FORMULATION OF RADIATION TRANSPORT SOLUTIONS FOR SHIELDING APPLICATIONS, INCLUDING INTEGRAL TRANSFORM METHODS, MATRIX TECHNIQUES, AND ASYMPTOTIC APPROXIMATIONS.
Technical rept. for 1 Oct 63-30 Sep 64,
GENERAL DYNAMICS/FORT WORTH TEX NUCLEAR AEROSPACE RESEARCH FACILITY
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The objective of this study is to develop new and improved computational models for the determination of radiation intensity behind bulk shields and to provide further insight into radiation transport phenomena. A study of integral transform methods as applied to the neutron transport equation in finite geometrics under the spherical harmonics formulation is presented, representative problems are treated in slab, spherical, and cylindrical geometries. A matrix-integral-operator solution in slab geometry is included. The results of a study of an asymptotic method of obtaining angular distributions behind bulk shields are presented and the problem of electron transport in the 1- to 5-Mev range is discussed. Author