Pub Date : 2025-09-15DOI: 10.1016/j.radmeas.2025.107516
Elizabeth Fairall , Tanya Hutton , Peane Maleka , Andy Buffler
A metrological characterisation of a high-energy neutron field at the iThemba Laboratory for Accelerator-Based Sciences (LABS) was combined with Monte Carlo radiation transport simulations to estimate the absorbed dose delivered to vials of human blood for an experimental setup relevant to conducting radiobiology experiments at this facility. Neutrons with a peak energy of 62.34(37) MeV were produced by a 66.48 MeV proton beam irradiating an 8.0 mm lithium target. The neutron beam energy distribution and fluence were characterised at emission angles of 0° and 16° via Time-of-Flight measurements with a BC-501A liquid scintillation detector, a 238U fission ionisation chamber, and two beam monitors. These measurements were combined with Monte Carlo radiation transport simulations developed in Geant4 to calculate the absorbed dose that would be delivered to four vials of human blood contained in high-density polyethylene phantoms placed at a distance of 4.300 m from the target during a typical irradiation. The absorbed dose delivered to each blood vial per unit monitor count was estimated and combined with measured monitor count rates to determine the absorbed dose rate. Depending on the vial position in the phantom, dose rates ranged from 24.36(78) mGy hour−1 to 26.22(84) mGy hour−1 at 0°, and from 13.16(42) mGy hour−1 to 14.21(46) mGy hour−1 at 16°.
{"title":"Quantification of neutron dose for the 7Li(p,n)7Be reaction at Ep = 66 MeV at the iThemba LABS high-energy neutron facility","authors":"Elizabeth Fairall , Tanya Hutton , Peane Maleka , Andy Buffler","doi":"10.1016/j.radmeas.2025.107516","DOIUrl":"10.1016/j.radmeas.2025.107516","url":null,"abstract":"<div><div>A metrological characterisation of a high-energy neutron field at the iThemba Laboratory for Accelerator-Based Sciences (LABS) was combined with Monte Carlo radiation transport simulations to estimate the absorbed dose delivered to vials of human blood for an experimental setup relevant to conducting radiobiology experiments at this facility. Neutrons with a peak energy of 62.34(37) MeV were produced by a 66.48 MeV proton beam irradiating an 8.0 mm lithium target. The neutron beam energy distribution and fluence were characterised at emission angles of 0° and 16° via Time-of-Flight measurements with a BC-501A liquid scintillation detector, a <sup>238</sup>U fission ionisation chamber, and two beam monitors. These measurements were combined with Monte Carlo radiation transport simulations developed in Geant4 to calculate the absorbed dose that would be delivered to four vials of human blood contained in high-density polyethylene phantoms placed at a distance of 4.300 m from the target during a typical irradiation. The absorbed dose delivered to each blood vial per unit monitor count was estimated and combined with measured monitor count rates to determine the absorbed dose rate. Depending on the vial position in the phantom, dose rates ranged from 24.36(78) mGy hour<sup>−1</sup> to 26.22(84) mGy hour<sup>−1</sup> at 0°, and from 13.16(42) mGy hour<sup>−1</sup> to 14.21(46) mGy hour<sup>−1</sup> at 16°.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"189 ","pages":"Article 107516"},"PeriodicalIF":2.2,"publicationDate":"2025-09-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145097122","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-09-11DOI: 10.1016/j.radmeas.2025.107525
Soheil Aghabaklooei , Hiroshi Yasuda
Ag-doped phosphate radiophotoluminescence (RPL) glass dosimeter (RPLD) is widely used for radiation dosimetry. Although RPLD has the advantage of reusability through proper annealing, the current annealing process has undesirable features, such as heating at a high temperature (approximately 400 °C) and subsequent long (nearly half a day) cooling. In this study, we propose a new approach to initialize RPLDs more safely and rapidly using ultraviolet light (UV), which is expected to be preferable in many occasions, including quality assurance (QA) for radiotherapy. Four samples of commercially available RPLD glass (FD-7) with a size of φ1.5 mm × 12 mm were irradiated with X-rays (160 kV, 6.3 mA) at 0.1, 0.5, 1, 2, and 5 Gy (for H2O) and exposed to UV from a high-pressure mercury UV lamp, which has a broad wavelength range with a dominant peak at 365 nm. RPL intensities were measured using an exclusive RPL readout system (FDG-1000, Asahi Techno Glass Co., Ltd.) at certain time intervals at room temperature. After 3-h UV exposure, the RPL intensity decreased by >90 % for irradiation of 1 Gy or higher, and 6-h UV exposure cleared >95 % of the RPL intensity for 2 Gy or higher. The RPL intensity increased slightly (2 % in 24 h at room temperature) after the termination of UV exposure. According to these findings, it is expected that the proposed heatless approach to initialize RPLDs, named ‘UV-annealing method’ here, will be effectively applied to routine dosimetry in relatively high-dose radiation fields, including radiotherapy facilities.
{"title":"Experimental investigation of a heatless approach for initializing radiophotoluminescence glasses (FD-7) using ultraviolet light","authors":"Soheil Aghabaklooei , Hiroshi Yasuda","doi":"10.1016/j.radmeas.2025.107525","DOIUrl":"10.1016/j.radmeas.2025.107525","url":null,"abstract":"<div><div>Ag-doped phosphate radiophotoluminescence (RPL) glass dosimeter (RPLD) is widely used for radiation dosimetry. Although RPLD has the advantage of reusability through proper annealing, the current annealing process has undesirable features, such as heating at a high temperature (approximately 400 °C) and subsequent long (nearly half a day) cooling. In this study, we propose a new approach to initialize RPLDs more safely and rapidly using ultraviolet light (UV), which is expected to be preferable in many occasions, including quality assurance (QA) for radiotherapy. Four samples of commercially available RPLD glass (FD-7) with a size of φ1.5 mm × 12 mm were irradiated with X-rays (160 kV, 6.3 mA) at 0.1, 0.5, 1, 2, and 5 Gy (for H<sub>2</sub>O) and exposed to UV from a high-pressure mercury UV lamp, which has a broad wavelength range with a dominant peak at 365 nm. RPL intensities were measured using an exclusive RPL readout system (FDG-1000, Asahi Techno Glass Co., Ltd.) at certain time intervals at room temperature. After 3-h UV exposure, the RPL intensity decreased by >90 % for irradiation of 1 Gy or higher, and 6-h UV exposure cleared >95 % of the RPL intensity for 2 Gy or higher. The RPL intensity increased slightly (2 % in 24 h at room temperature) after the termination of UV exposure. According to these findings, it is expected that the proposed heatless approach to initialize RPLDs, named ‘UV-annealing method’ here, will be effectively applied to routine dosimetry in relatively high-dose radiation fields, including radiotherapy facilities.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"189 ","pages":"Article 107525"},"PeriodicalIF":2.2,"publicationDate":"2025-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145047642","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-09-11DOI: 10.1016/j.radmeas.2025.107524
Chao Xie , Chunyun Jiang , Tao Qiu , Xiaodong Wang , Guoqiang Zeng , Shengyang Feng
Indoor radon gas exposure is a major source of ionizing radiation for the public, and its spatial distribution is highly heterogeneous. However, traditional single-point monitoring devices struggle to capture gradient changes, and high costs restrict large-scale deployment. This study developed an Internet of Things (IoT)-based Distributed Radon Monitoring System (DRMS) to achieve high-resolution spatial monitoring by integrating low-cost silicon-based (Si-PIN) sensor arrays with adaptive anti-jamming Zigbee networks. The system employs multiple radon concentration sensors to enhance sensitivity and constructs a star-cluster hybrid topology wireless network, ensuring reliable communication in complex environments (1000 m in line-of-sight and 300 m in non-line-of-sight). Experimental validation shows that DRMS demonstrates good temporal consistency with the standard radon detector RAD7 (Durridge Company Inc., USA) within the dynamic range of 100–300 Bq.m−3. It can capture spatial gradients of radon concentration up to 4.27 times in enclosed spaces (e.g., median value of 228.5 Bq.m−3 in corner areas vs. 53.5 Bq.m−3 in near-window areas), which matches the results of computational fluid dynamics (CFD) simulations (R2 = 0.962). The system provides a cost-effective and precise tool for radon risk assessment in complex environments such as mines and basements, holding significant value for achieving precise prevention and control of radon exposure risks and public health protection.
室内氡气暴露是公众电离辐射的主要来源，其空间分布极不均匀。然而，传统的单点监测设备难以捕捉梯度变化，而且高成本限制了大规模部署。本研究开发了一种基于物联网（IoT）的分布式氡监测系统（DRMS），通过集成低成本硅基（Si-PIN）传感器阵列和自适应抗干扰Zigbee网络，实现高分辨率空间监测。系统采用多个氡浓度传感器增强灵敏度，构建星团混合拓扑无线网络，保证了在复杂环境下（视距1000m和非视距300m）的可靠通信。实验验证表明，DRMS与标准氡探测器RAD7 （Durridge Company Inc.， USA）在100-300 Bq.m−3的动态范围内具有良好的时间一致性。在封闭空间内可捕获高达4.27倍的氡浓度空间梯度（例如，中位数为228.5 Bq）。角落区域的m−3比53.5 Bq。m−3在近窗区域)，这与计算流体力学（CFD）模拟结果相匹配（R2 = 0.962）。该系统为矿山、地下室等复杂环境的氡风险评估提供了一种经济高效的精确工具，对实现氡暴露风险的精准防控和公众健康保护具有重要价值。
{"title":"Distributed IoT-based radon monitoring in indoor spaces: Quantifying spatial gradients using multi-node Si-PIN arrays","authors":"Chao Xie , Chunyun Jiang , Tao Qiu , Xiaodong Wang , Guoqiang Zeng , Shengyang Feng","doi":"10.1016/j.radmeas.2025.107524","DOIUrl":"10.1016/j.radmeas.2025.107524","url":null,"abstract":"<div><div>Indoor radon gas exposure is a major source of ionizing radiation for the public, and its spatial distribution is highly heterogeneous. However, traditional single-point monitoring devices struggle to capture gradient changes, and high costs restrict large-scale deployment. This study developed an Internet of Things (IoT)-based Distributed Radon Monitoring System (DRMS) to achieve high-resolution spatial monitoring by integrating low-cost silicon-based (Si-PIN) sensor arrays with adaptive anti-jamming Zigbee networks. The system employs multiple radon concentration sensors to enhance sensitivity and constructs a star-cluster hybrid topology wireless network, ensuring reliable communication in complex environments (1000 m in line-of-sight and 300 m in non-line-of-sight). Experimental validation shows that DRMS demonstrates good temporal consistency with the standard radon detector RAD7 (Durridge Company Inc., USA) within the dynamic range of 100–300 Bq.m<sup>−3</sup>. It can capture spatial gradients of radon concentration up to 4.27 times in enclosed spaces (e.g., median value of 228.5 Bq.m<sup>−3</sup> in corner areas vs. 53.5 Bq.m<sup>−3</sup> in near-window areas), which matches the results of computational fluid dynamics (CFD) simulations (R<sup>2</sup> = 0.962). The system provides a cost-effective and precise tool for radon risk assessment in complex environments such as mines and basements, holding significant value for achieving precise prevention and control of radon exposure risks and public health protection.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"189 ","pages":"Article 107524"},"PeriodicalIF":2.2,"publicationDate":"2025-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145057436","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-09-11DOI: 10.1016/j.radmeas.2025.107515
Choirul Anam , Toshioh Fujibuchi , Donghee Han , Riska Amilia , Noor Diyana Osman , Geoff Dougherty
Purpose
The aim of this study is to estimate the organ dose using the size-specific dose estimates (SSDE) in an anthropomorphic phantom and compare the results with direct measurements using a pencil ionization chamber and radio-photo-luminescence dosimeters (RPLDs).
Methods
Organ dose estimation in computed tomography (CT) examination was performed using the SSDE concept. The central SSDE (SSDEc) and peripheral SSDE (SSDEp) were calculated from the weighted SSDE (SSDEw). A dose map was created from SSDEc and SSDEp with interpolation. Organ dose or dose at a specific position was calculated as the average of the dose map within a defined region of interest (ROI). We implemented the algorithm on an anthropomorphic phantom scanned by a Toshiba Alexion™ Access 4-slice CT scanner with both fixed tube current (FTC) and tube current modulation (TCM) modes. A pencil ionization chamber and RPLDs were used to measure the organ dose directly in the anthropomorphic phantom. The Kruskal-Wallis test was performed to assess whether there was any significance difference among the methods.
Results
The organ doses estimated using SSDE were comparable with the direct measurements using a pencil ionization chamber and RPLDs. The organ dose estimation using SSDE in FTC mode exhibits a discrepancy of approximately 4.02 ± 0.04 % and 4.59 ± 0.03 % compared to the direct measurements using the ionization chamber and RPLDs, respectively. The differences in the TCM mode are 5.09 ± 0.03 % and 17.91 ± 0.08 % compared to the direct measurements using an ionization chamber and RPLDs, respectively. The statistical analysis yielded a p-value >0.05, confirming the reliability of the SSDE method for organ dose estimation.
Conclusion
Organ dose estimation using the SSDE method has been successfully validated. The organ dose using SSDE was comparable to those from direct measurements.
{"title":"Estimated organ dose using the size-specific dose estimates (SSDE) and its comparison with direct measurements","authors":"Choirul Anam , Toshioh Fujibuchi , Donghee Han , Riska Amilia , Noor Diyana Osman , Geoff Dougherty","doi":"10.1016/j.radmeas.2025.107515","DOIUrl":"10.1016/j.radmeas.2025.107515","url":null,"abstract":"<div><h3>Purpose</h3><div>The aim of this study is to estimate the organ dose using the size-specific dose estimates (SSDE) in an anthropomorphic phantom and compare the results with direct measurements using a pencil ionization chamber and radio-photo-luminescence dosimeters (RPLDs).</div></div><div><h3>Methods</h3><div>Organ dose estimation in computed tomography (CT) examination was performed using the SSDE concept. The central SSDE (SSDE<sub>c</sub>) and peripheral SSDE (SSDE<sub>p</sub>) were calculated from the weighted SSDE (SSDE<sub>w</sub>). A dose map was created from SSDE<sub>c</sub> and SSDE<sub>p</sub> with interpolation. Organ dose or dose at a specific position was calculated as the average of the dose map within a defined region of interest (ROI). We implemented the algorithm on an anthropomorphic phantom scanned by a Toshiba Alexion™ Access 4-slice CT scanner with both fixed tube current (FTC) and tube current modulation (TCM) modes. A pencil ionization chamber and RPLDs were used to measure the organ dose directly in the anthropomorphic phantom. The Kruskal-Wallis test was performed to assess whether there was any significance difference among the methods.</div></div><div><h3>Results</h3><div>The organ doses estimated using SSDE were comparable with the direct measurements using a pencil ionization chamber and RPLDs. The organ dose estimation using SSDE in FTC mode exhibits a discrepancy of approximately 4.02 ± 0.04 % and 4.59 ± 0.03 % compared to the direct measurements using the ionization chamber and RPLDs, respectively. The differences in the TCM mode are 5.09 ± 0.03 % and 17.91 ± 0.08 % compared to the direct measurements using an ionization chamber and RPLDs, respectively. The statistical analysis yielded a <em>p</em>-value >0.05, confirming the reliability of the SSDE method for organ dose estimation.</div></div><div><h3>Conclusion</h3><div>Organ dose estimation using the SSDE method has been successfully validated. The organ dose using SSDE was comparable to those from direct measurements.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"189 ","pages":"Article 107515"},"PeriodicalIF":2.2,"publicationDate":"2025-09-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145047641","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-09-02DOI: 10.1016/j.radmeas.2025.107514
Yu Xiang , Xiaopan Jiang , Bin Tang , Xu Chen , Xiaoxuan Li , Xianchao Huang , Zhiming Zhang , Cunfeng Wei , Long Wei
The nuclide 113Cd is sensitive to thermal neutrons. Most of the gamma rays generated from 113Cd reactions have an energy of 558 keV. CdZnTe detectors contain Cd-113. Their good energy resolution for gamma rays ensures that they can identify the thermal neutrons by detecting the prompt gamma rays. Planar CdZnTe detectors are easy to manufacture and therefore cheap. Nonetheless, they have not yet been utilized in thermal neutron detection since their spectra lack the 558 keV photopeak, which is essential for identifying neutron capture events. In this paper, a 22 mm22 mm0.5 mm planar CdZnTe detector was used to detect the thermal neutrons from the No. 20 neutron beam line of China Spallation Neutron Source. A special detection method was applied to distinguish thermal neutrons from background radiation so that the planar detector was able to detect thermal neutrons. The intrinsic total detection efficiency of the detector for thermal neutrons was measured as 6.58%0.76%. The result demonstrates that planar CdZnTe detectors are also able to serve as thermal neutron detectors.
{"title":"The performance of a planar CdZnTe thermal neutron detector","authors":"Yu Xiang , Xiaopan Jiang , Bin Tang , Xu Chen , Xiaoxuan Li , Xianchao Huang , Zhiming Zhang , Cunfeng Wei , Long Wei","doi":"10.1016/j.radmeas.2025.107514","DOIUrl":"10.1016/j.radmeas.2025.107514","url":null,"abstract":"<div><div>The nuclide <sup>113</sup>Cd is sensitive to thermal neutrons. Most of the gamma rays generated from <sup>113</sup>Cd<span><math><mrow><msup><mrow><mrow><mo>(</mo><mi>n</mi><mo>,</mo><mi>γ</mi><mo>)</mo></mrow></mrow><mrow><mn>114</mn></mrow></msup><mi>Cd</mi></mrow></math></span> reactions have an energy of 558 keV. CdZnTe detectors contain Cd-113. Their good energy resolution for gamma rays ensures that they can identify the thermal neutrons by detecting the prompt gamma rays. Planar CdZnTe detectors are easy to manufacture and therefore cheap. Nonetheless, they have not yet been utilized in thermal neutron detection since their spectra lack the 558 keV photopeak, which is essential for identifying neutron capture events. In this paper, a 22 mm<span><math><mo>×</mo></math></span>22 mm<span><math><mo>×</mo></math></span>0.5 mm planar CdZnTe detector was used to detect the thermal neutrons from the No. 20 neutron beam line of China Spallation Neutron Source. A special detection method was applied to distinguish thermal neutrons from background radiation so that the planar detector was able to detect thermal neutrons. The intrinsic total detection efficiency of the detector for thermal neutrons was measured as 6.58%<span><math><mo>±</mo></math></span>0.76%. The result demonstrates that planar CdZnTe detectors are also able to serve as thermal neutron detectors.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"188 ","pages":"Article 107514"},"PeriodicalIF":2.2,"publicationDate":"2025-09-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145018418","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
A new Bonner sphere spectrometer (BSS) has been developed to measure the spectral fluence of high-intensity neutrons in boron neutron capture therapy facilities and radiation resistance test facilities for electronic devices. A pair of lithium-glass scintillators (GS20 and GS30) coupled with current-integrating photomultiplier tubes was adopted as a low-energy neutron detection element for the Bonner sphere detectors to compensate for the effects of γ-rays. The response matrix for the BSS was determined by Monte Carlo simulations of the response in pulse-counting mode and by using an experimentally determined conversion factor to convert the pulse-counting response to the current-integrating response. Since the new detector has geometric asymmetry, the directional dependence of the response functions was evaluated through experiments and Monte Carlo simulations. A significant directional dependence was observed, which is acceptable when neutrons from a single direction, but care must be taken when measuring neutrons originating from a wide range of directions.
{"title":"Development and response characterization of new Bonner sphere spectrometer using lithium-glass scintillators coupled with current-integrating photomultiplier tubes","authors":"Akihiko Masuda , Tetsuro Matsumoto , Seiya Manabe , Hideki Harano , Hiroki Tanaka , Yoshinori Sakurai , Daisuke Ito , Takushi Takata , Hiroaki Kumada","doi":"10.1016/j.radmeas.2025.107512","DOIUrl":"10.1016/j.radmeas.2025.107512","url":null,"abstract":"<div><div>A new Bonner sphere spectrometer (BSS) has been developed to measure the spectral fluence of high-intensity neutrons in boron neutron capture therapy facilities and radiation resistance test facilities for electronic devices. A pair of lithium-glass scintillators (GS20 and GS30) coupled with current-integrating photomultiplier tubes was adopted as a low-energy neutron detection element for the Bonner sphere detectors to compensate for the effects of γ-rays. The response matrix for the BSS was determined by Monte Carlo simulations of the response in pulse-counting mode and by using an experimentally determined conversion factor to convert the pulse-counting response to the current-integrating response. Since the new detector has geometric asymmetry, the directional dependence of the response functions was evaluated through experiments and Monte Carlo simulations. A significant directional dependence was observed, which is acceptable when neutrons from a single direction, but care must be taken when measuring neutrons originating from a wide range of directions.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"189 ","pages":"Article 107512"},"PeriodicalIF":2.2,"publicationDate":"2025-09-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145020743","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Following the Fukushima Daiichi Nuclear Power Plant accident, radioactive cesium contamination posed a significant environmental concern. This study developed a compact gamma-ray spectrometer utilizing a Gd2Si2O7:Ce (Ce:GPS) scintillator and a compact photomultiplier tube (PMT) for environmental monitoring. The spectrometer was designed to overcome the limitations of traditional NaI(Tl) detectors, leveraging the non-hygroscopic nature and high energy resolution of Ce:GPS scintillators. Performance was evaluated through measurements of a137Cs source and a comparison with a commercial NaI(Tl) survey meter. The spectrometer's potential for effective and portable monitoring of radioactive cesium in contaminated environments was demonstrated. The system was tested using sealed sources, confirming its ability to detect the 662 keV photopeak of 137Cs with high accuracy. The energy resolution of this photopeak was 10.8 % FWHM. Field measurements in radiocesium-contaminated areas showed the spectrometer's effectiveness in detecting dose rate variations and high-dose hotspots. This portable, durable spectrometer shows promise for applications in environmental radiation monitoring and remote sensing technologies.
{"title":"Development of a Ce:GPS scintillator-based spectrometer and its demonstration in radioactive cesium contamination sites","authors":"Yuki Morishita , Shigeo Nakama , Kotaro Ochi , Yoshimi Urabe , Marina Kanno","doi":"10.1016/j.radmeas.2025.107513","DOIUrl":"10.1016/j.radmeas.2025.107513","url":null,"abstract":"<div><div>Following the Fukushima Daiichi Nuclear Power Plant accident, radioactive cesium contamination posed a significant environmental concern. This study developed a compact gamma-ray spectrometer utilizing a Gd<sub>2</sub>Si<sub>2</sub>O<sub>7</sub>:Ce (Ce:GPS) scintillator and a compact photomultiplier tube (PMT) for environmental monitoring. The spectrometer was designed to overcome the limitations of traditional NaI(Tl) detectors, leveraging the non-hygroscopic nature and high energy resolution of Ce:GPS scintillators. Performance was evaluated through measurements of a<sup>137</sup>Cs source and a comparison with a commercial NaI(Tl) survey meter. The spectrometer's potential for effective and portable monitoring of radioactive cesium in contaminated environments was demonstrated. The system was tested using sealed sources, confirming its ability to detect the 662 keV photopeak of <sup>137</sup>Cs with high accuracy. The energy resolution of this photopeak was 10.8 % FWHM. Field measurements in radiocesium-contaminated areas showed the spectrometer's effectiveness in detecting dose rate variations and high-dose hotspots. This portable, durable spectrometer shows promise for applications in environmental radiation monitoring and remote sensing technologies.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"189 ","pages":"Article 107513"},"PeriodicalIF":2.2,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145026332","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-08-18DOI: 10.1016/j.radmeas.2025.107511
Zhou Yuan , Weihai Zhuo , Zhiyuan Yang , Jingfang Zhao , Bo Chen
The measurement of linear energy transfer (LET) distribution in carbon ion therapeutic fields is essential for optimizing beam quality control and enhancing therapeutic outcomes. To address the need for precise LET measurements, this study introduces a novel combined detector integrating CR-39 and thermoluminescent dosimeters (TLDs). Capitalizing on the respective strengths of each detector, a new method was developed to estimate LET spectra. Validation experiments and applications in both water and lung phantoms demonstrated that the combined detector significantly enhanced measurement accuracy compared to the use of either detector individually. The relative deviation in LETd measurements was controlled within 15 %. These findings suggest that the integrated detector system is highly effective for LET distribution measurements in carbon ion therapy and holds substantial potential for clinical applications.
{"title":"Combined detection method of LET measurement using CR-39 and TLD in carbon ion radiotherapy","authors":"Zhou Yuan , Weihai Zhuo , Zhiyuan Yang , Jingfang Zhao , Bo Chen","doi":"10.1016/j.radmeas.2025.107511","DOIUrl":"10.1016/j.radmeas.2025.107511","url":null,"abstract":"<div><div>The measurement of linear energy transfer (LET) distribution in carbon ion therapeutic fields is essential for optimizing beam quality control and enhancing therapeutic outcomes. To address the need for precise LET measurements, this study introduces a novel combined detector integrating CR-39 and thermoluminescent dosimeters (TLDs). Capitalizing on the respective strengths of each detector, a new method was developed to estimate LET spectra. Validation experiments and applications in both water and lung phantoms demonstrated that the combined detector significantly enhanced measurement accuracy compared to the use of either detector individually. The relative deviation in LET<sub>d</sub> measurements was controlled within 15 %. These findings suggest that the integrated detector system is highly effective for LET distribution measurements in carbon ion therapy and holds substantial potential for clinical applications.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"188 ","pages":"Article 107511"},"PeriodicalIF":2.2,"publicationDate":"2025-08-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144902735","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
This study aims to evaluate the potential of polyallyl diglycol carbonate (PADC) detectors, coupled with LiF converters, for passive environmental neutron dosimetry. Their performance is compared against three other methods, fission track detectors, thermoluminescent detectors (TLDs), and optically stimulated luminescence detectors (OSLDs), to determine their viability for passive routine neutron monitoring in environmental settings.
The four detector types investigated (PADCs, fission tracks, TLDs and OSLDs) were placed in a moderator sphere and exposed to an AmBe neutron field. The measurements evaluated the dose response, measurement range, and precision of each system.
Results confirm that the advantage of the track detectors (PADC or fission track) is their gamma insensitivity: the TLD and OSLD methods require the combination of neutron-sensitive with neutron-insensitive detectors, as both are gamma-sensitive. This translated into a detection limit =6 μ Sv for PADC detectors coupled with LiF converters, comparable to that of fission track detectors (3 μ Sv). In contrast, the gamma-sensitive luminescence systems showed a detection limit of 10 μ Sv for the TLDs and 180 μ Sv for the OSLDs under AmBe neutron irradiations. This worsens under simulated environmental conditions, where a significant gamma contribution is expected, as demonstrated by a test where mixed gamma/neutron irradiation was used.
These results indicate the potential of the PADC coupled with a LiF converter system as a robust alternative to fission track detectors for passive environmental neutron dosimetry.
{"title":"Weighing options for passive environmental neutron dosimetry: A comparative study of PADCs, TLDs, OSLDs, and fission track detectors","authors":"Lily Bossin, Jeppe Brage Christensen, Federico Alejandro Geser, Malgorzata Kasprzak, Sabine Mayer, Malgorzata Sliz, Alberto Stabilini, Eduardo Gardenali Yukihara","doi":"10.1016/j.radmeas.2025.107504","DOIUrl":"10.1016/j.radmeas.2025.107504","url":null,"abstract":"<div><div>This study aims to evaluate the potential of polyallyl diglycol carbonate (PADC) detectors, coupled with <span><math><msup><mrow></mrow><mrow><mn>6</mn></mrow></msup></math></span>LiF converters, for passive environmental neutron dosimetry. Their performance is compared against three other methods, fission track detectors, thermoluminescent detectors (TLDs), and optically stimulated luminescence detectors (OSLDs), to determine their viability for passive routine neutron monitoring in environmental settings.</div><div>The four detector types investigated (PADCs, fission tracks, TLDs and OSLDs) were placed in a moderator sphere and exposed to an AmBe neutron field. The measurements evaluated the dose response, measurement range, and precision of each system.</div><div>Results confirm that the advantage of the track detectors (PADC or fission track) is their gamma insensitivity: the TLD and OSLD methods require the combination of neutron-sensitive with neutron-insensitive detectors, as both are gamma-sensitive. This translated into a detection limit <span><math><mrow><msup><mrow><mi>H</mi></mrow><mrow><mo>∗</mo></mrow></msup><mrow><mo>(</mo><mn>10</mn><mo>)</mo></mrow></mrow></math></span>=6<!--> <!-->μ<!--> <!-->Sv for PADC detectors coupled with <span><math><msup><mrow></mrow><mrow><mn>6</mn></mrow></msup></math></span>LiF converters, comparable to that of fission track detectors (3<!--> <!-->μ<!--> <!-->Sv). In contrast, the gamma-sensitive luminescence systems showed a detection limit of 10<!--> <!-->μ<!--> <!-->Sv for the TLDs and 180<!--> <!-->μ<!--> <!-->Sv for the OSLDs under AmBe neutron irradiations. This worsens under simulated environmental conditions, where a significant gamma contribution is expected, as demonstrated by a test where mixed gamma/neutron irradiation was used.</div><div>These results indicate the potential of the PADC coupled with a <span><math><msup><mrow></mrow><mrow><mn>6</mn></mrow></msup></math></span>LiF converter system as a robust alternative to fission track detectors for passive environmental neutron dosimetry.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"188 ","pages":"Article 107504"},"PeriodicalIF":2.2,"publicationDate":"2025-08-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144903300","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2025-08-07DOI: 10.1016/j.radmeas.2025.107497
Yongqi Huang, Yang (Michael) Yang
Perovskite scintillators have emerged as one class of competitive scintillators for next-generation X-ray detection and imaging due to their unique properties, including high atomic number (Z), superior radiation absorption capability, high photoluminescence quantum yield (PLQY), ultrafast response time, excellent spatial resolution, and low-cost fabrication. The tunable structure and versatile chemical compositions of perovskite scintillators provide distinguishable advantages over traditional inorganic scintillators for optimizing scintillation performance. This review briefly outlines the historical development of scintillators and categorizes perovskite-based scintillators based on their structural characteristics, introducing key performance parameters and evaluation criteria. Recent progress is then summarized in three major application domains: high-resolution X-ray imaging, ultrafast dynamic imaging, and multi-energy spectral imaging. The discussion highlights representative achievements and technical challenges associated with light yield, temporal response, and image resolution. Finally, current research bottlenecks, such as poor environmental stability, fabrication complexity, and system integration issues, are examined, and potential strategies for future development are proposed, including material optimization, structural engineering, and interdisciplinary system-level integration. This review aims to provide a comprehensive understanding of perovskite scintillators and promote their practical implementation in advanced radiation detection technologies.
{"title":"Perovskite scintillators for X-ray detection and imaging","authors":"Yongqi Huang, Yang (Michael) Yang","doi":"10.1016/j.radmeas.2025.107497","DOIUrl":"10.1016/j.radmeas.2025.107497","url":null,"abstract":"<div><div>Perovskite scintillators have emerged as one class of competitive scintillators for next-generation X-ray detection and imaging due to their unique properties, including high atomic number (Z), superior radiation absorption capability, high photoluminescence quantum yield (PLQY), ultrafast response time, excellent spatial resolution, and low-cost fabrication. The tunable structure and versatile chemical compositions of perovskite scintillators provide distinguishable advantages over traditional inorganic scintillators for optimizing scintillation performance. This review briefly outlines the historical development of scintillators and categorizes perovskite-based scintillators based on their structural characteristics, introducing key performance parameters and evaluation criteria. Recent progress is then summarized in three major application domains: high-resolution X-ray imaging, ultrafast dynamic imaging, and multi-energy spectral imaging. The discussion highlights representative achievements and technical challenges associated with light yield, temporal response, and image resolution. Finally, current research bottlenecks, such as poor environmental stability, fabrication complexity, and system integration issues, are examined, and potential strategies for future development are proposed, including material optimization, structural engineering, and interdisciplinary system-level integration. This review aims to provide a comprehensive understanding of perovskite scintillators and promote their practical implementation in advanced radiation detection technologies.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"188 ","pages":"Article 107497"},"PeriodicalIF":2.2,"publicationDate":"2025-08-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144860345","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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