National Technical Reports Library

The National Technical Information Service acquires, indexes, abstracts, and archives the largest collection of U.S. government-sponsored technical reports in existence. The NTRL offers online, free and open access to these authenticated government technical reports. Technical reports and documents in its repository may be available online for free either from the issuing federal agency, the U.S. Government Publishing Office’s Federal Digital System website, or through search engines.

Details

U-Mo Foil/Cladding Interactions in Friction Stir Welded Monolithic RERTR Fuel Plates.

DE2007911729

Publication Date	2006
Personal Author	Keiser, D. D.; Jue, J. F.; Clark, C. R.
Page Count	12
Abstract	Interaction between U-Mo fuel and Al has proven to dramatically impact the overall irradiation performance of RERTR dispersion fuels. It is of interest to better understand how similar interactions may affect the performance of monolithic fuel plates, where a uranium alloy fuel is sandwiched between aluminum alloy cladding. The monolithic fuel plate removes the fuel matrix entirely, which reduces the total surface area of the fuel that is available to react with the aluminum and moves the interface between the fuel and cladding to a colder region of the fuel plate. One of the major fabrication techniques for producing monolithic fuel plates is friction stir welding. This paper will discuss the interactions that can occur between the U-Mo foil and 6061 Al cladding when applying this fabrication technique. It has been determined that the time at high temperatures should be limited as much as is possible during fabrication or any post-fabrication treatment to reduce as much as possible the interactions between the foil and cladding. Without careful control of the fabrication process, significant interaction between the U-Mo foil and Al alloy cladding can result. The reaction layers produced from such interactions can exhibit notably different morphologies vis-a-vis those typically observed for dispersion fuels.
Keywords	Research and test reactors Irradiation Fuel plates Uranium alloys Aluminum alloys Fabrication Welding Friction stir welding
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200802

U-Mo Foil/Cladding Interactions in Friction Stir Welded Monolithic RERTR Fuel Plates.

U-Mo Foil/Cladding Interactions in Friction Stir Welded Monolithic RERTR Fuel Plates.
DE2007911729

Publication Date	2006
Personal Author	Keiser, D. D.; Jue, J. F.; Clark, C. R.
Page Count	12
Abstract	Interaction between U-Mo fuel and Al has proven to dramatically impact the overall irradiation performance of RERTR dispersion fuels. It is of interest to better understand how similar interactions may affect the performance of monolithic fuel plates, where a uranium alloy fuel is sandwiched between aluminum alloy cladding. The monolithic fuel plate removes the fuel matrix entirely, which reduces the total surface area of the fuel that is available to react with the aluminum and moves the interface between the fuel and cladding to a colder region of the fuel plate. One of the major fabrication techniques for producing monolithic fuel plates is friction stir welding. This paper will discuss the interactions that can occur between the U-Mo foil and 6061 Al cladding when applying this fabrication technique. It has been determined that the time at high temperatures should be limited as much as is possible during fabrication or any post-fabrication treatment to reduce as much as possible the interactions between the foil and cladding. Without careful control of the fabrication process, significant interaction between the U-Mo foil and Al alloy cladding can result. The reaction layers produced from such interactions can exhibit notably different morphologies vis-a-vis those typically observed for dispersion fuels.
Keywords	Research and test reactors Irradiation Fuel plates Uranium alloys Aluminum alloys Fabrication Welding Friction stir welding
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200802