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Title: Update on US High Density Fuel Fabrication Development

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.

Authors:
; ; ; ; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NNSA
OSTI Identifier:
911918
Report Number(s):
INL/CON-07-12355
TRN: US0800211
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Conference: Research Reactor Fuel Management (RRFM),Lyon, France,03/11/2007,03/15/2007
Country of Publication:
United States
Language:
English
Subject:
21 - SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS, 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; ALLOY SYSTEMS; FABRICATION; FUEL MANAGEMENT; FUEL SYSTEMS; IRRADIATION; MOLYBDENUM; PERFORMANCE; RESEARCH REACTORS; URANIUM; Uranium Molybdenum Alloy Fuel

Citation Formats

C.R. Clark, G.A. Moore, J.F. Jue, B.H. Park, N.P. Hallinan, D.M. Wachs, and D.E. Burkes. Update on US High Density Fuel Fabrication Development. United States: N. p., 2007. Web.
C.R. Clark, G.A. Moore, J.F. Jue, B.H. Park, N.P. Hallinan, D.M. Wachs, & D.E. Burkes. Update on US High Density Fuel Fabrication Development. United States.
C.R. Clark, G.A. Moore, J.F. Jue, B.H. Park, N.P. Hallinan, D.M. Wachs, and D.E. Burkes. Thu . "Update on US High Density Fuel Fabrication Development". United States. doi:. https://www.osti.gov/servlets/purl/911918.
@article{osti_911918,
title = {Update on US High Density Fuel Fabrication Development},
author = {C.R. Clark and G.A. Moore and J.F. Jue and B.H. Park and N.P. Hallinan and D.M. Wachs and D.E. Burkes},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Mar 01 00:00:00 EST 2007},
month = {Thu Mar 01 00:00:00 EST 2007}
}

Conference:
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  • Advanced Materials Fabrication Facilities at Argonne National Laboratory have been involved in development of LEU dispersion fuel for research and test reactors from the beginning of RERTR program. This paper presents development of technology of high density LEU dispersion fuel fabrication for full size plate type fuel elements. A brief description of Advanced Materials Fabrication Facilities where development of the technology was carried out is given. A flow diagram of the manufacturing process is presented. U-Mo powder was manufactured by the rotating electrode process. The atomization produced a U-Mo alloy powder with a relatively uniform size distribution and a nearlymore » spherical shape. Test plates were fabricated using tungsten and depleted U-7 wt.% Mo alloy, 4043 Al and Al-2 wt% Si matrices with Al 6061 aluminum alloy for the cladding. During the development of the technology of manufacturing of full size high density LEU dispersion fuel plates special attention was paid to meet the required homogeneity, bonding, dimensions, fuel out of zone and other mechanical characteristics of the plates.« less
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