JACKETED FUEL ELEMENTS FOR GRAPHITE MODERATED REACTORS
Abstract
Fuel elements for a heterogeneous, fluid cooled, graphite moderated reactor are described. The fuel elements are comprised of a body of natural uranium hermetically sealed in a jacket of corrosion resistant material. The jacket, which may be aluminum or some other material which is non-fissionable and of a type having a low neutron capture cross-section, acts as a barrier between the fissioning isotope and the coolant or moderator or both. The jacket minimizes the tendency of the moderator and coolant to become radioactive and/or contaminated by fission fragments from the fissioning isotope.
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4208106
- Patent Number(s):
- 2886503
- 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-13-023131
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTORS; ALUMINUM; BARRIERS; CAPTURE; CONTAMINATION; COOLANTS; CORROSION; CROSS SECTIONS; FISSION PRODUCTS; FISSIONABLE MATERIALS; FUEL ELEMENTS; GRAPHITE MODERATOR; JACKETS; LIQUIDS; NATURAL URANIUM FUEL; NEUTRONS; PLANNING; POWER PLANTS; SEALS; ZONES
Citation Formats
Szilard, L, Wigner, E P, and Creutz, E C. JACKETED FUEL ELEMENTS FOR GRAPHITE MODERATED REACTORS. United States: N. p., 1959.
Web.
Szilard, L, Wigner, E P, & Creutz, E C. JACKETED FUEL ELEMENTS FOR GRAPHITE MODERATED REACTORS. United States.
Szilard, L, Wigner, E P, and Creutz, E C. Tue .
"JACKETED FUEL ELEMENTS FOR GRAPHITE MODERATED REACTORS". United States.
@article{osti_4208106,
title = {JACKETED FUEL ELEMENTS FOR GRAPHITE MODERATED REACTORS},
author = {Szilard, L and Wigner, E P and Creutz, E C},
abstractNote = {Fuel elements for a heterogeneous, fluid cooled, graphite moderated reactor are described. The fuel elements are comprised of a body of natural uranium hermetically sealed in a jacket of corrosion resistant material. The jacket, which may be aluminum or some other material which is non-fissionable and of a type having a low neutron capture cross-section, acts as a barrier between the fissioning isotope and the coolant or moderator or both. The jacket minimizes the tendency of the moderator and coolant to become radioactive and/or contaminated by fission fragments from the fissioning isotope.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {5}
}
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