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Properties of extruded fuel rods for HTGR applications

Author
Hamner, R. L.
Published
United States : [publisher not identified], 1977.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1977.
Physical Description
microfiche : negative ; 11 x 15 cm
Additional Creators
Eatherly, W. P. and Robbins, J. M.

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Summary
Until recently, a small program existed at ORNL and at LASL investigating extrusion as a process for fabricating fuel rods or elements for high temperature gas-cooled reactors. This work was undertaken because of the relative simplicity of the extrusion process over injection molding techniques. Also, in looking ahead to process heat reactors where the outlet gas temperatures of 1000/sup 0/C or greater are desirable, the fuel would operate at temperatures no higher than steam-cycle reactors if in direct contact with the helium content. Hollow extruded rods with a strong continuous matrix offer such a configuration. Advantages and disadvantages of extruded fuel rods are described.
Report Numbers
CONF-770701-4
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: W-7405-ENG-26
OSTI Identifier 7096087
Research organization: Oak Ridge National Lab., TN (USA).
Funding Information
Sponsored by USDOE.
View MARC record | catkey: 44260999