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 Lab. (INL), Idaho Falls, ID (United States)
- 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
Clark, C R, Hallinan, N P, Jue, J F, Keiser, D D, and Wight, J M. Monolithic Fuel Fabrication Process Development. United States: N. p., 2006.
Web.
Clark, C R, Hallinan, N P, Jue, J F, Keiser, D D, & Wight, J M. Monolithic Fuel Fabrication Process Development. United States.
Clark, C R, Hallinan, N P, Jue, J F, Keiser, D D, and Wight, J M. 2006.
"Monolithic Fuel Fabrication Process Development". United States. https://www.osti.gov/servlets/purl/911194.
@article{osti_911194,
title = {Monolithic Fuel Fabrication Process Development},
author = {Clark, C R and Hallinan, N P and Jue, J F and Keiser, D D and Wight, J M},
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 = {},
url = {https://www.osti.gov/biblio/911194},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon May 01 00:00:00 EDT 2006},
month = {Mon May 01 00:00:00 EDT 2006}
}
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