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Modeling the stochastic-deterministic boundary in luminescence: Consequences for dose estimation 模拟发光的随机-确定性边界:剂量估计的后果
IF 2.2 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-09-19 DOI: 10.1016/j.radmeas.2025.107529
Eren Şahiner
Kinetic models based on deterministic ordinary differential equations (ODEs) are effective for macroscopic systems, but a breakdown of their foundational assumptions is observed for single-grain and nanodosimetric applications where particle numbers are small. In this study, the metrological consequences of this stochastic-deterministic divergence are quantitatively investigated. The study's primary contribution is to deconvolve the divergence into two distinct components: a robust, inherent imprecision and a model-dependent, systematic inaccuracy. Intrinsic physical stochasticity is confirmed to be a dominant source of imprecision, generating an irreducible dose uncertainty of over 20 % that accounts for a significant fraction of single-grain overdispersion. Conversely, a systematic inaccuracy (e.g., a >50 % dose bias), initially observed in a simplified model, is demonstrated to be a methodological artifact, not a universal consequence of discreteness. It is shown that this systematic bias can be reduced to negligible levels (<1 %) by using either a more physically realistic multi-trap model or a correctly specified simple model. Based on this deconvolution, analytical protocols are assessed. An "Average-Dose-First" protocol is identified as the superior method, as it provides an accurate final dose estimate while correctly propagating measurement uncertainty. A general framework for understanding and partitioning variance in luminescence data is thereby established. Practical recommendations are provided for improving the accuracy of modern luminescence science by selecting appropriate models and using correct statistical protocols, with a strong emphasis on the critical need for model validation.
基于确定性常微分方程(ode)的动力学模型对宏观系统是有效的,但在颗粒数较小的单粒和纳米剂量学应用中,它们的基本假设被破坏了。在本研究中,定量研究了这种随机确定性发散的计量后果。这项研究的主要贡献是将这种差异解卷积为两个不同的组成部分:一个是强大的、固有的不精确性,另一个是依赖于模型的、系统的不精确性。固有的物理随机性被证实是不精确的主要来源,产生超过20%的不可减少的剂量不确定性,这占单粒过度分散的很大一部分。相反,最初在简化模型中观察到的系统性不准确性(例如,50%剂量偏差)被证明是方法学上的人为因素,而不是离散性的普遍后果。研究表明,通过使用更实际的多陷阱模型或正确指定的简单模型,这种系统偏差可以减少到可以忽略不计的水平(< 1%)。基于这种反褶积,分析方案被评估。“平均剂量优先”方案被认为是优越的方法,因为它在正确传播测量不确定度的同时提供了准确的最终剂量估计。从而建立了理解和划分发光数据方差的一般框架。通过选择合适的模型和使用正确的统计协议,为提高现代发光科学的准确性提供了实用的建议,并强调了对模型验证的迫切需要。
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引用次数: 0
Application of deep learning-based track detection technique in neutron personal dose monitoring research 基于深度学习的轨迹检测技术在中子个人剂量监测研究中的应用
IF 2.2 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-09-18 DOI: 10.1016/j.radmeas.2025.107526
Yuji Miao , Wei Chen , Lu Tian , Xiaodong Shi , Yuanyuan Zhou , Xiangyong Fan , Jiayi Ma , Jin Wang
This study introduces the application of the object detection paradigm (Faster R-CNN) to fast neutron track detection using deep learning algorithms. Neutron dose measurements were conducted using CR-39 detectors, and two methods-morphological features-based detection and deep learning (Faster R-CNN) were evaluated. The deep learning method demonstrated superior accuracy, particularly in identifying small tracks and impurity points, achieving a correct-count rate of 98.7 %. Additionally, it significantly improved detection speed compared to manual and morphological feature-based methods. The performance of the neutron personal dosimetry system, which incorporates the deep learning approach, was validated through linearity validation, coefficient of variation analysis, and dose verification. Due to its fully automated nature, this method can reduce measurement uncertainty and can be extended to recognize other types of particle tracks.
本研究介绍了使用深度学习算法的目标检测范式(Faster R-CNN)在快中子轨道检测中的应用。使用CR-39探测器进行中子剂量测量,并评估两种方法-基于形态学特征的检测和深度学习(Faster R-CNN)。深度学习方法显示出优越的准确性,特别是在识别小轨迹和杂质点方面,达到了98.7%的正确率。此外,与人工和基于形态学特征的方法相比,该方法显著提高了检测速度。采用深度学习方法的中子个人剂量测定系统的性能通过线性验证、变异系数分析和剂量验证进行了验证。由于其完全自动化的性质,该方法可以降低测量的不确定度,并可以扩展到识别其他类型的粒子轨迹。
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引用次数: 0
Copper-based halide Cs3Cu2I5: (X) bulk single crystals: Growth and applications 铜基卤化物Cs3Cu2I5: (X)块状单晶:生长与应用
IF 2.2 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2025-09-18 DOI: 10.1016/j.radmeas.2025.107527
Jianjia Li, Yunfei Ren, Zhicheng Wang, Xiaoming Li
Low-dimensional copper-based halides have garnered wide attention due to their strong self-trapped exciton (STE) emission, among which, Cs3Cu2I5 (CCI), characterized by a zero-dimensional electronic structure, exhibits promising application potential across multiple fields owing to its non-toxicity and excellent environmental stability. Notably, its exceptional radioluminescence properties make it an outstanding scintillator material for high-energy radiation detection. In recent years, although reports on diverse CCI material morphologies abound, bulk single crystals have become the primary focus because of their superior light output and low defect density. In this review, we systematically summarize and discuss the growth methodologies and applications of CCI bulk single crystals, which encompasses both melt and solution growth techniques, as well as currently developed and potentially superior application scenarios. Furthermore, we dedicate a section to discuss doping engineering strategies applied to CCI materials and the resultant property enhancements. Finally, the key challenges and future research directions for CCI bulk single crystals are outlined.
低维铜基卤化物因其强烈的自俘获激子(STE)发射而受到广泛关注,其中,Cs3Cu2I5 (CCI)具有零维电子结构,具有无毒性和优异的环境稳定性,在多个领域具有广阔的应用前景。值得注意的是,其特殊的辐射发光特性使其成为高能辐射探测的杰出闪烁体材料。近年来,尽管各种CCI材料形态的报道很多,但大块单晶由于其优越的光输出和低缺陷密度而成为主要焦点。在本文中,我们系统地总结和讨论了CCI块体单晶的生长方法和应用,包括熔体和溶液生长技术,以及目前发展和潜在的应用场景。此外,我们还专门讨论了应用于CCI材料的掺杂工程策略以及由此产生的性能增强。最后,对CCI本体单晶的关键挑战和未来的研究方向进行了概述。
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引用次数: 0
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 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 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 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 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 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 (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.
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。
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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 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)114Cd 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×22 mm×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%±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。
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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 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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Radiation Measurements
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