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Update on US High Density Fuel Fabrication Development. Research Reactor Fuel Management (RRFM).

DE2007911918

Publication Date	2007
Personal Author	Clark, C. R.; Moore, G. A.; Jue, J. F.; Park, B. H.; Hallinan, N. P.
Page Count	9
Abstract	Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. This metallic fuel type is capable of being fabricated at much higher loadings than any presently used research reactor fuel. Due to the broad range of fuel types this alloy system encompasses-fuel powder to monolithic foil and binary fuel systems to multiple element additions-significant amounts of research and development have been conducted on the fabrication of these fuels. This paper presents an update of the US RERTR effort to develop fabrication techniques and the fabrication methods used for the RERTR-9A miniplate test.
Keywords	Fabrication Research and test reactors Irradiation Alloys Molybdenum Dispersion nuclear fuels Enriched uranium
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National, Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200801

Update on US High Density Fuel Fabrication Development. Research Reactor Fuel Management (RRFM).

Update on US High Density Fuel Fabrication Development. Research Reactor Fuel Management (RRFM).
DE2007911918

Publication Date	2007
Personal Author	Clark, C. R.; Moore, G. A.; Jue, J. F.; Park, B. H.; Hallinan, N. P.
Page Count	9
Abstract	Second generation uranium molybdenum fuel has shown excellent in-reactor irradiation performance. This metallic fuel type is capable of being fabricated at much higher loadings than any presently used research reactor fuel. Due to the broad range of fuel types this alloy system encompasses-fuel powder to monolithic foil and binary fuel systems to multiple element additions-significant amounts of research and development have been conducted on the fabrication of these fuels. This paper presents an update of the US RERTR effort to develop fabrication techniques and the fabrication methods used for the RERTR-9A miniplate test.
Keywords	Fabrication Research and test reactors Irradiation Alloys Molybdenum Dispersion nuclear fuels Enriched uranium
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National, Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200801