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, 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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