Radiation Measurements最新文献_第9页

Radiation source analysis of beamline stations at fourth-generation synchrotron light facility 第四代同步加速器光束线站辐射源分析

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-09-16 DOI: 10.1016/j.radmeas.2025.107528

Jiaduo Chen , Shiping Jiang , Penghui Yang , Lin Wang

Bremsstrahlung produced by electrons in the storage ring is a major concern in the radiation shielding design of synchrotron light sources, primarily arising from the Touschek effect and vacuum-related effect. Depending on the underlying mechanism, the resulting bremsstrahlung is classified as either solid or gas bremsstrahlung, both of which can propagate into beamline stations, especially from straight sections, thereby posing radiological risks to personnel and equipment.

With the advancement of fourth-generation synchrotron light sources based on diffraction-limited storage ring technology, the characteristics of bremsstrahlung radiation originating from straight sections have become increasingly complex, making earlier radiation source models no longer directly applicable. The objective of this study is to conduct an analysis of radiation sources in beamline stations of fourth-generation synchrotron facilities, clarify their respective contributions, and evaluate the implications of different modeling methodologies for shielding design. This study focuses on a representative beamline at the Hefei Advanced Light Facility. Three modeling approaches are developed and compared: (i) a simplified model, which assumes uniform electron losses throughout the storage ring with fixed-angle impacts on internal surfaces; (ii) a more refined model, which uses ELEGANT to accurately simulate electron loss positions and dynamics in straight sections, coupled with FLUKA to analyze the generation and transport of solid bremsstrahlung; and (iii) a gas bremsstrahlung model, which employs FLUKA to directly simulate electron–residual gas interactions.

The study compares the energy spectra, angular distributions, and spatial profiles of bremsstrahlung from the three models on the upstream wall of the first optical enclosure. Ambient dose equivalent distributions surrounding the enclosure are also evaluated. Results indicate that both solid and gas bremsstrahlung are major contributors to radiation levels in the beamline stations, each exhibiting distinct spatial and spectral characteristics. In addition, the study finds that the simplified model introduces significant deviations in the estimation of solid bremsstrahlung, highlighting the importance of accurately incorporating electron loss information in radiation simulations for beamline stations at fourth-generation synchrotron light sources to achieve reliable shielding assessments.

存储环中电子产生的轫致辐射是同步加速器光源辐射屏蔽设计中的一个重要问题，主要是由于图谢克效应和真空相关效应引起的。根据潜在的机制，产生的轫致辐射分为固体或气体轫致辐射，这两种轫致辐射都可以传播到束线站，特别是从直线段传播，从而对人员和设备构成辐射风险。随着基于限衍射存储环技术的第四代同步加速器光源的发展，源自直线截面的轫致辐射特性变得越来越复杂，使得早期的辐射源模型不再直接适用。本研究的目的是对第四代同步加速器设施光束线站的辐射源进行分析，阐明其各自的贡献，并评估不同建模方法对屏蔽设计的影响。本研究的重点是合肥先进光设施具有代表性的光束线。本文提出并比较了三种建模方法：(i)简化模型，该模型假设整个存储环的电子损失均匀，内表面受到固定角度的冲击；（ii）更精细的模型，使用ELEGANT精确模拟直线段的电子损失位置和动力学，结合FLUKA分析固体轫致辐射的产生和输运；（iii）气体轫致模型，采用FLUKA直接模拟电子-残余气体相互作用。研究比较了三种模型在第一光学罩上游壁面上轫致辐射的能谱、角分布和空间分布。还评估了围体周围的环境剂量当量分布。结果表明，固体轫致和气体轫致都是影响光束线站辐射水平的主要因素，并表现出不同的空间和光谱特征。此外，研究发现，简化模型在估计固体轫致辐射时引入了显著偏差，突出了在第四代同步加速器光源光束线站的辐射模拟中准确纳入电子损失信息以实现可靠屏蔽评估的重要性。

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引用次数: 0

Quantification of neutron dose for the 7Li(p,n)7Be reaction at Ep = 66 MeV at the iThemba LABS high-energy neutron facility iThemba实验室高能中子装置Ep = 66 MeV下7Li(p,n)7Be反应的中子剂量定量

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-09-15 DOI: 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°.

iThemba加速器科学实验室（实验室）高能中子场的计量特征与蒙特卡罗辐射输运模拟相结合，以估计输送到人体血液小瓶的吸收剂量，该实验装置与在该设施进行放射生物学实验有关。用66.48 MeV质子束辐照8.0 mm锂靶，产生峰值能量为62.34(37)MeV的中子。利用BC-501A型液体闪烁探测器、238U裂变电离室和两台中子束监测器对发射角为0°和16°的中子束能量分布和通量进行了飞行时间测量。这些测量结果与在Geant4中开发的蒙特卡罗辐射传输模拟相结合，以计算在典型辐照期间，在距离目标4300米的距离放置在高密度聚乙烯模型中的四瓶人体血液中的吸收剂量。估计每单位监测计数给每个血瓶的吸收剂量，并结合监测计数率来确定吸收剂量率。根据小瓶在幻影中的位置，剂量率在0°时为24.36(78)mGy小时−1至26.22(84)mGy小时−1，在16°时为13.16(42)mGy小时−1至14.21(46)mGy小时−1。

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引用次数: 0

Experimental investigation of a heatless approach for initializing radiophotoluminescence glasses (FD-7) using ultraviolet light 用紫外光初始化辐射光致发光玻璃（FD-7）的无热方法的实验研究

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-09-11 DOI: 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.

掺银磷酸盐辐射光致发光（RPL）玻璃剂量计（RPLD）被广泛应用于辐射剂量测定。虽然RPLD通过适当的退火具有可重复使用的优点，但目前的退火工艺具有不理想的特点，例如在高温（约400°C）下加热和随后的长时间（近半天）冷却。在这项研究中，我们提出了一种使用紫外线（UV）更安全、快速地初始化rpld的新方法，该方法有望在许多场合，包括放射治疗的质量保证（QA）中更可取。采用尺寸为φ1.5 mm × 12 mm的4个市售RPLD玻璃（FD-7）样品，分别以0.1、0.5、1、2和5 Gy （H2O）的x射线（160 kV, 6.3 mA）照射，并在高压汞紫外线灯下照射，该灯具有宽波长范围，主峰位于365 nm。在室温下，使用专用的RPL读出系统（FDG-1000, Asahi Techno Glass Co., Ltd）以一定的时间间隔测量RPL强度。紫外线照射3小时后，1 Gy及以上照射的RPL强度降低了90%；照射6小时后，2 Gy及以上照射的RPL强度降低了95%。紫外照射终止后，RPL强度略有增加（室温下24 h内增加2%）。根据这些发现，我们期望所提出的初始化rpld的无热方法，即“uv退火法”，将有效地应用于相对高剂量辐射领域的常规剂量测定，包括放射治疗设施。

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引用次数: 0

Distributed IoT-based radon monitoring in indoor spaces: Quantifying spatial gradients using multi-node Si-PIN arrays 室内空间分布式物联网氡监测：利用多节点Si-PIN阵列量化空间梯度

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-09-11 DOI: 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。

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引用次数: 0

Estimated organ dose using the size-specific dose estimates (SSDE) and its comparison with direct measurements 使用大小特异性剂量估计值（SSDE）估计器官剂量及其与直接测量的比较

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-09-11 DOI: 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 (SSDE_c) and peripheral SSDE (SSDE_p) were calculated from the weighted SSDE (SSDE_w). A dose map was created from SSDE_c and SSDE_p 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.

本研究的目的是在拟人模型中使用尺寸特异性剂量估计值（SSDE）来估计器官剂量，并将结果与使用铅笔电离室和射电光致发光剂量计（RPLDs）的直接测量结果进行比较。方法采用SSDE概念对CT检查中的器官剂量进行估计。由加权SSDE （SSDEw）计算中心SSDE （SSDEc）和外周SSDE （SSDEp）。用插值法从SSDEc和SSDEp建立剂量图。器官剂量或特定位置的剂量计算为确定感兴趣区域（ROI）内剂量图的平均值。我们在东芝Alexion™Access 4层CT扫描仪扫描的拟人幻影上实现了该算法，该扫描仪具有固定管电流（FTC）和管电流调制（TCM）模式。使用铅笔电离室和rpld直接测量拟人化幻影中的器官剂量。采用Kruskal-Wallis检验评估不同方法间是否存在显著性差异。结果使用SSDE估算的器官剂量与使用铅笔电离室和RPLDs直接测量的器官剂量相当。与使用电离室和rpld直接测量相比，在FTC模式下使用SSDE进行的器官剂量估计分别显示出约4.02±0.04%和4.59±0.03%的差异。与使用电离室和rpld直接测量相比，TCM模式的差异分别为5.09±0.03%和17.91±0.08%。统计分析的p值为>；0.05，证实了SSDE方法估计器官剂量的可靠性。结论用SSDE方法估算器官剂量是可行的。使用SSDE的器官剂量与直接测量的剂量相当。

{"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}

引用次数: 0

The performance of a planar CdZnTe thermal neutron detector 平面CdZnTe热中子探测器的性能

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-09-02 DOI: 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

{(n, γ)}^{114} Cd

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

\times

22 mm

\times

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%

\pm

0.76%. The result demonstrates that planar CdZnTe detectors are also able to serve as thermal neutron detectors.

核素113Cd对热中子很敏感。113Cd(n,γ)114Cd反应产生的伽马射线能量大多为558 keV。CdZnTe探测器含有Cd-113。它们对伽马射线的良好能量分辨率确保它们可以通过探测提示的伽马射线来识别热中子。平面CdZnTe探测器易于制造，因此价格低廉。尽管如此，它们还没有被用于热中子探测，因为它们的光谱缺乏558 keV的光峰，这是识别中子捕获事件所必需的。本文利用22 mm×22 mm×0.5 mm平面CdZnTe探测器对中国散裂中子源20号中子束流线的热中子进行了探测。采用一种特殊的检测方法将热中子与背景辐射区分开来，使平面探测器能够探测热中子。对热中子的本征总探测效率为6.58%±0.76%。结果表明，平面型CdZnTe探测器也可以作为热中子探测器。

{"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}

引用次数: 0

Development and response characterization of new Bonner sphere spectrometer using lithium-glass scintillators coupled with current-integrating photomultiplier tubes 锂-玻璃闪烁体耦合积流光电倍增管新型邦纳球光谱仪的研制与响应特性研究

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-09-01 DOI: 10.1016/j.radmeas.2025.107512

Akihiko Masuda , Tetsuro Matsumoto , Seiya Manabe , Hideki Harano , Hiroki Tanaka , Yoshinori Sakurai , Daisuke Ito , Takushi Takata , Hiroaki Kumada

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.

研制了一种新型的邦纳球谱仪（BSS），用于测量电子设备中硼中子俘获治疗设备和耐辐射测试设备中高强度中子的光谱影响。采用一对锂玻璃闪烁体（GS20和GS30）耦合电流积分光电倍增管作为Bonner球探测器的低能中子探测元件，以补偿γ射线的影响。BSS的响应矩阵由脉冲计数模式下响应的蒙特卡罗模拟确定，并使用实验确定的转换因子将脉冲计数响应转换为电流积分响应。由于新型探测器具有几何不对称性，通过实验和蒙特卡罗模拟评估了响应函数的方向依赖性。观察到明显的方向依赖性，当中子来自单一方向时，这是可以接受的，但当测量来自广泛方向的中子时，必须小心。

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引用次数: 0

Development of a Ce:GPS scintillator-based spectrometer and its demonstration in radioactive cesium contamination sites 基于Ce:GPS闪烁体的光谱仪的研制及其在放射性铯污染现场的演示

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-08-29 DOI: 10.1016/j.radmeas.2025.107513

Yuki Morishita , Shigeo Nakama , Kotaro Ochi , Yoshimi Urabe , Marina Kanno

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.

福岛第一核电站事故后，放射性铯污染引发了严重的环境问题。本研究利用Gd2Si2O7:Ce （Ce:GPS）闪烁体和紧凑型光电倍增管（PMT）开发了一种紧凑型伽马射线光谱仪，用于环境监测。该光谱仪旨在克服传统NaI（Tl）探测器的局限性，利用Ce:GPS闪烁体的非吸湿性和高能量分辨率。通过对a137Cs源的测量以及与商用NaI（Tl）测量仪的比较来评估其性能。证明了该光谱仪在污染环境中有效、便携监测放射性铯的潜力。该系统使用密封光源进行了测试，证实其能够以高精度检测137Cs的662 keV光峰。该峰的能量分辨率为10.8% FWHM。在放射性污染地区的现场测量表明，该光谱仪在检测剂量率变化和高剂量热点方面是有效的。这种便携式、耐用的光谱仪在环境辐射监测和遥感技术中显示出应用前景。

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引用次数: 0

Combined detection method of LET measurement using CR-39 and TLD in carbon ion radiotherapy CR-39与TLD在碳离子放疗中LET测量的联合检测方法

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-08-18 DOI: 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 LET_d 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.

碳离子治疗场中线性能量传递（LET）分布的测量对于优化束流质量控制和提高治疗效果至关重要。为了满足精确LET测量的需求，本研究引入了一种集成CR-39和热释光剂量计（tld）的新型组合探测器。利用每个探测器各自的优势，开发了一种估计LET光谱的新方法。验证实验和在水和肺幻影中的应用表明，与单独使用任何一种检测器相比，组合检测器显着提高了测量精度。LETd测量的相对偏差控制在15%以内。这些发现表明，集成的检测器系统对于碳离子治疗中LET分布的测量是非常有效的，具有巨大的临床应用潜力。

引用次数: 0

Weighing options for passive environmental neutron dosimetry: A comparative study of PADCs, TLDs, OSLDs, and fission track detectors 被动环境中子剂量计的称重选择：padc、tld、osld和裂变径迹探测器的比较研究

IF 2.2 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2025-08-16 DOI: 10.1016/j.radmeas.2025.107504

Lily Bossin, Jeppe Brage Christensen, Federico Alejandro Geser, Malgorzata Kasprzak, Sabine Mayer, Malgorzata Sliz, Alberto Stabilini, Eduardo Gardenali Yukihara

This study aims to evaluate the potential of polyallyl diglycol carbonate (PADC) detectors, coupled with

^{6}

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

H^{*} (10)

=6 μ Sv for PADC detectors coupled with

^{6}

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

^{6}

LiF converter system as a robust alternative to fission track detectors for passive environmental neutron dosimetry.

本研究旨在评估PADC（聚烯丙基二甘醇碳酸酯）探测器和6liff转换器在被动环境中子剂量测定中的应用潜力。将它们的性能与其他三种方法（裂变径迹探测器、热释光探测器（tld）和光激发发光探测器（osld））进行比较，以确定它们在环境设置中被动常规中子监测的可行性。所研究的四种探测器类型（padc、裂变径迹、TLDs和osld）被放置在慢化剂球中并暴露在AmBe中子场中。测量评估了每个系统的剂量反应、测量范围和精度。结果证实了径迹探测器（PADC或裂变径迹）的优点是它们的伽马不敏感：TLD和OSLD方法需要中子敏感和中子不敏感探测器的结合，因为两者都是伽马敏感的。这意味着与6LiF转换器耦合的PADC探测器的检测极限H * (10)=6 μ Sv，与裂变径迹探测器的检测极限（3 μ Sv）相当。相比之下，在AmBe中子辐照下，伽马敏感发光系统对TLDs的检测限为10 μ Sv，对OSLDs的检测限为180 μ Sv。在模拟环境条件下，这种情况会恶化，因为在模拟环境条件下，使用混合伽马/中子辐照的测试表明，伽马对辐射的贡献很大。这些结果表明，PADC与6LiF变换器系统耦合的潜力，作为被动环境中子剂量测定的裂变径迹探测器的强大替代品。

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