Abstract
A detailed knowledge of the thermal flux distribution in a phantom is important for modeling the boron dose in Boron Neutron Capture Therapy (BNCT) and augmented boron dose in Fast Neutron Therapy (FNT). Monte Carlo simulations of the thermal neutron flux with MCNP code need experimental verification, moreover such simulations in the case of FNT are difficult due to the lack of neutron cross-sections information for high energies of neutrons. In this circumstances a separate measurement of the thermal neutron flux is required. This measurement is complicated by a presence of low LET radiation in a mixed neutron-gamma field of a nuclear reactor or accelerator beam.
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