Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 161 / Number 1 / Pages 49-67
Nuclear Science and Engineering / Volume 161 / Number 1 / Pages 49-67
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This work presents the development of an analytical approximation solution for a space-time-dependent neutron transport problem in a one-dimensional system consisting of a homogenized medium with a central external source with Green's functions. The delayed neutron production is implemented with the multiple-scale expansion method. Qualitative results for a given system are analyzed and an example of the use for the analysis of accelerator-driven systems is given.
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