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Title: 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 DTIE; NSA-13-023131
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}
}