27 February 1997 Errors caused by energy grouping of Monte Carlo method for neutron transmission through thin assembly
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Proceedings Volume 2867, International Conference Neutrons in Research and Industry; (1997) https://doi.org/10.1117/12.267958
Event: Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry, 1996, Crete, Greece
Abstract
The errors of the neutron spectra calculated by a multi- group Monte Carlo code were investigated by comparing the spectra with those by a continuous-energy Monte Carlo code for the transport of approximately MeV neutrons through graphite piles. When mono-directional neutrons impinge on a 10 cm thick pile, the transmission spectrum calculated with the multi-group code shows a violent oscillation caused by the truncation approximation of the Legendre series for group-transfer cross sections. The oscillations diminish and the spectrum obtained by the multi-group code tends to agree well with one by the continuous-energy code, when one or several of the following conditions are satisfied; 1) the neutron source is isotropic, 2) the thickness of the piles is large enough, 3) the detector locates in the pile.
© (1997) COPYRIGHT Society of Photo-Optical Instrumentation Engineers (SPIE). Downloading of the abstract is permitted for personal use only.
Hiroshi Sekimoto, Hiroshi Sekimoto, Tsuyoshi Noura, Tsuyoshi Noura, } "Errors caused by energy grouping of Monte Carlo method for neutron transmission through thin assembly", Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); doi: 10.1117/12.267958; https://doi.org/10.1117/12.267958
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