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The monoenergetic steady-state integral neutron transport equation is solved analytically for several simple source configurations for pure absorbers. Specifically, the scalar neutron flux, phi(r), is derived for configurations in cartesian geometry representing the point, infinite line, infinite plane, finite line, infinite ribbon, finite ribbon, infinite tube, and finite box sources. Some of these configurations (point, infinite line, and infinite ribbon sources) were investigated previously by Case, deHoffmann and Placzek and are reviewed here for completeness. The others are more complex and represent new analytic solutions against which multidimensional numerical transport calculational codes may be tested. (auth

Analytic transport theory solutions for steady sources in pure absorbers