FUEL ELEMENT FOR A NUCLEAR REACTOR
Abstract
A fuel element structure particularly useful in high temperature nuclear reactors is presented. Basically, the structure comprises two coaxial graphite sleeves integrally joined together by radial fins. Due to the high structural strength of graphite at high temperatures and the rigidity of this structure, nuclear fuel encased within the inner sleeve in contiguous relation therewith is supported and prevented from expanding radially at high temperatures. Thus, the necessity of relying on the usual cladding materials with relatively low temperature limitations for structural strength is removed. (AEC)
- Inventors:
- Issue Date:
- OSTI Identifier:
- 4684955
- Patent Number(s):
- 3111475
- 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-17-042320
- Resource Type:
- Patent
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
- Subject:
- REACTOR TECHNOLOGY; DEFORMATION; FINS; FUEL CANS; FUEL ELEMENTS; GRAPHITE; HIGH TEMPERATURE; MECHANICAL STRUCTURES; REACTORS
Citation Formats
Davidson, J K. FUEL ELEMENT FOR A NUCLEAR REACTOR. United States: N. p., 1963.
Web.
Davidson, J K. FUEL ELEMENT FOR A NUCLEAR REACTOR. United States.
Davidson, J K. Tue .
"FUEL ELEMENT FOR A NUCLEAR REACTOR". United States.
@article{osti_4684955,
title = {FUEL ELEMENT FOR A NUCLEAR REACTOR},
author = {Davidson, J K},
abstractNote = {A fuel element structure particularly useful in high temperature nuclear reactors is presented. Basically, the structure comprises two coaxial graphite sleeves integrally joined together by radial fins. Due to the high structural strength of graphite at high temperatures and the rigidity of this structure, nuclear fuel encased within the inner sleeve in contiguous relation therewith is supported and prevented from expanding radially at high temperatures. Thus, the necessity of relying on the usual cladding materials with relatively low temperature limitations for structural strength is removed. (AEC)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1963},
month = {11}
}
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