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Proceedings Paper

Spectral tailoring study on neutron irradiation facility for BNCT
Author(s): Otohiko Aizawa
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Paper Abstract

In this paper we have calculated the space-dependent neutron energy spectra by changing the configuration of filter and reflector materials between the reactor core and the irradiation port. The dimensions used in this calculation are 120 cm in diameter and 250cm in depth for R-Z geometry after due consideration of the neutron irradiation facility at the Musashi reactor. The filter and reflector materials used are carbon, aluminum, alumina, silicon, iron, lead, bismuth, polyethylene and lithium-fluoride. The calculations have been performed by using the Monte Carlo code and the 2D discrete-ordinate transport code adopting the S12 and P3 approximations.

Paper Details

Date Published: 27 February 1997
PDF: 4 pages
Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); doi: 10.1117/12.267955
Show Author Affiliations
Otohiko Aizawa, Musashi 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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