The equivalent roles of the time and lethargy variables for the following infinite plane geometry transport problems are shown: (1) monoenergetic time-dependent neutron transport in an isotropically scattering homogeneous medium; (2) neutrons slowing down assuming a particular scattering kernel in a medium with constant cross section. This relationship is used to generate an analytic benchmark solution to which the S//N multigroup transport code ANISN can be compared. These results are relevant to nuclear reactors.
|Original language||English (US)|
|Number of pages||5|
|State||Published - Jan 1 1977|
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