Accession Number : AD0484683

Title :   THE EFFECT OF NUCLEAR RADIATION ON DISPERSION FUEL MATERIALS,

Corporate Author : BATTELLE MEMORIAL INST COLUMBUS OH RADIATION EFFECTS INFORMATION CENTER

Personal Author(s) : Kangilaski, M.

Report Date : 01 JAN 1966

Pagination or Media Count : 80

Abstract : A complete summary of the irradiation performance of the various fuel materials dispersed in different matrices has been collected. The irradiation performance of the following dispersions is discussed in the report: BeO-UO2, BeO-UO2-ThO2, Al2O3-UO2, MgO-UO2, UO2, UC, UC2, and *U, Th)C2 U3O8 glass, and UAl3 dispersed in aluminum; UO2, UC, and UN dispersed in stainless steel; UO2 and UO2-Y2O3 dispersed in nickel-chromium alloys; UO2 dispersed in niobium, UO2 dispersed in molybdenum, UO2, UN, and UC dispersed in tungsten. The data which is summarized includes percentage of fuel by weight and volume, specimen shape and size, fuel particle size, cladding material and clad thickness, irradiation temperature, heat generation rates, irradiation times, fuel burnup, fission gas release, dimensional and density changes resulting from irradiation. (Author)

Descriptors :   (*REACTOR FUELS, OPTIMIZATION), (*CERAMIC MATERIALS, REACTOR FUELS), (*METALS, REACTOR FUELS), (*ALLOYS, REACTOR FUELS), BERYLLIUM, BERYLLIUM COMPOUNDS, OXIDES, URANIUM COMPOUNDS, THORIUM COMPOUNDS, ALUMINUM COMPOUNDS, MAGNESIUM COMPOUNDS, CARBIDES, GRAPHITE, ALUMINUM, STAINLESS STEEL, REFRACTORY METALS, NITRIDES, ELASTIC PROPERTIES, THERMAL CONDUCTIVITY, NEUTRONS, DAMAGE, RADIATION EFFECTS, IRON, SCATTERING.

Subject Categories : Fission Reactor Materials

Distribution Statement : APPROVED FOR PUBLIC RELEASE