Abstract
A neutronic study of an accelerator-based neutron irradiation facility (ANIF) for boron neutron capture therapy (BNCT) was performed using three-dimensional Monte Carlo transport calculations. The major components of the ANIF are a radio-frequency quadrupole proton accelerator, a /sup 7/Li target, and a moderator assembly. Neutrons are generated by bombarding the /sup 7/Li target with 2.5-MeV protons. The neutrons emerging from the /sup 7/Li target are too energetic to be used for BNCT and must therefore be moderated. Calculations show that, among all materials for the ANIF, beryllia (BeO) and heavy water (D/sub 2/O) are the best moderators. Between them, beryllia provides better neutron spectra, but D/sub 2/O gives higher neutron intensities. Adding alumina (Al/sub 2/O/sub 3/) to D/sub 2/O improves the neutron spectra, but it also increases gamma-ray contamination.
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