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Determination of plutonium in human urine

Description: Report is made of chemical procedures for determination of plutonium in human urine. The procedures are provided in outline form and statistical methods are provided for interpretation of the results.
Date: August 14, 1947
Creator: Langham, W. H.
Partner: UNT Libraries Government Documents Department

Highlights of GE-NMPO research (CY 1964). Part B

Description: Research on materials and components for high-temperature reactors is summarized. The work is centered on studies of substoichiometric urania and urania solid solutions above 1800 deg C and their compatibility with refractory metals; development of refractory-metal fuel element materials capable of operation above 1800 deg C in nonoxidizing atmospheres; development of reactor control, reflector, and shield materials, stabilization of UO/sub 2/ in ceramic fuel elements to extend high-temperature highburnup capabilities; stability of high-melting carbides and borides in high-temperature gaseous environments; and coated-fuel particle development and evaluation. (JRD)
Date: March 1, 1965
Partner: UNT Libraries Government Documents Department

HIGH-TEMPERATURE RESEARCH ON CARBIDES FOR FUEL AND STRUCTURAL APPLICATIONS.

Description: High temperature physico-chemical properties of refractory carbides for fuel and structural use were determined. Density and phases of vacuum hot pressed HfC, TaC, and ZrC are tabulated and the diffusion coefficients, lattice parameters, and thermodynamic properties of TaC and UC are given. (F.S.)
Date: October 31, 1969
Creator: White, J.F. & Juenke, E.F.
Partner: UNT Libraries Government Documents Department

Pu, U redistribution in (U,Pu)O/sub 2/ fuels by temperature gradients

Description: A predictive model of the time-dependent evolution of radial Pu/U + Pu gradients in operating nonmolten mixed oxide fuels is being developed. This model is based on preferential evaporation-condensation and vapor transport of metal-bearing species either along cracks and porosity channels within the fuel or inside closed pores migrating up the temperature gradient; equilibrium thermodynamics are applied to calculate the continually changing vapor composition over the hot fuel. Predictions of the model are used in combination with recent in-pile experimental data (from nonmolten mixed oxide fuel pins irradiated in EBR-II from 0.2 to about 11 at. % burnup at varying powers) to delineate the key parameters in radial actinide redistribution. A correlation between fuel stoichiometry (O-to-Pu ratio) and the degree of redistribution (described by an enrichment factor ..gamma../sub Pu/) identified, however, the degree of restructuring of the fuel - as determined by the peak linear power rating, time at this power, and the initial fuel density - also has a strong influence on the final value of ..gamma../sub Pu/. Certain kinetic features of the process and intended modifications to the present model are discussed, and evidence for axial actinide vapor transport in an irradiated annular fuel is also presented.
Date: August 1, 1972
Creator: Adamson, M.G. & Aitken, E.A.
Partner: UNT Libraries Government Documents Department