学術雑誌論文

学術雑誌論文

text

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2025, 1080, p. 170721

Development and validation of gamma-ray dose measurement method using glass dosimeter covered with mixed material filters in a high-energy gamma-ray field

Elsevier B.V.

英語

text

2025-07-04

https://doi.org/10.1016/j.nima.2025.170721

Aoki K., Xu Z., Matsuki M., et al. Development and validation of gamma-ray dose measurement method using glass dosimeter covered with mixed material filters in a high-energy gamma-ray field. Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 1080, 170721 (2025); https://doi.org/10.1016/j.nima.2025.170721.

Boron Neutron Capture Therapy (BNCT) is a next-generation radiation therapy that utilizes the nuclear reaction between neutrons and boron-10 (¹⁰B) to selectively destroy cancer cells. In the treatment field of BNCT, secondary gamma rays are generated from neutron capture reactions, resulting in forming of a mixed field of neutrons and gamma rays. Therefore, in order to accurately determine the patient's exposure dose, it is necessary to separately measure neutron and gamma-ray doses. To address this, our research group has proposed and been investigating the “Shielding Filter Method”, which estimates gamma-ray doses by using two radiophotoluminescence glass dosimeters (RPLGD), adjusting the sensitivity by covering each dosimeter with an appropriate shielding filter, and making the difference between the measured results. In the previous study, we first aimed to measure gamma-ray doses using a single filter in a gamma-only field. As a result, it was found that the measured dose had a large error when the incident angle of the gamma-rays to the glass dosimeter was large. In this study, we optimized the design by thinning the filter and adjusting the placement of filter materials, and by adding filter covers in both ends. Consequently, the reproducibility of the air kerma coefficient within a 6.1 % error was confirmed for the entire energy range up to 10 MeV. Furthermore, irradiation experiments using gamma-ray standard sources were conducted and the obtained results were consistent with both the PHITS simulation results and theoretical values within an acceptable error. Going forward, we plan to design and manufacture two types of filters for two glasses to verify whether gamma-ray doses can be measured in a mixed neutron and gamma-ray field.

© 2025. This manuscript version is made available under the CC-BY-NC-ND 4.0 license https://creativecommons.org/licenses/by-nc-nd/4.0/

102616

Development and validation of gamma-ray dose measurement method using glass dosimeter covered with mixed material filters in a high-energy gamma-ray field

Elsevier B.V.

英語

2025-07-04

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

1080

170721

https://doi.org/10.1016/j.nima.2025.170721

https://hdl.handle.net/11094/102616