Evaluation of depth-dose profiles in a water phantom at the BNCT facility at BINP

Abstract

In this study, we present depth-dose profiles measured with a water phantom at the boron neutron-capture therapy (BNCT) facility at Budker Institute of Nuclear Physics (BINP). The presented results demonstrate that the proposed design of radiation detector with an optical fiber readout, which includes three different sensors (the first based on a plastic scintillator enriched with boron, the second based on a simple plastic scintillator, and the third having no scintillator at all), enables measurement of neutron flux, as well as estimations of the dose induced by gamma rays. The results of simulations with the GEANT4 package demonstrated good agreement with the experimental data and can be used for further system improvement.

In Vivo Accelerator-Based Boron Neutron Capture Therapy for Spontaneous Tumors in Large Animals: Case Series

“…The neutron-beam shaping assembly and detailed characteristics of the beam, including the neutron spectra, fast neutron, and photon components are described in previous reports [ 83 , 84 , 85 , 86 , 87 ]. Based on previous experimental data and spatial distribution of the beam components [ 88 ], plus an NMC code developed at IBRAE RAS [ 89 ] to simulate particle transport by the Monte Carlo method, we calculated neutron spectra and absorbed-dose depth distribution in simulated tumor, skin, and surrounding tissues prior to BNCT sessions. The dose rates (irradiation intensity) for each proton beam energy are provided in Table 2 .…”

Dosimetry of Neutron Flow and Gamma-Radiation for two Neutron Beam Shaping Assembly at the VITA Facility using a Scintillator Detector

“…Полная поглощенная доза равна сумме четырех компонент доз. в воздухе или в водном фантоме [3], достигнут существенный прогресс в реализации метода мгновенной гамма-спектроскопии для измерения борной дозы in situ при проведении терапии [4] и предложен и реализован метод измерения азотной дозы [5].…”

Polymer-Stabilized Elemental Boron Nanoparticles for Boron Neutron Capture Therapy: Initial Irradiation Experiments

“…The accelerator was operated at a proton current of 1.725-1.812 mA and an energy of 2.032 MeV. Based on the irradiation settings and previously experimentally studied spatial distribution of the beam components [53], the irradiation fluences were calculated by the Monte Carlo method using an NMC code developed at the Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAS) [54]. The characteristics of the beam, its contamination with fast neutrons and photons, and the neutron spectra were similar to those described previously [51,53,55,56].…”

“…Based on the irradiation settings and previously experimentally studied spatial distribution of the beam components [53], the irradiation fluences were calculated by the Monte Carlo method using an NMC code developed at the Nuclear Safety Institute of the Russian Academy of Sciences (IBRAE RAS) [54]. The characteristics of the beam, its contamination with fast neutrons and photons, and the neutron spectra were similar to those described previously [51,53,55,56]. One milliampere-hour resulted in the following fluences: thermal neutrons-2.608 × 10 12 /cm 2 , epithermal neutrons-7.696 × 10 10 /cm 2 , fast neutrons-6.118 × 10 10 /cm 2 , and photons-7.201 × 10 11 /cm 2 , with the absorbed doses as follows: fast neutrons-0.314 Gy, photons-2.997 Gy.…”