Author: Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 112
Book Description
The Development and Testing of the UO2 Fuel Element System
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
Author: W. W. BrownCritical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices
Author: Summary Report
Author: Reactor Irradiation of Uranium-impregnated Graphite at 1500°C to 10% Burnup
Author: P. J. PetersonPublisher:
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
Author: G. Rolland ColePublisher:
ISBN:
Category : Irradiation
Languages : en
Pages : 36
Book Description
Graphite Corrosion Studies for the Ultra High Temperature Reactor Experiment
Author: Peter Gordon SalgadoPublisher:
ISBN:
Category : Gas cooled reactors
Languages : en
Pages : 44
Book Description
Metallography of Irradiated UO2-containing Fuel Elements
Author: W. K. BarneyPublisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 64
Book Description
Symposium on Powder Packed Uranium Dioxide Fuel Elements
Author: Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 204
Book Description
Radiation Behavior of Metallic Fuels for Sodium Graphite Reactors
Author: B. R. HaywardPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 40
Book Description