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R. E. Maerker, F. J. Muckenthaler
Nuclear Science and Engineering | Volume 29 | Number 3 | September 1967 | Pages 444-454
Technical Paper | doi.org/10.13182/NSE67-A17293
Articles are hosted by Taylor and Francis Online.
Monte Carlo calculations, employing the albedo concept, have been carried out to determine the thermal-neutron flux distributions along the centerlines of a straight, a two-legged, and a three-legged square open concrete duct for a particularly demanding source geometry. The neutrons entering the duct were of thermal energy. The calculations used differential angular albedo data for concrete which have been reported previously. A comparison of the results of the calculations with those from a geometrically similar experiment shows good agreement and places on a firm foundation the concept of treating the thermal-neutron duct transmission problem as a reflection phenomenon at a point that is describable by the differential albedo properties of the walls.