<p>Fast-neutron fluence rate contributes to absorbed dose in reactor-based Gd-neutron capture therapy and must be quantified for reliable dosimetry. In this work, fast-neutron measurements were performed in the epithermal horizontal channel of the VVR-SM reactor using an SDMF-1608.PRO mobile dosimeter-spectrometer with digital neutron-gamma discrimination and detector-response-based spectral reconstruction. Measurements were obtained in air at 270&#xa0;cm from the collimator window and with aluminum and boron-paraffin attenuators placed at the collimator exit. Detector-reconstructed integral fast-neutron fluence rates of the order of 10<sup>4</sup>–10<sup>5</sup> n/(cm^2·s) were obtained, and an attenuation-based procedure was used to estimate the corresponding fluence rate at the collimator exit. The results show that fast neutrons constitute a non-negligible dose component in the epithermal beam. At the same time, the attenuation-based reconstruction should be regarded as approximate, especially for thick boron-paraffin shielding, and is best interpreted together with Monte Carlo transport calculations.</p>

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Measurements of fast neutron fluence rate for dose assessment in Gd-neutron capture therapy at the VVR-SM reactor

  • D. О. Yuldashev,
  • G. А. Kulabdullaev,
  • G. А. Abdullaeva,
  • A. A. Kim,
  • O. R. Tojiboev,
  • F. Kh. Ergashev

摘要

Fast-neutron fluence rate contributes to absorbed dose in reactor-based Gd-neutron capture therapy and must be quantified for reliable dosimetry. In this work, fast-neutron measurements were performed in the epithermal horizontal channel of the VVR-SM reactor using an SDMF-1608.PRO mobile dosimeter-spectrometer with digital neutron-gamma discrimination and detector-response-based spectral reconstruction. Measurements were obtained in air at 270 cm from the collimator window and with aluminum and boron-paraffin attenuators placed at the collimator exit. Detector-reconstructed integral fast-neutron fluence rates of the order of 104–105 n/(cm^2·s) were obtained, and an attenuation-based procedure was used to estimate the corresponding fluence rate at the collimator exit. The results show that fast neutrons constitute a non-negligible dose component in the epithermal beam. At the same time, the attenuation-based reconstruction should be regarded as approximate, especially for thick boron-paraffin shielding, and is best interpreted together with Monte Carlo transport calculations.