Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiation
A 100 kW thermal power pool-type light water reactor and Pu(Be) as a fast neutron source were used to determine the appropriate carrier for irradiating boron-containing samples with neutron beams. The tested materials (carriers) were subjected to neutron beams in the reactor's tangential channe...
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| Format: | Article |
| Language: | English |
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Elsevier
2023-08-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573323002152 |
| _version_ | 1797770051463413760 |
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| author | Ezddin Hutli Peter Zagyvai |
| author_facet | Ezddin Hutli Peter Zagyvai |
| author_sort | Ezddin Hutli |
| collection | DOAJ |
| description | A 100 kW thermal power pool-type light water reactor and Pu(Be) as a fast neutron source were used to determine the appropriate carrier for irradiating boron-containing samples with neutron beams. The tested materials (carriers) were subjected to neutron beams in the reactor's tangential channel. The geometrical arrangement of experimental facilities relative to the neutron beam trajectory, as well as the effect of sample thickness on the count rate, were investigated. The majority of the detectable charged particles emitted by the neutron beam's interaction with tested materials and the detector's detecting layer are protons (recoiled hydrogen) and particles generated in nuclear reactions (protons and alpha particles), respectively. Stopping and Range of Ions in Matter (SRIM) software was used to do theoretical calculations for the range of expected released particles in various materials, including human tissue. The results of measurement and calculation are in good agreement. According to experiments and theoretical calculations, the number of protons emitted by tissue-like materials may commit a dose comparable to that of boron capture reactions. Furthermore, the range of protons is significantly larger than that of alpha particles, which most probably changes dose distribution in healthy cells surrounding the tumor, which is undesirable in the BNCT approach. |
| first_indexed | 2024-03-12T21:17:51Z |
| format | Article |
| id | doaj.art-6a66325c7f604ccbae18c61187665935 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-03-12T21:17:51Z |
| publishDate | 2023-08-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-6a66325c7f604ccbae18c611876659352023-07-29T04:34:54ZengElsevierNuclear Engineering and Technology1738-57332023-08-0155829842996Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiationEzddin Hutli0Peter Zagyvai1Centre for Energy Research, Budapest, Hungary; Institute of Nuclear Techniques, Budapest University of Technology and Economics, Budapest, Hungary; Corresponding author. Centre for Energy Research, Budapest, Hungary.Centre for Energy Research, Budapest, Hungary; Institute of Nuclear Techniques, Budapest University of Technology and Economics, Budapest, HungaryA 100 kW thermal power pool-type light water reactor and Pu(Be) as a fast neutron source were used to determine the appropriate carrier for irradiating boron-containing samples with neutron beams. The tested materials (carriers) were subjected to neutron beams in the reactor's tangential channel. The geometrical arrangement of experimental facilities relative to the neutron beam trajectory, as well as the effect of sample thickness on the count rate, were investigated. The majority of the detectable charged particles emitted by the neutron beam's interaction with tested materials and the detector's detecting layer are protons (recoiled hydrogen) and particles generated in nuclear reactions (protons and alpha particles), respectively. Stopping and Range of Ions in Matter (SRIM) software was used to do theoretical calculations for the range of expected released particles in various materials, including human tissue. The results of measurement and calculation are in good agreement. According to experiments and theoretical calculations, the number of protons emitted by tissue-like materials may commit a dose comparable to that of boron capture reactions. Furthermore, the range of protons is significantly larger than that of alpha particles, which most probably changes dose distribution in healthy cells surrounding the tumor, which is undesirable in the BNCT approach.http://www.sciencedirect.com/science/article/pii/S1738573323002152ReactorBoronNeutronAlphaProtonDose |
| spellingShingle | Ezddin Hutli Peter Zagyvai Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiation Nuclear Engineering and Technology Reactor Boron Neutron Alpha Proton Dose |
| title | Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiation |
| title_full | Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiation |
| title_fullStr | Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiation |
| title_full_unstemmed | Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiation |
| title_short | Measurement of the applicability of various experimental materials in a medically relevant reactor neutron source Part One: Material characteristics acting as a carrier for boron compounds during neutron irradiation |
| title_sort | measurement of the applicability of various experimental materials in a medically relevant reactor neutron source part one material characteristics acting as a carrier for boron compounds during neutron irradiation |
| topic | Reactor Boron Neutron Alpha Proton Dose |
| url | http://www.sciencedirect.com/science/article/pii/S1738573323002152 |
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