Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source part two: Study of H3BO3 and B-DTPA under neutron irradiation

  • Ezddin Hutli (Centre for Energy Research, Thermo-hydraulics Department) ;
  • Peter Zagyvai (Centre for Energy Research, Environmental Physics Department)
  • Received : 2022.08.11
  • Accepted : 2023.03.02
  • Published : 2023.07.25
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Abstract

Experiments related to Boron Neutron Capture Therapy (BNCT) accomplished at the Institute of Nuclear Techniques (INT), Budapest University of Technology and Economics (TUB) are presented. Relevant investigations are required before designing BNCT for vivo applications. Samples of relevant boron compounds (H3BO3, BDTPA) usually employed in BNCT were investigated with neutron beam. Channel #5 in the research reactor (100 kW) of INT-TUB provides the neutron beam. Boron samples are mounted on a carrier for neutron irradiation. The particle attenuation of several carrier materials was investigated, and the one with the lowest attenuation was selected. The effects of boron compound type, mass, and compound phase state were also investigated. To detect the emitted charged particles, a traditional ZnS(Ag) detector was employed. The neutron beam's interaction with the detector-detecting layer is investigated. Graphite (as a moderator) was employed to change the neutron beam's characteristics. The fast neutron beam was also thermalized by placing a portable fast neutron source in a paraffin container and irradiating the H3BO3. The obtained results suggest that the direct measurement approach appears to be insufficiently sensitive for determining the radiation dose committed by the Alpha particles from the 10B (n,α) reaction. As a result, a new approach must be used.

Keywords

Acknowledgement

The first author would like to express his deepest appreciation to the INT-TUB training reactor staff for their outstanding assistance. His appreciation also goes to Dr. L. Duffek, SOTE Department of Radiology, Semmelweis Clinic, for his assistance. Prof. Szabolcs Czifrus, director of the Institute of Nuclear Techniques at Budapest University of Technology and Economics (INTTUB), is also appreciated for his insightful comments. My heartfelt gratitude goes to the Ministry of Higher Education in the Great Libyan Arab Jamahiriya for funding this study at the INT-TUB reactor in Hungary.

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