Design of moderator and multiplier systems for D–T neutron source in BNCT

Boron Neutron Capture Therapy (BNCT) is an outstanding way to treat Glioblastoma Multiforme. Epithermal neutrons with energy from 1 eV to 10 keV represent the most effective range for brain tumor therapy. In this research we have focused on 3H(d, n) 4He reaction as a neutron source using Cock Craft...

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Bibliographic Details
Published in:Annals of nuclear energy 2009-08, Vol.36 (8), p.1100-1102
Main Authors: Eskandari, M.R., Kashian, S.
Format: Article
Language:English
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Summary:Boron Neutron Capture Therapy (BNCT) is an outstanding way to treat Glioblastoma Multiforme. Epithermal neutrons with energy from 1 eV to 10 keV represent the most effective range for brain tumor therapy. In this research we have focused on 3H(d, n) 4He reaction as a neutron source using Cock Craft Walton accelerator. High neutron yield with 14.1 MeV energy can be generated via accelerating a deuteron beam with 110 keV energy. A Monte Carlo simulation code (MCNP4C) was used to design the D–T source. Pb and 238U are suggested as neutron multipliers; AlF 3 and BeO as a moderator and reflector, respectively. An Al layer is used for decreasing the ratio of fast to total neutron fluxes. Epithermal neutron flux in the suggested system is 10 8 n/cm 2 s and is a suitable flux for BNCT applications. Finally the suggested configuration is compared to the most recent works and it is shown that the proposed configuration works better.
ISSN:0306-4549
1873-2100
DOI:10.1016/j.anucene.2009.05.005