Predicted Radiation Output from Plutonium and Uranium Oxide

摘要

Los Alamos developed software packages MISC and SOURCES were used to create gamma and neutron source terms for several forms of special nuclear material (SNM) In conjunction with combinatorial solid geometry models of the oxide material, such intrinsic radiation (INRAD) source definitions were the basis for transport simulations using the Monte Carlo code MCNP~(™) Calculations of photon and neutron output were produced m terms of exposure- and dose-rate maps, respectively, for operational considerations in advance of several detector measurement campaigns Synthetic radiographs were made of the plutonium oxide powder geometry to better estimate the unknown material density. This paper describes modeling and prediction efforts and ongoing comparisons with measurement Beside geometry, accurate modeling requires knowledge of the material age, chemical/isotopic composition and density. Plutonium oxide; uranium oxide; intrinsic radiation (INRAD); leakage; radiation transport