Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 110 / Number 2
W. L. Dunn, A. M. Yacout, F. O′Foghludha
Nuclear Science and Engineering
Volume 110 / Number 2 / February 1992 / Pages 134-156
Format:electronic copy (download)
Gamma-ray and neutron dose-equivalent buildup factors are calculated for six common shielding materials in a point-source, infinite-slab, point-detector geometry using a decomposition of the solution to the transport problem into single- and multiple-scatter components. A rigorous solution for the single-scatter component is constructed and a Monte Carlo model for the multiple-scatter component is employed. Simplified models are fit to the calculated buildup factors as functions of slab thickness and source-detector separation, and model constants are evaluated for each of several source energies. Single-scatter and total slab buildup factors are presented, both in tabular form and in graphs that also show the fitted models, for six materials. The models are demonstrated for a sample problem.
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