In Pile-fission Gas Release and Swelling of UO 2 Fuel in Light Water Reactor PDF Download
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Author: Moustafa S. El-Koliel
Publisher:
ISBN:
Category :
Languages : en
Pages : 25
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Book Description
Author: Moustafa S. El-Koliel
Publisher:
ISBN:
Category :
Languages : en
Pages : 25
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Book Description
Author: Moustafa S. El-Koliel
Publisher:
ISBN:
Category :
Languages : en
Pages : 25
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Book Description
Author: Ralph O. Meyer
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 78
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Book Description
Author:
Publisher: Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development
ISBN:
Category : Science
Languages : en
Pages : 572
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Book Description
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: Gilbert E. Raines
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 46
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Author: JB. Melehan
Publisher:
ISBN:
Category : Complex compounds
Languages : en
Pages : 10
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Book Description
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: W. B. Cottrell
Publisher:
ISBN:
Category : Nuclear merchant ships
Languages : en
Pages : 148
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 14
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Book Description
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:
Publisher:
ISBN:
Category :
Languages : en
Pages : 32
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Book Description
Author: James B. Melehan
Publisher:
ISBN:
Category : Fission gases
Languages : en
Pages : 60
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Book Description
