Fluence and dose measurements for an accelerator neutron beam |
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Authors: | Z. Liu S.H. Byun F.E. McNeill C.E. Mothersill C.B. Seymour W.V. Prestwich |
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Affiliation: | Medical Physics and Applied Radiation Sciences Department, McMaster University, Hamilton, ON, Canada L8S 4K1 |
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Abstract: | The 3 MV Van de Graaff accelerator at McMaster University accelerator laboratory is extended to a neutron irradiation facility for low-dose bystander effects research. A long counter and an Anderson-Braun type neutron monitor have been used as monitors for the determination of the total fluence. Activation foils were used to determine the thermal neutron fluence rate (around 106 neutrons s−1). Meanwhile, the interactions of neutrons with the monitors have been simulated using a Monte Carlo N Particle (MCNP) code. Bystander effects, i.e. damage occurring in cells that were not traversed by radiation but were in the same radiation environment, have been well observed following both alpha and gamma irradiation of many cell lines. Since neutron radiation involves mixed field (including gamma and neutron radiations), we need to differentiate the doses for the bystander effects from the two radiations. A tissue equivalent proportional counter (TEPC) filled with propane based tissue equivalent gas simulating a 2 μm diameter tissue sphere has been investigated to estimate the neutron and gamma absorbed doses. A photon dose contamination of the neutron beam is less than 3%. The axial dose distribution follows the inverse square law and lateral and vertical dose distributions are relatively uniform over the irradiation area required by the biological study. |
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Keywords: | Monte Carlo N Particle Photon dose Neutron dose Dose rate Count rate Fluence rate Dose distribution |
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