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Title: Monolithic Fuel Fabrication Process Development

Abstract

The pursuit of a high uranium density research reactor fuel plate has led to monolithic fuel, which possesses the greatest possible uranium density in the fuel region. Process developments in fabrication development include friction stir welding tool geometry and cooling improvements and a reduction in the length of time required to complete the transient liquid phase bonding process. Annealing effects on the microstructures of the U-10Mo foil and friction stir welded aluminum 6061 cladding are also examined.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
911194
Report Number(s):
INL/CON-06-01370
TRN: US0704453
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Conference: Research Reactor Fuel Management (RRFM),Sofia, Bulgaria,04/30/2006,05/04/2006
Country of Publication:
United States
Language:
English
Subject:
10 - SYNTHETIC FUELS, 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ALUMINIUM; ANNEALING; BONDING; FABRICATION; FRICTION; FUEL MANAGEMENT; FUEL PLATES; GEOMETRY; RESEARCH REACTORS; TRANSIENTS; URANIUM; WELDING; fabrication; monolithic fuel; process; uranium

Citation Formats

C. R. Clark, N. P. Hallinan, J. F. Jue, D. D. Keiser, and J. M. Wight. Monolithic Fuel Fabrication Process Development. United States: N. p., 2006. Web.
C. R. Clark, N. P. Hallinan, J. F. Jue, D. D. Keiser, & J. M. Wight. Monolithic Fuel Fabrication Process Development. United States.
C. R. Clark, N. P. Hallinan, J. F. Jue, D. D. Keiser, and J. M. Wight. Mon . "Monolithic Fuel Fabrication Process Development". United States. doi:. https://www.osti.gov/servlets/purl/911194.
@article{osti_911194,
title = {Monolithic Fuel Fabrication Process Development},
author = {C. R. Clark and N. P. Hallinan and J. F. Jue and D. D. Keiser and J. M. Wight},
abstractNote = {The pursuit of a high uranium density research reactor fuel plate has led to monolithic fuel, which possesses the greatest possible uranium density in the fuel region. Process developments in fabrication development include friction stir welding tool geometry and cooling improvements and a reduction in the length of time required to complete the transient liquid phase bonding process. Annealing effects on the microstructures of the U-10Mo foil and friction stir welded aluminum 6061 cladding are also examined.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon May 01 00:00:00 EDT 2006},
month = {Mon May 01 00:00:00 EDT 2006}
}

Conference:
Other availability
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