Pre-irradiation data for the zirconium-uranium dioxide cermet fuel and the assembled fuel elements
Author: J. L. Conversi
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Published: 1969
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Author: J. L. Conversi
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Published: 1969
Total Pages: 0
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DOWNLOAD EBOOKAuthor: J. D. Craigie
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Published: 1969
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DOWNLOAD EBOOKAuthor: R. J. Chenier
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Published: 1967
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DOWNLOAD EBOOKAuthor: K. D. Cotnam
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Published: 1967
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DOWNLOAD EBOOKAuthor: J. D. Craigie
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Published: 1966
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DOWNLOAD EBOOKAuthor: G. K. Wong
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Published: 1963
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DOWNLOAD EBOOKAuthor: J. D. Craigie
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Published: 1969
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DOWNLOAD EBOOKAuthor: K. D. Cotnam
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Published: 1967
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DOWNLOAD EBOOKAuthor: L. R. Bourque
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Published: 1979
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Published: 1986
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DOWNLOAD EBOOKUranium-Plutonium-Zirconium metal fuel irradiation tests to support the ANL Integral Fast Reactor concept are discussed. Satisfactory performance has been demonstrated to 2.9 at.% peak burnup in three alloys having 0, 8, and 19 wt % plutonium. Fuel swelling measurements at low burnup in alloys to 26 wt % plutonium show that fuel deformation is primarily radial in direction. Increasing the plutonium content in the fuel diminishes the rate of fuel-cladding gap closure and axial fuel column growth. Chemical redistribution occurs by 2.1 at.% peak burnup and generally involves the inward migration of zirconium and outward migration of uranium. Fission gas release to the plenum ranges from 46% to 56% in the alloys irradiated to 2.9 at.% peak burnup. No evidence of deleterious fuel-cladding chemical or mechanical interaction was observed.