct 01 00:00:00 EDT 1959},
month = {Thu Oct 01 00:00:00 EDT 1959}
}
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