Accession Number DE2013-1009918
Title Detailed Destructive Post-Irradiation of Mixed Uranium and Plutonium Oxide Fuel.
Publication Date 2013
Media Count 10p
Personal Author C. R. Hexel J. M. Giaquinto J. S. Delashmitt R. H. Ilgner R. R. Smith T. J. Keever
Abstract The United States Department of Energy (DOE) Fissile Materials Disposition Program (FMDP) is pursuing disposal of surplus weapons-usable plutonium by reactor irradiation as the fissile constituent of MOX fuel. Lead test assemblies (LTAs) have been irradiated for approximately 36 months in Duke Energy's Catawba-1 nuclear power plant (NPP). Per the mixed oxide (MOX) fuel topical report, approved by the U.S. Nuclear Regulatory Commission (NRC), destructive post-irradiation examinations (PIEs) are to be performed on second cycle rods (irradiated to an average burnup of approximately 45 GWd/MTHM). The Radiochemical Analysis Group (RAG) at Oak Ridge National Laboratory (ORNL) is currently performing the detailed destructive post-irradiation examinations (PIE) on four of the mixed uranium and plutonium oxide fuel rods. The analytical process involves dissolution of designated fuel segments in a shielded hot cell for high precision quantification of select fission products and actinide isotopes employing isotope dilution mass spectrometry (IDMS) among other analyses. The hot cell dissolution protocol to include the collection and subsequent alkaline fusion digestion of the fuels acid resistant metallic particulates will be presented. Although the IDMS measurements of the fission products and actinide isotopes will not be completed by the time of the 51st INMM meeting, the setup and testing of the HPLC chromatographic separations in preparation for these measurements will be discussed.
Keywords Actinide nuclei
Destructive testing
Fissile materials
Fuel rods
Hot cells
Irradiation
Isotope dilution
Liquid chromatography
Mass spectroscopy
Mixed oxide fuels
Nuclear power plants
Plutonium oxides
Post irradiation examination
Radiochemical analysis
Uranium


 
Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77I - Reactor Fuels & Fuel Processing
77H - Reactor Engineering & Nuclear Power Plants
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1323
Contract Number DE-AC05-00OR22725

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