Radiation Measurements最新文献_第9页

Using neutron-neutron angular correlation as a complementary observable in the fast neutron multiplicity counting for low-quality nuclear materials 在低质量核材料快中子多重计数中使用中子-中子角相关作为互补观测

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

Radiation Measurements

Pub Date : 2025-12-01 Epub Date: 2025-10-24 DOI: 10.1016/j.radmeas.2025.107541

Kaile Li, Peng Xu, Sufen Li, Jiangyu Yan

In the process of nuclear fission, due to the momentum enhancement of the fission fragments, the neutrons will exhibit angular correlation. For a certain class of problem the emergent n-n angular correlation trends with multiplication. Using the scintillation array can simultaneously obtain time and angle information of fission neutrons. Therefore, this paper make an exploratory study of the potential of using neutron-neutron angular correlation as a complementary observable in the fast neutron multiplicity counting. This paper explores the intrinsic relationship between neutron anisotropy and multiplication coefficient, and neutron anisotropy can be used as a reference to reflect multiplication coefficient On this basis, the fission neutron anisotropy was quantified with the ratio of neutron–neutron coincidences observed at 180° and 90°. Fitting the neutron leakage multiplication coefficient and anisotropy. After measuring the anisotropy of the sample, the leakage multiplication coefficient can be obtained through this fitting relationship, and then combine it with fast neutron multiplicity to solve the mass of nuclear material,. The results were verified through simulation calculations by Geant4. The deviation of the results obtained by using this method is significantly lower than that obtained by using the fast neutron multiplicity method. This method can be used for estimate the quality properties of nuclear materials, but is not intended for the assay of completely unknown items. Instead, we reframe its potential application for situations where a item's general class is known.

在核裂变过程中，由于裂变碎片的动量增强，中子会表现出角相关。对于一类问题，出现的n-n角相关趋势与乘法有关。利用闪烁阵列可以同时获得裂变中子的时间和角度信息。因此，本文对中子-中子角相关作为互补观测在快中子多重计数中的潜力进行了探索性研究。本文探讨了中子各向异性与倍增系数之间的内在关系，中子各向异性可以作为反映倍增系数的参考。在此基础上，用180°和90°处观测到的中子-中子符合率来量化裂变中子各向异性。拟合中子泄漏倍增系数和各向异性。测量样品的各向异性后，可以通过这种拟合关系得到泄漏倍增系数，然后将其与快中子多重度结合，求解核材料的质量。通过Geant4的仿真计算验证了结果。与快中子多重度法相比，该方法得到的结果偏差明显小于快中子多重度法。该方法可用于估计核材料的质量性质，但不适用于完全未知项目的测定。相反，我们重新定义了它的潜在应用程序，以用于已知项的一般类的情况。

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引用次数: 0

Utilizing the coincidence and anti-coincidence counting of crosstalk events to enhance measurement accuracy in BNCT-SPECT 利用串扰事件的符合计数和反符合计数来提高ct - spect的测量精度

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

Radiation Measurements

Pub Date : 2025-12-01 Epub Date: 2025-10-14 DOI: 10.1016/j.radmeas.2025.107538

Yu Fujiwara, Mana Miyagawa, Mikito Yagura, Jiye Qiu, Shingo Tamaki, Sachie Kusaka, Fuminobu Sato, Isao Murata

Single Photon Emission Computed Tomography (SPECT) in Boron Neutron Capture Therapy (BNCT) plays a vital role in real-time monitoring of treatment effects. However, image quality can be degraded by background noise. We propose a novel noise-reduction technique that utilizes both coincidence and anti-coincidence counting methods, leveraging the crosstalk phenomenon between adjacent scintillators. To evaluate the feasibility of this approach, we measured γ-ray spectra from a¹³⁷Cs standard source using two GAGG scintillators. The results showed noise reduction improvements of 15.9 % with coincidence and 3.8 % with anti-coincidence methods. Additionally, theoretical analysis demonstrated that this approach is effective in multiple scintillators arranged by the forward nature of Compton Scattering. This approach offers a promising path toward improving BNCT-SPECT imaging quality by effectively discriminating target signals from noise in high-density detector arrays.

单光子发射计算机断层扫描（SPECT）在硼中子俘获治疗（BNCT）中的实时监测治疗效果起着至关重要的作用。但是，背景噪声会降低图像质量。我们提出了一种新的降噪技术，利用符合和反符合计数方法，利用相邻闪烁体之间的串扰现象。为了评估这种方法的可行性，我们使用两个GAGG闪烁体测量了a137Cs标准源的γ射线光谱。结果表明，采用符合方法降噪15.9%，采用反符合方法降噪3.8%。此外，理论分析表明，该方法在康普顿散射正向排列的多闪烁体中是有效的。该方法通过在高密度探测器阵列中有效区分目标信号和噪声，为提高BNCT-SPECT成像质量提供了一条有希望的途径。

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引用次数: 0

Glow curve deconvolution – Why are most published results wrong? Common pitfalls in measurement and analysis 辉光曲线反褶积——为什么大多数已发表的结果都是错误的？测量和分析中的常见缺陷

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

Radiation Measurements

Pub Date : 2025-12-01 Epub Date: 2025-10-09 DOI: 10.1016/j.radmeas.2025.107537

Stephen W.S. McKeever

The published literature is full of reports claiming to determine the trapping parameters – trap depth (E_t, eV), frequency factor (s, s⁻¹) and kinetic order (b) – from thermoluminescence (TL) glow curves. In recent years probably the most popular approaches employ ‘Computerized Glow Curve Deconvolution’ methods of fitting the glow curve using standard TL equations. Regrettably, most of these efforts are at best unreliable and at worst simply wrong. This paper illustrates that, in order to accept the published results with a degree of confidence, the details of the experimental method and the appropriateness of the theory used must both be examined carefully. Examples of poor experimental method include inadequate temperature control (e.g. measuring the temperature of the heater, not the sample), ignoring changes in luminescence efficiency with increasing temperature (thermal quenching), and no, or improper, consideration of the emission spectrum (i.e. whether it is constant as the temperature changes). Examples of inappropriate theory include the use of General-Order Kinetics when this is unjustified. This results from an apparent misunderstanding of TL kinetics when dealing with systems described by multiple-trap/multiple-recombination-site models. Most published analyses assume non-interactive kinetics between the various trapping and recombination sites and treat each trap as isolated from all other traps and from the recombination sites. This paper discusses these issues in detail and concludes that once the glow curves are properly obtained, deconvolution analysis should consider the potential for localized recombination (including thermally excited tunneling) and, if delocalized recombination dominates, only first-order kinetics should be used in almost all examples, with the possible exception of the highest-temperature TL peak for which second-order kinetics may apply.

已发表的文献中充满了声称从热释光（TL）发光曲线确定捕获参数-捕获深度（Et, eV），频率因子（s, s−1）和动力学顺序(b)的报告。近年来，可能最流行的方法采用“计算机辉光曲线反褶积”方法拟合辉光曲线使用标准TL方程。遗憾的是，这些努力往好里说是不可靠的，往坏里说是完全错误的。本文说明，为了有信心地接受已发表的结果，必须仔细检查实验方法的细节和所使用理论的适当性。较差的实验方法包括温度控制不充分（例如测量加热器的温度，而不是样品的温度），忽略发光效率随温度升高的变化（热猝灭），没有或不适当考虑发射光谱（即是否随温度变化而恒定）。不恰当理论的例子包括在不合理的情况下使用一般级动力学。这是由于在处理由多陷阱/多重组位点模型描述的系统时对TL动力学的明显误解。大多数已发表的分析假设各种捕获和重组位点之间的非相互作用动力学，并将每个陷阱与所有其他陷阱和重组位点隔离开来。本文详细讨论了这些问题，并得出结论，一旦正确获得发光曲线，反褶积分析应考虑局域复合的潜力（包括热激发隧道），如果非局域复合占主导地位，则几乎所有例子都应只使用一级动力学，除了可能适用二阶动力学的最高温度TL峰。

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引用次数: 0

Calculation and verification of energy deposition by high-energy deuterons in thick beryllium target 高能氘核在厚铍靶中的能量沉积计算与验证

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

Radiation Measurements

Pub Date : 2025-12-01 Epub Date: 2025-09-29 DOI: 10.1016/j.radmeas.2025.107530

Zhichao Gao , Xueying Zhang , Yongqin Ju , Rui Han , Honglin Ge , Fei Ma , Yanbin Zhang , Bin Zhou , Liang Chen , GuoYu Tian , Tao Wan , Yaoxuan Cui , Wenli Qu

The d-Be neutron source is a compact accelerator neutron source with significant potential. The energy deposition of a high-energy deuteron beam in beryllium target serves as an important reference consideration in the design of target heat removal systems. The total energy deposition of deuterons, energy deposition linear density, and the contributions of different secondary particles in thick beryllium targets is investigated using Geant4 toolkit with three reaction models. Additionally, we conducted an experiment of a 300 MeV deuteron beam bombarding thick beryllium targets, where multiple thermoluminescent detectors were used to measure the dose distribution in targets. The comparison between simulation results and experimental data indicate that the Geant4 simulation effectively estimates the energy deposition of the d-Be reactions, with the BIC_AllHP model showing the best agreement with the experimental data.

d-Be中子源是一种紧凑的加速器中子源，具有显著的潜力。高能氘核束在铍靶中的能量沉积是靶热系统设计的重要参考因素。利用Geant4工具和三种反应模型，研究了厚铍靶中氘核的总能量沉积、能量沉积线密度以及不同二次粒子的贡献。此外，我们还进行了300 MeV氘核束轰击厚铍靶的实验，使用多个热释光探测器测量靶内的剂量分布。模拟结果与实验数据的比较表明，Geant4模拟能有效地估计d-Be反应的能量沉积，其中BIC_AllHP模型与实验数据最吻合。

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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 : 2025-12-01 Epub 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

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 : 2025-12-01 Epub 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 homogeneous thick-walled graphite cylindrical ionization chamber for determination of source strength of HDR 60Co brachytherapy sources 一种均匀厚壁石墨圆柱形电离室的研制，用于测定HDR 60Co近距离治疗源的强度

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

Radiation Measurements

Pub Date : 2025-12-01 Epub Date: 2025-10-07 DOI: 10.1016/j.radmeas.2025.107535

Sudhir Kumar , Rahul Kumar Chaudhary , S.D. Sharma , B.K. Sapra

Purpose

The source strength of brachytherapy sources should be verified prior to their clinical use. To fulfil the requirement for the standardization of high-dose rate (HDR) ⁶⁰Co brachytherapy sources, a homogeneous thick-walled graphite cylindrical ionization chamber of nominal sensitive volume 223.5 cm³ was designed, developed and established as a reference standard.

Methods

Experimental measurements were conducted with HDR ⁶⁰Co brachytherapy sources at different radiotherapy centres across India to determine the basic characteristics of this ionization chamber. The reference air-kerma rate,

{\overset{\cdot}{K}}_{R}

, of the HDR ⁶⁰Co sources was determined from the measured signal using the air-kerma calibration coefficient formalism developed earlier analytically based on Burlin general cavity theory and large cavity theory and validated with Monte-Carlo calculations.

Results

The basic characteristics of this chamber were in conformity with requirements specified in IAEA TRS-374 report. The

{\overset{\cdot}{K}}_{R}

of HDR ⁶⁰Co sources determined experimentally using this chamber was within 3 % of the

{\overset{\cdot}{K}}_{R}

value quoted by the supplier, which is traceable to PTB, Germany. The standardized HDR ⁶⁰Co sources were used for calibrating the eight well-type ionization chambers of different radiotherapy centres and the values of air-kerma calibration coefficient

N_{{\overset{\cdot}{K}}_{R}}

so obtained agreed within 3 % of the vendor-quoted values.

Conclusion

The performance of the newly developed chamber was found to be satisfactory and it qualifies to be designated as a reference standard for the measurement of

{\overset{\cdot}{K}}_{R}

of HDR ⁶⁰Co sources and for calibration of the well-type chambers of radiotherapy centres.

目的近距离放射治疗源的强度在临床使用前应进行验证。为满足高剂量率（HDR） 60Co近距离放射治疗源标准化要求，设计、研制并建立了标称敏感体积为223.5 cm3的均匀厚壁石墨圆柱形电离室作为参考标准。方法利用印度不同放射治疗中心的HDR 60Co近距离放射治疗源进行实验测量，确定该电离室的基本特性。HDR 60Co源的参考空气-克尔玛率K·R由测量信号确定，采用先前基于Burlin一般腔理论和大腔理论解析开发的空气-克尔玛校准系数公式，并通过蒙特卡罗计算进行验证。结果该试验箱的基本特性符合IAEA TRS-374报告的要求。使用该实验箱实验测定的HDR 60Co源的K·R与供应商报价的K·R值相差3%以内，该供应商可追溯到德国PTB。标准化的HDR 60Co源用于校准不同放射治疗中心的8个井型电离室，由此获得的空气-克尔曼校准系数NK·R值在供应商报价的3%以内一致。结论所研制的腔体性能良好，可作为HDR 60Co源K·R测量和放疗中心井型腔体标定的参考标准。

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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 : 2025-12-01 Epub 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

Drastic reduction of the slow scintillation component in highly luminescent Ce3+ and Mg2+ doped Lu2.5Gd0.5Ga2Al3O12 garnet powders 在高发光的Ce3+和Mg2+掺杂的Lu2.5Gd0.5Ga2Al3O12石榴石粉末中，慢闪烁成分急剧减少

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

Radiation Measurements

Pub Date : 2025-12-01 Epub Date: 2025-10-22 DOI: 10.1016/j.radmeas.2025.107542

Lenka Prouzová Procházková , Eliška Müllerová , Jan Bárta , Estelle Homeyer , Alena Zavadilová , Christophe Dujardin , Václav Čuba

This paper deals with the photochemical preparation of nanomaterials with garnet structure. Ce³⁺ and Mg²⁺ doped Lu_2.5Gd_0.5Ga₂Al₃O₁₂ powders were prepared by using UV irradiation of aqueous solutions with low-pressure mercury lamps and subsequent calcination of the solid products. The synthesis was optimized and gives access to a range of doping which is very hard to achieve with single crystal growth from melt. The effect of Ce and Mg concentration on the structural and luminescence properties was studied. Garnets were analyzed using X-ray fluorescence (XRF) and X-ray powder diffraction (XRPD) and their luminescence properties under optical and X-ray photon excitations were investigated. XRF and XRD show that the samples are sufficiently chemically pure and phase-pure and their elemental composition corresponds with expectations. Laser-induced breakdown spectroscopy confirmed that Mg concentrations in Mg-codoped samples are slightly lower than the nominal. Luminescence spectra show typical emission maxima of 5d-4f Ce³⁺ transition and 4f-4f Gd³⁺ transition. The effects of the concentration of Ce³⁺ and Mg²⁺ on the RL intensity, light yields and decays were observed.

本文研究了石榴石结构纳米材料的光化学制备。采用低压汞灯紫外照射水溶液，煅烧固体产物，制备了Ce3+和Mg2+掺杂Lu2.5Gd0.5Ga2Al3O12粉末。该合成得到了优化，并提供了一系列的掺杂，这是很难从熔体中获得单晶生长。研究了Ce和Mg浓度对结构和发光性能的影响。采用x射线荧光（XRF）和x射线粉末衍射（XRPD）对石榴石进行了分析，研究了石榴石在光学和x射线光子激发下的发光特性。XRF和XRD表明，样品具有足够的化学纯度和相纯性，元素组成符合预期。激光诱导击穿光谱证实，Mg共掺杂样品中的Mg浓度略低于标称浓度。发光光谱显示5d-4f Ce3+跃迁和4f-4f Gd3+跃迁的典型发射最大值。观察了Ce3+和Mg2+浓度对RL强度、产光率和衰减的影响。

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引用次数: 0

Investigation of thermal neutron/gamma discrimination capability of a CLYC Scintillator with a SiPM in a mixed field of 241Am-Be neutron source: Pulse shape discrimination using constant fraction time over threshold (CF-TOT) and cumulative charge ratio (CCR) 带有SiPM的CLYC闪烁体在241Am-Be中子源混合场中热中子/伽马识别能力的研究：利用恒分数阈值时间（CF-TOT）和累积电荷比（CCR）进行脉冲形状识别

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

Radiation Measurements

Pub Date : 2025-12-01 Epub Date: 2025-10-17 DOI: 10.1016/j.radmeas.2025.107540

Haluk Yücel , Ege Can Karanfil , Mehmet Can Karaman , Okay Tüzel , Zeynep Dağıstan , Kadir Özgür Hanci , Miray Özkan

In this study, neutron detection and neutron/gamma discrimination capability of a 99 % ⁶Li enriched CLYC (Cs₂LiYCl₆:Ce) scintillator detector module incorporating a built-in microcontroller-based MCA featuring analog-signal processing for pulse shape discrimination method is investigated. This miniature detector module has a small-sized

15 \times 15 \times 25 m m^{3}

CLYC crystal, optically coupled with Silicon Photomultiplier (SiPM). It uses a temperature compensated bias supply. The analog-signal processing components of this compact detector system implement the constant fraction time over threshold (CF-TOT) and cumulative charge ratio (CCR) methods for the pulse shape discrimination. The neutron/gamma measurements were performed in a thermalized neutron field having a thermal neutron flux of 2.11 × 10³ n∙cm⁻²∙s⁻¹ of an ²⁴¹Am-Be neutron source. The obtained pulse-height spectra is stored in a 4096 channels ADC/MCA. From the observed spectra, noise and low-energy events are lying quite far from neutron and gamma pulses. The figure of merit (FoM) criteria for the performance of PSD method was estimated to be 1.274. This means that the presently developed compact neutron detector system based on CLYC scintillation crystal has a good thermal neutron/gamma discrimination capability although there are high energy gamma-ray in the field. Thus, this compact device can be a versatile device for measuring thermal neutron fluxes in space-constrained or portable applications such as small ducts or openings. Moreover, it has a potential use for the detection of neutrons in the mixed fields from micro-modular (MMR) reactors or small modular reactor (SMR) environments.

在这项研究中，研究了含有内置微控制器的MCA的99% 6Li富集CLYC （Cs2LiYCl6:Ce）闪烁体探测器模块的中子探测和中子/伽马识别能力，该模块具有用于脉冲形状识别方法的模拟信号处理。这个微型探测器模块有一个小尺寸的15×15×25mm3 CLYC晶体，与硅光电倍增管（SiPM）光学耦合。它使用温度补偿偏置电源。该系统的模拟信号处理组件实现了恒分数阈值时间（CF-TOT）和累积电荷比（CCR）方法进行脉冲形状判别。中子/伽马测量是在241Am-Be中子源的热中子场中进行的，热中子通量为2.11 × 103 n∙cm−2∙s−1。得到的脉冲高度谱存储在4096通道ADC/MCA中。从观测到的光谱来看，噪声和低能事件离中子和伽马脉冲很远。评价PSD方法性能的优点值（FoM）标准估计为1.274。这意味着目前研制的基于CLYC闪烁晶体的紧凑型中子探测器系统，尽管存在高能伽玛射线，但仍具有良好的热中子/伽玛识别能力。因此，这种紧凑的装置可以是一个多功能的装置，用于测量空间受限或便携式应用，如小管道或开口的热中子通量。此外，它在微模块反应堆（MMR）或小模块反应堆（SMR）环境中混合场的中子探测方面具有潜在的用途。

{"title":"Investigation of thermal neutron/gamma discrimination capability of a CLYC Scintillator with a SiPM in a mixed field of 241Am-Be neutron source: Pulse shape discrimination using constant fraction time over threshold (CF-TOT) and cumulative charge ratio (CCR)","authors":"Haluk Yücel , Ege Can Karanfil , Mehmet Can Karaman , Okay Tüzel , Zeynep Dağıstan , Kadir Özgür Hanci , Miray Özkan","doi":"10.1016/j.radmeas.2025.107540","DOIUrl":"10.1016/j.radmeas.2025.107540","url":null,"abstract":"<div><div>In this study, neutron detection and neutron/gamma discrimination capability of a 99 % <sup>6</sup>Li enriched CLYC (Cs<sub>2</sub>LiYCl<sub>6</sub>:Ce) scintillator detector module incorporating a built-in microcontroller-based MCA featuring analog-signal processing for pulse shape discrimination method is investigated. This miniature detector module has a small-sized <span><math><mrow><mn>15</mn><mo>×</mo><mn>15</mn><mo>×</mo><mn>25</mn><mspace></mspace><mi>m</mi><msup><mi>m</mi><mn>3</mn></msup></mrow></math></span> CLYC crystal, optically coupled with Silicon Photomultiplier (SiPM). It uses a temperature compensated bias supply. The analog-signal processing components of this compact detector system implement the constant fraction time over threshold (CF-TOT) and cumulative charge ratio (CCR) methods for the pulse shape discrimination. The neutron/gamma measurements were performed in a thermalized neutron field having a thermal neutron flux of 2.11 × 10<sup>3</sup> n∙cm<sup>−2</sup>∙s<sup>−1</sup> of an <sup>241</sup>Am-Be neutron source. The obtained pulse-height spectra is stored in a 4096 channels ADC/MCA. From the observed spectra, noise and low-energy events are lying quite far from neutron and gamma pulses. The figure of merit (FoM) criteria for the performance of PSD method was estimated to be 1.274. This means that the presently developed compact neutron detector system based on CLYC scintillation crystal has a good thermal neutron/gamma discrimination capability although there are high energy gamma-ray in the field. Thus, this compact device can be a versatile device for measuring thermal neutron fluxes in space-constrained or portable applications such as small ducts or openings. Moreover, it has a potential use for the detection of neutrons in the mixed fields from micro-modular (MMR) reactors or small modular reactor (SMR) environments.</div></div>","PeriodicalId":21055,"journal":{"name":"Radiation Measurements","volume":"189 ","pages":"Article 107540"},"PeriodicalIF":2.2,"publicationDate":"2025-12-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145363317","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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