An angle distribution of a neutron dose behind randomly inhomogeneous polyethylene slab

Calculational studies on peculiarities of forming reactor neutron dose in incidental polyethylene medium are carried out, wherein substance distribution is described by binomial law. Applicability of effective cross section for neutron flux weakening in incidental - heterogeneous medium is shown by comparison of calculations by the Monte Carlo method and experiments on model cylindrical assemblies. Simple analytical expression for evaluations of neutron dose angular distribution behind the plane hydrogenous heterogeneous barrier is obtained basing on the calculational results. 15 refs., 3 figs., 2 tabs