Nuclear Science and Engineering / Volume 13 / Number 2 / June 1962 / Pages 190-196
Technical Paper / dx.doi.org/10.13182/NSE62-A26147
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The time and speed independent neutron transport equation in its integral form is applied to the calculation of the disturbed neutron flux in the vicinity of neutron detectors. The method is also applied to the calculation of the average flux in a two-detector system where the detectors are close enough to interact with each other. Hand methods of solving the integral equations are developed and shown to give results in good agreement with more accurate numerical methods of solving the integral equations.