FUEL ELEMENT
Abstract
A ceramic fuel element for a nuclear reactor that has improved structural stability as well as improved cooling and fission product retention characteristics is presented. The fuel element includes a plurality of stacked hollow ceramic moderator blocks arranged along a tubular raetallic shroud that encloses a series of axially apertured moderator cylinders spaced inwardly of the shroud. A plurality of ceramic nuclear fuel rods are arranged in the annular space between the shroud and cylinders of moderator and appropriate support means and means for directing gas coolant through the annular space are also provided. (AEC)
- Inventors:
- Issue Date:
- Research Org.:
- Originating Research Org. not identified
- OSTI Identifier:
- 4693890
- Patent Number(s):
- 3111477
- 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-17-042321
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTOR TECHNOLOGY; CERAMICS; COOLING; CYLINDERS; FISSION PRODUCTS; FUEL ELEMENTS; GAS COOLANT; JACKETS; MECHANICAL STRUCTURES; MODERATORS; REACTORS; STABILITY
Citation Formats
Bean, R W. FUEL ELEMENT. United States: N. p., 1963.
Web.
Bean, R W. FUEL ELEMENT. United States.
Bean, R W. Tue .
"FUEL ELEMENT". United States.
@article{osti_4693890,
title = {FUEL ELEMENT},
author = {Bean, R W},
abstractNote = {A ceramic fuel element for a nuclear reactor that has improved structural stability as well as improved cooling and fission product retention characteristics is presented. The fuel element includes a plurality of stacked hollow ceramic moderator blocks arranged along a tubular raetallic shroud that encloses a series of axially apertured moderator cylinders spaced inwardly of the shroud. A plurality of ceramic nuclear fuel rods are arranged in the annular space between the shroud and cylinders of moderator and appropriate support means and means for directing gas coolant through the annular space are also provided. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {11}
}
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