The Development and Testing of the UO2 Fuel Element System

The Development and Testing of the UO2 Fuel Element System PDF Author:
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 112

Book Description


Exponential Experiments with Graphite Lattices Containing Multirod Slightly Enriched Uranium Fuel Clusters

Exponential Experiments with Graphite Lattices Containing Multirod Slightly Enriched Uranium Fuel Clusters PDF Author: W. W. Brown
Publisher:
ISBN:
Category : Graphite
Languages : en
Pages : 50

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Summary Report

Summary Report PDF Author:
Publisher:
ISBN:
Category : Graphite
Languages : en
Pages : 142

Book Description


Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices

Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 44

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Reactor Irradiation of Uranium-impregnated Graphite at 1500°C to 10% Burnup

Reactor Irradiation of Uranium-impregnated Graphite at 1500°C to 10% Burnup PDF Author: P. J. Peterson
Publisher:
ISBN:
Category : Graphite as fuel
Languages : en
Pages : 50

Book Description
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.

Preliminary Irradiation of Fused UO2

Preliminary Irradiation of Fused UO2 PDF Author: G. Rolland Cole
Publisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 36

Book Description


Symposium on Effects of Irradiation on Fuel and Fuel Elements

Symposium on Effects of Irradiation on Fuel and Fuel Elements PDF Author: W. D. Manly
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 114

Book Description


Effects of Irradiation on Bulk UO2

Effects of Irradiation on Bulk UO2 PDF Author: John D. Eichenberg
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 198

Book Description


Metallography of Irradiated UO2-containing Fuel Elements

Metallography of Irradiated UO2-containing Fuel Elements PDF Author: W. K. Barney
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 64

Book Description


Nuclear Characteristics of UO2 and ThO2 Fuel for Phase III NPR Operation

Nuclear Characteristics of UO2 and ThO2 Fuel for Phase III NPR Operation PDF Author: G. J. Busselman
Publisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 122

Book Description