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Proceedings Paper

Errors caused by energy grouping of Monte Carlo method for neutron transmission through thin assembly
Author(s): Hiroshi Sekimoto; Tsuyoshi Noura
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Paper 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.

Paper Details

Date Published: 27 February 1997
PDF: 4 pages
Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); doi: 10.1117/12.267958
Show Author Affiliations
Hiroshi Sekimoto, Tokyo Institute of Technology (Japan)
Tsuyoshi Noura, Tokyo Institute of Technology (Japan)


Published in SPIE Proceedings Vol. 2867:
International Conference Neutrons in Research and Industry
George Vourvopoulos, Editor(s)

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