Abstract
The newly developed j N method has been further extended to deal with multilayer slab systems with anisotropic scattering of neutrons. In the present article, the complete mathematical formalism for space-angle energy-time dependent neutron transport in slab geometry is given. The time moments of the neutron flux resulting from the incidence of an external delta function source can also be obtained in a simple analytical form similar to the stationary flux and calculated easily with a reasonable accuracy. By the use of this theory, an optimization study of moderators installed in pulsed reactors or accelerator pulsed reactors is carried out with respect to the heterogeneous poisoning. The thermal neutron yield leaking from a water slab and the variance of the leakage time distribution are obtained. The results have shown that heterogeneous poisoning can give a gam m the figure-of-merit for accelerator pulsed reactors by a factor of more than 3 compared to the unpoisoned value.
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