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Author : Moustafa S. El-Koliel
Publisher :
ISBN 13 :
Total Pages : 25 pages
Book Rating : 4.:/5 (84 download)
Download or read book In Pile-fission Gas Release and Swelling of UO2 Fuel in Light Water Reactors written by Moustafa S. El-Koliel and published by . This book was released on 1999 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher : Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development
ISBN 13 :
Total Pages : 572 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fission Gas Behaviour in Water Reactor Fuels written by and published by Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development. This book was released on 2002 with total page 572 pages. Available in PDF, EPUB and Kindle. Book excerpt: Communicates the results of an international seminar which reviewed recent progress in the field of fission gas behaviour in light water reactor fuel and sought to improve the models used in computer codes predicting fission gas release. State-of-the-art knowledge is presented for both uranium-oxide and mixed-oxide fuels loaded in water reactors.
Author :
Publisher : OECD Publishing
ISBN 13 :
Total Pages : 562 pages
Book Rating : 4.3/5 (91 download)
Download or read book Pellet-clad Interaction in Water Reactor Fuels written by and published by OECD Publishing. This book was released on 2005 with total page 562 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication sets out the findings of an international seminar, held in Aix-en-Provence, France in March 2004, which considered recent progress in the field of pellet-clad interaction in light water reactor fuels. It also reviews current understanding of relevant phenomena and their impact on the nuclear fuel rod under the widest possible conditions, and about both uranium-oxide and mixed-oxide fuels.
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Download or read book Fission Gas Induced Fuel Swelling in Low and Medium Burnup Fuel During High Temperature Transients. [PWR]. written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The behavior of light water reactor fuel elements under postulated accident conditions is being studied by the EG and G Idaho, Inc., Thermal Fuels Behavior Program for the Nuclear Regulatory Commission. As a part of this program, unirradiated and previously irradiated, pressurized-water-reactor type fuel rods were tested under power-cooling-mismatch (PCM) conditions in the Power Burst Facility (PBF). During these integral in-reactor experiments, film boiling was produced on the fuel rods which created high fuel and cladding temperatures. Fuel rod diameters increased in the film boiling region to a greater extent for irradiated rods than for unirradiated rods. The purpose of the study was to investigate and assess the fuel swelling which caused the fuel rod diameter increases and to evaluate the ability of an analytical code, the Gas Release and Swelling Subroutine - Steady-State and Transient (GRASS-SST), to predict the results.
Author : Gilbert E. Raines
Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.3/5 (91 download)
Download or read book In-pile Fission-gas-release Behavior of Alumina-coated UO2 Particles Irradiated to High Burnup written by Gilbert E. Raines and published by . This book was released on 1961 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : JB. Melehan
Publisher :
ISBN 13 :
Total Pages : 10 pages
Book Rating : 4.:/5 (125 download)
Download or read book In-Pile Fission-Gas Release from UO2 written by JB. Melehan and published by . This book was released on 1962 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: A program has been conducted and is continuing at Battelle Memorial Inst. under the sponsorship of the United States Atomic Energy Commission to study the release of fission gas from UO2 and to relate the release to material properties, both chemical and structural. Work in the program has involved the preparation and characterization of sintered polycrystalline and fused single-crystal UO2 samples, the construction of a beam-tube loop facility for the irradiation of the UO2 under controlled temperature and atmosphere, and the collection and analysis of released fission gases during irradiation. Irradiation experiments have been conducted in purified helium-hydrogen atmosphere at temperatures from 500 to 1500 F, with fission gases continuously collected and analyzed for krypton and xenon during irradiation of natural uranium specimens. Irradiation exposures of the specimens have been in the region of 1018 nvt.
Author : International Atomic Energy Agency
Publisher : IAEA
ISBN 13 :
Total Pages : 100 pages
Book Rating : 4.3/5 (91 download)
Download or read book Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 100 pages. 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 : Ralph O. Meyer
Publisher :
ISBN 13 :
Total Pages : 68 pages
Book Rating : 4.3/5 (91 download)
Download or read book Fission Gas Release from Fuel at High Burnup written by Ralph O. Meyer and published by . This book was released on 1978 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : W. B. Cottrell
Publisher :
ISBN 13 :
Total Pages : 148 pages
Book Rating : 4.:/5 (319 download)
Download or read book Fission-product Release from UO2 written by W. B. Cottrell and published by . This book was released on 1960 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 14 pages
Book Rating : 4.:/5 (684 download)
Download or read book Fission Gas Release from UO{sub 2+x} in Defective Light Water Reactor Fuel Rods written by and published by . This book was released on 1999 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: A simplified semi-empirical model predicting fission gas release form UO{sub 2+x} fuel to the fuel rod plenum as a function of stoichiometry excess (x) is developed to apply to the fuel of a defective LWR fuel rod in operation. The effect of fuel oxidation in enhancing gas diffusion is included as a parabolic dependence of the stoichiometry excess. The increase of fission gas release in a defective BWR fuel rod is at the most 3 times higher than in an intact fuel rod because of small extent of UO2 oxidation. The major enhancement contributor in fission gas release of UO{sub 2+x} fuel is the increased diffusivity due to stoichiometry excess rather than the higher temperature caused by degraded fuel thermal conductivity.
Author : Atomic Energy of Canada Limited
Publisher :
ISBN 13 :
Total Pages : 39 pages
Book Rating : 4.:/5 (622 download)
Download or read book Microstructure-Dependent Model For Fission Product Gas Release and Swelling in Uo2 Fuel written by Atomic Energy of Canada Limited and published by . This book was released on 1977 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. J. F. Notley
Publisher :
ISBN 13 :
Total Pages : 39 pages
Book Rating : 4.:/5 (158 download)
Download or read book A Microstructure-dependent Model for Fission Product Gas Release and Swelling in UO2 Fuel written by M. J. F. Notley and published by . This book was released on 1979 with total page 39 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : James B. Melehan
Publisher :
ISBN 13 :
Total Pages : 62 pages
Book Rating : 4.3/5 (91 download)
Download or read book In-pile Fission-gas Release from Uranium Carbide and Uranium Nitride written by James B. Melehan and published by . This book was released on 1964 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : M. H. Wood
Publisher :
ISBN 13 :
Total Pages : 46 pages
Book Rating : 4.:/5 (865 download)
Download or read book Modelling Fission Gas Release and Swelling in Fast Reactor Fuel Pins written by M. H. Wood and published by . This book was released on 1975 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : James B. Melehan
Publisher :
ISBN 13 :
Total Pages : 60 pages
Book Rating : 4.3/5 (91 download)
Download or read book Release of Fission Gases from UO2 During and After Irradiation written by James B. Melehan and published by . This book was released on 1963 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
Publisher :
ISBN 13 :
Total Pages : 32 pages
Book Rating : 4.3/5 (91 download)
Download or read book The Behavior of Fission-Gas in Fuels written by and published by . This book was released on 1965 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : R. D. Macdonald
Publisher :
ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (141 download)
Download or read book A proposal to measure the in-pile fission gas release from uo2 fuel elements containing graphite discs and blocks written by R. D. Macdonald and published by . This book was released on 1971 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
