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

Aoki, K.; Xu, Z.; Matsuki, M.; Kusaka, S.; Tamaki, S.; Sato, F.; Murata, I.

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

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

Aoki, K.; Xu, Z.; Matsuki, M. et al.

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

Number of Access:32（2025-10-09 07:51 Counts）

Identifier to cite or link to this item: https://hdl.handle.net/11094/102616

Link to primary information

File	Format	Terms of use	Size	Views	Date.Available	Description	information
NuclInstrumMethodsPhysResSectA_1080	pdf	None	5.95 MB	32	2025.08.29

Creative Commons : Attribution - NonCommercial - NoDerivatives

Item Information

Output File Export EndNote Basic Export Mendeley

Title	Development and validation of gamma-ray dose measurement method using glass dosimeter covered with mixed material filters in a high-energy gamma-ray field
Creator	CreatorName Aoki, K.
	CreatorName Xu, Z.
	CreatorName Matsuki, M.
	NRID 1000030781314 1000030781314 ORCID 0009-0008-8141-7778 0009-0008-8141-7778 researchmap permalink ks21 ks21 Scopus Author ID 57200213734 57200213734 CreatorName Kusaka, S.
	NRID 1000010823396 1000010823396 researchmap permalink stu417767g stu417767g Scopus Author ID 56785322900 56785322900 CreatorName Tamaki, S.
	CreatorName Sato, F.
	NRID 1000030273600 1000030273600 researchmap permalink read0185261 read0185261 Scopus Author ID 7101662513 7101662513 CreatorName Murata, I.
Subject	Air kerma
	Bayesian estimation
	Boron neutron capture therapy (BNCT)
	Dose estimation
	Mixed radiation field
	RPLGD
Description	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.
Abstract	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.
Publisher	Elsevier B.V.
Source Title	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
Volume (Issue)	1080
Page	170721
Date of Issued	2025-07-04
Language	English
Handle URL	https://hdl.handle.net/11094/102616
PISSN	01689002
Relation.isIdenticalTo	DOI (Publisher Version) https://doi.org/10.1016/j.nima.2025.170721
Access Rights	open access
CopyRight	© 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/
oaire:version	Version of Record
Category	学術雑誌論文 Journal Article

Resource Type	journal article
Local Type	Journal Article
DCMI Type	Text
DCTERMS.bibliographicCitation	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2025, 1080, p. 170721
DC.title	Development and validation of gamma-ray dose measurement method using glass dosimeter covered with mixed material filters in a high-energy gamma-ray field
DC.creator	Aoki, K.
	Xu, Z.
	Matsuki, M.
	Kusaka, S.
	Tamaki, S.
	Sato, F.
	Murata, I.
DC.publisher	Elsevier B.V.
DC.language' scheme='DCTERMS.RFC1766	English
DC.type' scheme='DCTERMS.DCMIType	Text
DCTERMS.issued' scheme='DCTERMS.W3CDTF	2025-07-04
DC.identifier	https://doi.org/10.1016/j.nima.2025.170721
DC.subject	Air kerma
	Bayesian estimation
	Boron neutron capture therapy (BNCT)
	Dose estimation
	Mixed radiation field
	RPLGD
DC.description	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.
DCTERMS.abstract	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.
DC.rights	© 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/
DC.format	102616
citation_title	Development and validation of gamma-ray dose measurement method using glass dosimeter covered with mixed material filters in a high-energy gamma-ray field
citation_author	Aoki, K.
	Xu, Z.
	Matsuki, M.
	Kusaka, S.
	Tamaki, S.
	Sato, F.
	Murata, I.
citation_publisher	Elsevier B.V.
citation_language	English
citation_date	2025-07-04
citation_journal_title	Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
citation_volume	1080
citation_firstpage	170721
citation_doi	https://doi.org/10.1016/j.nima.2025.170721
citation_public_url	https://hdl.handle.net/11094/102616

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

Link to primary information

Item Information

Show details