Author: J. L. CrosthwaitePublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
Proposal for a high power density, uranium-graphite fuel irradiation in WR-1
Author: J. L. CrosthwaiteFinal proposal for the irradiation of a uranium-graphite fuel bundle in WR-1
Author: R. W. JonesPost-irradiation examination of the failed high power density uranium-graphite fuel experiment
Author: J. L. GrosthwaitePost-irradiation examination of a uranium-graphite fuel bundle irradiated in WR-1
Author: L. M. SwansonA preliminary proposal to irradiate a uranium-graphite fuel bundle in WR-1
Author: R. W. JonesReactor 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.
Final proposal for the irradiation of a zirconium-uranium fuel bundle in WR-1
Author: W. R. JonesPost-irradiation examination of high-power density uc fuel elements from WR-1
Author: M. L. SwansonA proposal to irradiate high power density tho2 fuel elements in the WR-1 reactor
Author: H. R. LeeNuclear Graphite
Author: R. E. NightingalePublisher: Academic Press
ISBN: 1483258483
Category : Technology & Engineering
Languages : en
Pages : 566
Book Description
Nuclear Graphite focuses on the development and uses of nuclear graphite, including machining practices, manufacture, nuclear properties and structure, radiation, and electrical resistance. The selection first discusses the applications of graphite in the nuclear industry, machining practices, and manufacture. Discussions focus on early, current, and future applications of graphite, impregnation, graphitization, purification, general machining techniques, and equipment and methods in the nuclear industry. The book then examines the structure and nuclear and properties of graphite. The text evaluates radiation-induced structural and dimensional changes; radiation effects on electrical and thermal properties; and radiation effects on mechanical properties. Topics include radiation effects on crystal structure, electrical resistance, thermoelectric power, magnetoresistance, coefficient of friction, irradiation under stress, and elastic moduli of nuclear graphite. The book also ponders on stored energy, annealing radiation effects, and gas-graphite systems. The selection is a dependable source of data for readers interested in the applications of nuclear graphite.