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Author : J. L. Bates
Release : 1959
Genre : Mixed oxide fuels (Nuclear engineering)
Kind : eBook
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Book Synopsis Irradiation Testing of Plutonium-uranium Oxide Nuclear Fuel by : J. L. Bates
Download or read book Irradiation Testing of Plutonium-uranium Oxide Nuclear Fuel written by J. L. Bates. This book was released on 1959. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Francisco Cruz Dimayuga
Release : 1997
Genre : Irradiation
Kind : eBook
Book Rating : 029/5 ( reviews)
Book Synopsis Status of Irradiation Testing and PIE of MOX (Pu-containing) Fuel by : Francisco Cruz Dimayuga
Download or read book Status of Irradiation Testing and PIE of MOX (Pu-containing) Fuel written by Francisco Cruz Dimayuga. This book was released on 1997. Available in PDF, EPUB and Kindle. Book excerpt:
Author : International Atomic Energy Agency
Release : 2006
Genre : Business & Economics
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Book Synopsis Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors by : International Atomic Energy Agency
Download or read book Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors written by International Atomic Energy Agency. This book was released on 2006. Available in PDF, EPUB and Kindle. Book excerpt: The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.
Author :
Release : 2004
Genre : Nuclear fuels
Kind : eBook
Book Rating : 085/5 ( reviews)
Book Synopsis Characterisation and Quality Control of Nuclear Fuels by :
Download or read book Characterisation and Quality Control of Nuclear Fuels written by . This book was released on 2004. Available in PDF, EPUB and Kindle. Book excerpt: Papers presented at the International Conference on Characterisation and Quality Control of Nuclear Fuels, held at Hyderabad in 2002.
Author :
Release : 2010
Genre :
Kind : eBook
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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.
