Irradiation Testing of Plutonium-uranium Oxide Nuclear Fuel
Author : J. L. Bates
Publisher :
Page : 56 pages
File Size : 21,50 MB
Release : 1959
Category : Mixed oxide fuels (Nuclear engineering)
ISBN :
Author : J. L. Bates
Publisher :
Page : 56 pages
File Size : 21,50 MB
Release : 1959
Category : Mixed oxide fuels (Nuclear engineering)
ISBN :
Author : Francisco Cruz Dimayuga
Publisher : Chalk River, Ont., Canada : Fuel Development Branch, Chalk River Laboratories
Page : 15 pages
File Size : 13,40 MB
Release : 1997
Category : Irradiation
ISBN : 9780660171029
Author : International Atomic Energy Agency
Publisher : IAEA
Page : 100 pages
File Size : 48,78 MB
Release : 2006
Category : Business & Economics
ISBN :
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 :
Publisher : Allied Publishers
Page : 738 pages
File Size : 21,59 MB
Release : 2004
Category : Nuclear fuels
ISBN : 9788177646085
Papers presented at the International Conference on Characterisation and Quality Control of Nuclear Fuels, held at Hyderabad in 2002.
Author :
Publisher :
Page : pages
File Size : 16,75 MB
Release : 2010
Category :
ISBN :
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.
Author : J. L. Bates
Publisher :
Page : 46 pages
File Size : 32,63 MB
Release : 1959
Category : Nuclear fuel elements
ISBN :
Author : Pierre Zaleski
Publisher :
Page : 602 pages
File Size : 30,68 MB
Release : 1976
Category : Nuclear energy
ISBN :
Author : Brian R. T. Frost
Publisher : Elsevier
Page : 284 pages
File Size : 20,5 MB
Release : 2013-10-22
Category : Technology & Engineering
ISBN : 1483155250
Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overview of nuclear reactors and fuel elements, as well as fuel element design and development based on the reactor operator's approach, materials scientist's approach, and interdisciplinary approach. The reader is then introduced to different types of nuclear fuels and their irradiation behavior, considerations for using cladding and duct materials in fuel element design and development, and fuel element design and modeling. The chapters that follow focus on the testing of fuel element performance, experimental techniques and equipment for testing fuel element designs, and the performance of fuels for water reactors. Fuel elements for gas-cooled reactors, fast reactors, and research and test reactors are also described. The book concludes with an assessment of unconventional fuel elements. This book will be useful to fuel element technologists as well as materials scientists and engineers.
Author :
Publisher :
Page : 114 pages
File Size : 12,32 MB
Release : 1960
Category : Government contractors
ISBN :
Author :
Publisher :
Page : 12 pages
File Size : 34,18 MB
Release : 1983
Category :
ISBN :