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Detailed Destructive Post-Irradiation Examinations of Mixed Uranium and Plutonium Oxide Fuel

2010
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Release : 2010
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Book Synopsis Detailed Destructive Post-Irradiation Examinations of Mixed Uranium and Plutonium Oxide Fuel by :

Download or read book Detailed Destructive Post-Irradiation Examinations of Mixed Uranium and Plutonium Oxide Fuel written by . This book was released on 2010. Available in PDF, EPUB and Kindle. Book excerpt: 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 fuel's 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.

Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide

2022-09 Science
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Release : 2022-09
Genre : Science
Kind : eBook
Book Rating : 205/5 ( reviews)

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Book Synopsis Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide by : Masato Kato

Download or read book Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide written by Masato Kato. This book was released on 2022-09. Available in PDF, EPUB and Kindle. Book excerpt: "Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deeper understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, this book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors"--

Neutronics Benchmark of a MOX Assembly with Near-weapons-grade Plutonium

1998
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Release : 1998
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Book Synopsis Neutronics Benchmark of a MOX Assembly with Near-weapons-grade Plutonium by :

Download or read book Neutronics Benchmark of a MOX Assembly with Near-weapons-grade Plutonium written by . This book was released on 1998. Available in PDF, EPUB and Kindle. Book excerpt: One of the proposed ways to dispose of surplus weapons-grade plutonium (Pu) is to irradiate the high-fissile material in light-water reactors in order to reduce the Pu enrichment to the level of spent fuels from commercial reactors. Considerable experience has been accumulated about the behavior of mixed-oxide (MOX) uranium and plutonium fuels for plutonium recycling in commercial reactors, but the experience is related to Pu enrichments typical of spent fuels quite below the values of weapons-grade plutonium. Important decisions related to the kind of reactors to be used for the disposition of the plutonium are going to be based on calculations, so the validation of computational algorithms related to all aspects of the fuel cycle (power distributions, isotopics as function of the burnup, etc.), for weapons-grade isotopics is very important. Analysis of public domain data reveals that the cycle-2 irradiation in the Quad cities boiling-water reactor (BWR) is the most recent US destructive examination. This effort involved the irradiation of five MOX assemblies using 80 and 90% fissile plutonium. These benchmark data were gathered by General Electric under the sponsorship of the Electric Power Research Institute. It is emphasized, however, that global parameters are not the focus of this benchmark, since the five bundles containing MOX fuels did not significantly affect the overall core performance. However, since the primary objective of this work is to compare against measured post-irradiation assembly data, the term benchmark is applied here. One important reason for performing the benchmark on Quad Cities irradiation is that the fissile blends (up to 90%) are higher than reactor-grade and, quite close to, weapons-grade isotopics.

Passive Nondestructive Assay of Nuclear Materials

1991 Non-destructive testing
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Author :
Release : 1991
Genre : Non-destructive testing
Kind : eBook
Book Rating : 247/5 ( reviews)

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Book Synopsis Passive Nondestructive Assay of Nuclear Materials by : Doug Reilly

Download or read book Passive Nondestructive Assay of Nuclear Materials written by Doug Reilly. This book was released on 1991. Available in PDF, EPUB and Kindle. Book excerpt:

Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors

2013-06-29 Technology & Engineering
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Release : 2013-06-29
Genre : Technology & Engineering
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Book Rating : 889/5 ( reviews)

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Book Synopsis Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors by : E.R. Merz

Download or read book Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors written by E.R. Merz. This book was released on 2013-06-29. Available in PDF, EPUB and Kindle. Book excerpt: MOX fuel, a mixture of weapon-grade plutonium and natural or depleted uranium, may be used to deplete a portion of the world's surplus of weapon-grade plutonium. A number of reactors currently operate in Europe with one-third MOX cores, and others are scheduled to begin using MOX fuels in both Europe and Japan in the near future. While Russia has laboratory-scale MOX fabrication facilities, the technology remains under study. No fuels containing plutonium are used in the U.S. The 25 presentations in this book give an impressive overview of MOX technology. The following issues are covered: an up to date report on the disposition of ex-weapons Pu in Russia; an analysis of safety features of MOX fuel configurations of different reactor concepts and their operating and control measures; an exchange of information on the status of MOX utilisation in existing power plants, the fabrication technology of various MOX fuels and their behaviour in practice; a discussion of the typical national approaches by Russia and the western countries to the utilisation of Pu as MOX fuel; an introduction to new ideas, enhancing the disposition option of MOX fuel exploitation and destruction in existing and future advanced reactor systems; and the identification of common research areas where defined tasks can be initiated in cooperative partnership.

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