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Abstract

For treatment of deep-seated tumors, high epithermal neutron beam flux with minimal contamination from gamma rays as well as thermal and fast neutrons is desired for boron neutron capture therapy (BNCT). For this purpose, a beam shaping assembly (BSA) was designed to provide an epithermal neutron beam with little contamination. The Monte Carlo N-Particle code was employed for a design rendering epithermal neutron flux of $5.63 \times 10^{9}$ n cm⁻² s⁻¹. Different mesh sizes were implemented to improve the accuracy of the computed dose map and in-phantom parameter in the head phantom and tumor. In the present work, the material test reactor (MTR) with consideration of the general specifications of the Tehran Research Reactor (TRR) was considered as a neutron source. The MAKXSF auxiliary processing code was used to calculate temperature of every part of the research reactor core.

Keywords

BNCT BSA design dose mapping MCNP5 MAKXSF

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Dose mapping simulation and BSA design for improving the dosimetry accuracy for research reactor BNCT

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