Proposal for a high power density, uranium-graphite fuel irradiation in WR-1
Author : J. L. Crosthwaite
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Page : 0 pages
File Size : 17,63 MB
Release : 1967
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Author : J. L. Crosthwaite
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Page : 0 pages
File Size : 17,63 MB
Release : 1967
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Author : R. W. Jones
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Page : 0 pages
File Size : 19,88 MB
Release : 1966
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Author : J. L. Grosthwaite
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Page : 0 pages
File Size : 37,79 MB
Release : 1968
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Author : L. M. Swanson
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Page : 0 pages
File Size : 15,73 MB
Release : 1968
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Author : R. W. Jones
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Page : 0 pages
File Size : 46,51 MB
Release : 1966
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Author : P. J. Peterson
Publisher :
Page : 50 pages
File Size : 41,99 MB
Release : 1963
Category : Graphite as fuel
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Two type-AUC graphite fuel elements loaded by solution impregnation to an average concentration of 0.115 g/cc of 93.13% enriched U converted to UC and UC2 were irradiated at temperatures of about 1500 deg C to a 10.2% maximum burnup, corresponding to an irradiation level of 219 kwh/cc or 2.45 x 101 fissions/cc of fuel element. Post-irradiation measurements of the elements showed dimensional changes of -4.3 and -4.8% with the grain, and --0.8 to -2.5% across the grain. Weight losses were 3.2 and 5.1% for the individual elements with approximately 11% of the total U being lost from the elements. With-the- grain thermal conductivity at nominal room temperature was reduced by a factor of approximates 7 and electrical conductivities by factors of 3.4 to 8.3, also at room temperature. Impact strength appeared to be somewhat improved by irradiation. Migration of U within the element was detected by radiographic density observations but not evaluated quantitatively. As anticipated, fission product release was high.
Author : W. R. Jones
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Page : 0 pages
File Size : 28,74 MB
Release : 1966
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Author : M. L. Swanson
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Page : 0 pages
File Size : 37,83 MB
Release : 1977
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Author : H. R. Lee
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Page : 0 pages
File Size : 33,14 MB
Release : 1971
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Author : J. H. W. Simmons
Publisher : Elsevier
Page : 264 pages
File Size : 13,10 MB
Release : 2013-10-22
Category : Technology & Engineering
ISBN : 1483186490
Nuclear Energy, Volume 102: Radiation Damage in Graphite provides a general account of the effects of irradiation on graphite. This book presents valuable work on the structure of the defects produced in graphite crystals by irradiation. Organized into eight chapters, this volume begins with an overview of the description of the methods of manufacturing graphite and of its physical properties. This text then presents details of the method of setting up a scale of irradiation dose. Other chapters consider the effect of irradiation at a given temperature on a physical property of graphite. This book discusses as well the changes in dimensions produced by irradiation and the effects of irradiation on the mechanical properties of graphite. The final chapter deals with the accumulation of stored energy, which is one of the main problems caused by the irradiation of graphite in nuclear reactors. This book is a valuable resource for physicists and chemical physicists.