Abstract
A study was made of the dose distributions and of the differential neutron energy spectra across the exit face of iron slabs of 6, 9 and 12 inch thickness exposed to an isotropic broad spectrum neutron source (Am-Be). A comparison was presented of the dose values observed with Hurst-type proportional counters and those calculated with the Monte Carlo codes 05R and Morse. The 05R program utilized the DNA 4124 cross-section set as point cross-sections while Morse utilized a set of troup-transfer cross-sections generated from the DNA 4124 set with the code Supertog. The results show a marked dependence on the representation of the cross-section sets. Detailed comparisons of calculated and measured emergent neutron spectra were also made. The spectra were measured with an NE213 scintillation spectrometer which was calibrated for use with the Ferdor unfolding code. In addition to the Monte Carlo calculations, the Anisn one-dimensional discrete ordinate code was used for a S16-P8 calculation with the same group transfer cross-section set used with Morse.
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