Nuclear Analysis最新文献_第3页

Recent advancements of organic scintillators in enhancing the performance of fast neutron detection: A review 有机闪烁体在提高快中子探测性能方面的最新进展综述

Nuclear Analysis

Pub Date : 2025-03-26 DOI: 10.1016/j.nucana.2025.100171

D. Arun Kumar , E. Parthiban

Recent advancements in organic scintillators with neutron-gamma discrimination properties have significantly enhanced the performance of fast neutron detection, addressing critical needs in high energy physics, radiation therapy, homeland securities and well-logging industry. In this review, we summarize the latest developments in single-crystal organic materials focusing on their high light yield, excellent neutron-gamma discrimination and fast decay times. The first part of the review involves principles of scintillation, physical phenomenon and its mechanism of organic scintillation crystals. The second part presents the organic scintillation materials for fast neutron detection and its properties. Finally, in the third part delves into the potential applications and future prospects of organic scintillators, emphasizing their versatility in various detection systems. The findings underscore the pivotal role of organic scintillators in advancing fast neutron detection technology, paving the way for more efficient and reliable radiation monitoring solutions.

近年来，具有中子-伽马识别特性的有机闪烁体的进展显著提高了快中子探测的性能，解决了高能物理、放射治疗、国土安全和测井行业的关键需求。本文综述了单晶有机材料的最新研究进展，重点介绍了单晶有机材料的高光产率、优异的中子- γ鉴别和快速衰减时间。第一部分综述了有机闪烁晶体的闪烁原理、物理现象及其机理。第二部分介绍了用于快中子探测的有机闪烁材料及其性质。最后，第三部分深入探讨了有机闪烁体的潜在应用和未来前景，强调了它们在各种检测系统中的通用性。这一发现强调了有机闪烁体在推进快中子探测技术方面的关键作用，为更有效、更可靠的辐射监测解决方案铺平了道路。

引用次数: 0

Dose distribution comparison using image registration principles 基于图像配准原理的剂量分布比较

Nuclear Analysis

Pub Date : 2025-03-24 DOI: 10.1016/j.nucana.2025.100170

Meryeme Bellahsaouia , Ibtissam Zidouh , Ouadie Kabach , Wafae Chfeq , Assia Arctout , Taher Elkhoukhi , Elmahjoub Chakir

Radiotherapy relies on accurate dose distribution comparison methods, but current approaches have limitations. This study introduces a novel algorithm based on image registration principles to address these limitations. The algorithm uses a transformation matrix derived from image registration to align an evaluated dose distribution with a reference distribution. This transformation employs multiple steps: detecting keypoints, constructing descriptors, matching keypoints, and estimating an affine transformation matrix. The transformed distribution is then directly comparable to the reference through linear least squares regression. Validation on 174 dose distribution pairs demonstrated robust performance, with bias and precision within clinically acceptable limits. Linearity assessments confirmed consistent behavior across a wide range of dose intensities. Comparisons with gamma analysis showed substantial agreement (Cohen's Kappa: 0.77), while additional metrics highlighted its clinical suitability: precision (0.98), recall (0.95), accuracy (0.94), specificity (0.86), and F1-score (0.96). These results establish the algorithm as a promising complement to gamma analysis, with strong potential for clinical integration.

放射治疗依赖于精确的剂量分布比较方法，但目前的方法有局限性。本研究引入一种基于图像配准原理的新算法来解决这些限制。该算法使用图像配准导出的变换矩阵将评估的剂量分布与参考分布对齐。该变换采用多个步骤：检测关键点、构造描述符、匹配关键点和估计仿射变换矩阵。转换后的分布然后通过线性最小二乘回归与参考直接比较。174对剂量分布对的验证显示了稳健的性能，偏差和精度在临床可接受的范围内。线性评估证实了在大剂量强度范围内的一致行为。与伽玛分析的比较显示了大量的一致性（Cohen’s Kappa: 0.77），而其他指标强调了其临床适用性：精密度（0.98）、召回率（0.95）、准确度（0.94）、特异性（0.86）和f1评分（0.96）。这些结果确立了该算法作为伽马分析的一个有希望的补充，具有很强的临床整合潜力。

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引用次数: 0

Elastic scattering of Lithium induced nuclear reactions 锂诱导核反应的弹性散射

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100153

S. Madhu , Reddi Rani L. , H.C. Manjunatha , N. Sowmya , H.S. Anushree , Krishnakanth E.

A total of 347 experimentally accessible lithium-induced fusion reactions at various energies were analyzed. The study utilized real nuclear potential and volume imaginary potential within the optical model framework, with elastic cross-sections calculated using the FRESCO code. The value derived from the optical model agrees well with existing results at various scattering angles. The study refines existing empirical relations for elastic scattering by improving predictive accuracy and expanding their applicability to under explored reaction channels. Compared to previous models, our relations achieve better alignment with experimental data for lithium-induced reactions, particularly at higher energies. The standard deviation derived from the empirical relationship with that of experimental data is observed to be smaller. Elastic scattering cross-sections of

^{6, 7}

Li-induced fusion reactions are function of the Coulomb-interaction parameter and center of mass energy. As a result, the current methodology may be used to forecast elastic scattering cross-sections of

^{6, 7}

Li-induced fusion reactions in unknown isotopes of targets ranging from Li to Bi.

分析了347个不同能量的锂诱导聚变反应。该研究利用了光学模型框架内的真实核势和体积虚势，并使用FRESCO代码计算了弹性截面。在不同散射角下，光学模型的计算结果与已有的结果吻合较好。该研究通过提高弹性散射的预测精度和扩大其对未探明反应通道的适用性来完善现有的经验关系。与以前的模型相比，我们的关系与锂诱导反应的实验数据更好地吻合，特别是在更高的能量下。由经验关系得出的标准偏差与实验数据的标准偏差较小。6,7锂诱导聚变反应的弹性散射截面是库仑相互作用参数和质心能量的函数。因此，目前的方法可用于预测6,7li诱导聚变反应的弹性散射截面，这些聚变反应发生在从Li到Bi的未知目标同位素中。

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引用次数: 0

Use GIS technical to map natural radioactivity in soil samples for the University of Kufa, Iraq 利用GIS技术绘制伊拉克库法大学土壤样品中的天然放射性

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2024.100139

Abrrar Abbas Ibrahim , Abdalsattar K. Hashim , Ali Abid Abojassim

GIS "Geographic Information System" technology was used to map the specific activity (S.A.) of primordial radionuclides ²³⁸U, ²³²Th, and ⁴⁰K in selected soil samples for twelve locations at the University of Kufa, Iraq. S.A. values were determined using gamma spectrometry type NaI(Tl) with volume “3 × 3”. Also, the values of radiological parameters such as Ra_eq "radium equivalent", H_ex "external hazard index", I_γr "representative gamma risk index", D_r "Absorbed Dose rate", AEDE_outdoor "Annual Effective Dose Equivalent in outdoor", and ELCR "Excess Lifetime Cancer Risk" were determined. The average value of S.A. for ²³⁸U, ²³²Th, and ⁴⁰K was 10.35 ± 0.9 Bq/kg, 7.31 ± 1.8 Bq/kg, and 256.19 ± 55.7 Bq/kg, respectively. While, the average values of Ra_eq (Bq/kg), H_ex, I_γr, D_r (nGy/h), AEDE_outdoor (mSv/y), and ELCR were 48.00, 0.130, 0.373, 23.70, 0.029, and 0.102 × 10⁻³, respectively. The results of S.A. and each radiological parameter of the study area locations were low according to acceptable level reports by UNSCEAR, ICRP, and OCDE. Therefore, it can be concluded that the soil samples of the University of Kufa were safe.

利用GIS“地理信息系统”技术绘制了伊拉克库法大学12个地点土壤样品中原始放射性核素238U、232Th和40K的比活度（sa）。采用体积为“3 × 3”的γ能谱法测定sa值。测定放射学参数Raeq“镭当量”、Hex“外部危害指数”、i - γ - r“代表性伽马风险指数”、Dr“吸收剂量率”、AEDEoutdoor“室外年有效剂量当量”、ELCR“超额终身癌症风险”等。238U、232Th和40K的sa平均值分别为10.35±0.9 Bq/kg、7.31±1.8 Bq/kg和256.19±55.7 Bq/kg。Raeq （Bq/kg）、Hex、Iγr、Dr （nGy/h）、AEDEoutdoor （mSv/y）和ELCR的平均值分别为48.00、0.130、0.373、23.70、0.029和0.102 × 10−3。根据UNSCEAR、ICRP和OCDE的可接受水平报告，sa的结果和研究区域位置的各放射学参数均为低水平。因此，库法大学的土样是安全的。

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引用次数: 0

Measurement of natural radioactivity and assessment of radiological hazard indices in soil from Tirunelveli District, Tamil Nadu, India with statistical approach 印度泰米尔纳德邦Tirunelveli地区土壤天然放射性的测量和放射性危害指数的统计方法评估

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100156

T. Krishnamoorthi , Satyanarayan Bramha , S. Chandrasekaran , R. Ravichandaran , S. Sivakumar , R. Ravisankar

The activity concentrations of naturally occurring radionuclides ²³⁸U, ²³²Th, and ⁴⁰K were determined in 31 soil samples collected from the Tirunelveli District of Tamil Nadu using grid sampling method. Gamma-ray spectrometry was applied using NaI(Tl) detector and a PC-based MCA. The mean radioactivity concentrations of ²³⁸U, ²³²Th, and ⁴⁰K were found to be 12.98 Bq.kg^−1, 162.89 Bq.kg⁻¹ and 453.04 Bq.kg⁻¹, respectively. The spatial map of the radionuclides was drawn and is discussed. The radiological hazards associated with soils were determined using radium equivalent activity (Ra_eq), annual gonadal dose equivalent (AGDE), activity utilization index (AUI), internal hazard index (H_in) external hazard index (H_ex) and gamma representative level index (I_γ), were calculated. Results were discussed and compared with the internationally recommended approved values. Statistical method was used to determine the natural associations between samples and variables. This work may provide baseline data for future soil radioactive environmental monitoring and the results of the study can serve as a reference for future radiological assessments.

采用网格采样法测定了泰米尔纳德邦Tirunelveli地区31份土壤样品中天然存在的放射性核素238U、232Th和40K的活性浓度。伽玛射线能谱法采用NaI（Tl）检测器和基于pc的MCA。238U、232Th和40K的平均放射性浓度为12.98 Bq。kg−1,162.89 Bq。kg−1和453.04 Bq。公斤−1,分别。绘制了放射性核素的空间图，并进行了讨论。采用镭当量活度（Raeq）、年性腺剂量当量（AGDE）、活度利用指数（AUI）、内害指数（Hin）、外害指数（Hex）和γ代表性水平指数（Iγ）测定土壤放射性危害。结果进行了讨论，并与国际上推荐的认可值进行了比较。采用统计学方法确定样本与变量之间的自然关联。本工作可为今后土壤放射性环境监测提供基线数据，研究结果可为今后土壤放射性评价提供参考。

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引用次数: 0

Natural radioactivity assessments and radiological hazards in agricultural soils around mining activities in Karibib, Namibia 纳米比亚卡里比卜采矿活动周围农业土壤的自然放射性评估和放射性危害

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100155

Sylvanus Ameh Onjefu , Biere Peter Ebibuloami , Caspah Kamunda , Markus Hitila , Marius Kudumo Mutorwa , Jeya Kudi Kennedy , Euodia Hess , Damian C. Onwudiwe

A total of 17 soil samples were randomly collected from agricultural farms around mining areas from Karibib, Erongo region, Namibia. The samples were analyzed for natural radioactivity using a high purity germanium (HPGe) detector. The average activity concentrations of ²²⁶Ra, ²³²Th and ⁴⁰K were 80.80, 73.60, and 493.96 Bq.kg ^{– 1} respectively. The radiological assessments were calculated in terms of radium equivalent activity (224.09 Bq.kg ^{– 1}), absorbed dose rate (102.39 nGy h-¹), annual effective dose equivalent (indoor and outdoor) (1.26 mSv y ^{– 1} and 5.02 mSv y ^{– 1}) and the internal and external hazard indices (0.61) and (0.82) respectively. The average values of ²²⁶Ra, ²³²Th and ⁴⁰K were higher than the world average values as well as those of the radiological parameters of absorbed dose rate and annual effective dose equivalent. The average values of radium equivalent activity, and the indices radiological hazards were below the internationally acceptable limits.

从纳米比亚Erongo地区Karibib矿区周围的农场随机收集了17个土壤样本。使用高纯度锗（HPGe）探测器分析样品的天然放射性。226Ra、232Th和40K的平均活性浓度分别为80.80、73.60和493.96 Bq。分别是Kg - 1。放射学评估以镭当量活度（224.09 Bq）计算。kg -1)、吸收剂量率（102.39 nGy h-1）、年有效剂量当量（室内和室外）（1.26 mSv y -1和5.02 mSv y -1）以及内外危害指数（0.61）和（0.82）。226Ra、232Th和40K的平均值高于世界平均值，吸收剂量率和年有效剂量当量等放射学参数的平均值也高于世界平均值。镭当量活度平均值和辐射危害指数均低于国际可接受限值。

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引用次数: 0

Potential health risk assessment of sediment and water in some Niger Delta areas of Nigeria 尼日利亚一些尼日尔三角洲地区沉积物和水的潜在健康风险评估

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100159

Damaris Osiga-Aibangbee, Omamoke O.E. Enaroseha, Godwin K. Agbajor

The Niger Delta areas of Nigeria suffer substantial environmental issues owing to radionuclides pollution in sediment and water. These places are vital for local residents, supplying drinking water, food, and livelihoods. However, exposure to radionuclides causes health concerns to both people and aquatic species. This research examines health risk in sediment and water from some chosen locations in Delta State, Nigeria. Twelve (12) sediment samples and Twelve (12) water samples were randomly chosen and gathered from four communities at a depth of 10 cm, with each location giving 200 g of samples spaced of minimum of 50 m apart. Analysis was done at the CERD - IFE utilizing Gamma Ray Spectrometry, which contained a thallium-activated 16″x16″ Sodium iodide [NaI(Tl)] detector to quantify the activity concentrations of ²³⁸U, ²³²Th, and ⁴⁰K. The analysis indicated that activity concentrations in sediment samples for ⁴⁰K, ²³⁸U, and, ²³²Th varied from 294.29 ± 11.98 to 774.4 ± 10.92, 3.91 ± 0.06 to 14.13 ± 0.1, and 1.32 ± 0.05 to 5.29 ± 0.10 Bq/kg, respectively. In water samples, activity concentrations for ⁴⁰K, ²³⁸U, and, ²³²Th ranged from 232.32 ± 5.08 to 780.72 ± 9.31, 5.34 ± 0.06 to 11.29 ± 0.04, and 0.93 ± 0.04 to 3.07 ± 0.08 Bq/l, respectively. Base on health risk assessment, radium equivalent (Ra_eq) values ranged from 242.34 to 556.41 Bq/kg, with a mean value of 396.21 Bq/kg and was found to exceed the international standard of 370 Bq/kg. The discrepancies are due to geological differences and the existence of radioactive thorium materials, variable behavior and metabolism. Although radionuclide hazard indices suggest that the communities are safe from radiation, the long-term impacts of low-dose radiation exposure might pose health problems, hence frequent monitoring of radioactive levels in sediments and water is advised.

由于沉积物和水中的放射性核素污染，尼日利亚的尼日尔三角洲地区遭受严重的环境问题。这些地方对当地居民至关重要，为他们提供饮用水、食物和生计。然而，暴露于放射性核素会对人和水生物种造成健康问题。本研究考察了尼日利亚三角洲州一些选定地点沉积物和水中的健康风险。从四个群落中随机抽取12个沉积物样本和12个水样，采集深度为10厘米，每个位置间隔至少50米，采样量为200克。在CERD - IFE上使用伽马射线能谱仪进行分析，其中包含铊活化的16″x16″碘化钠[NaI(Tl)]探测器，以量化238U， 232Th和40K的活性浓度。分析表明，40K、238U和232Th在沉积物样品中的活性浓度变化范围分别为294.29±11.98 ~ 774.4±10.92、3.91±0.06 ~ 14.13±0.1和1.32±0.05 ~ 5.29±0.10 Bq/kg。在水样中，40K、238U和232Th的活度浓度分别为232.32±5.08 ~ 780.72±9.31、5.34±0.06 ~ 11.29±0.04和0.93±0.04 ~ 3.07±0.08 Bq/l。根据健康风险评估，镭当量（Raeq）值为242.34至556.41 Bq/kg，平均值为396.21 Bq/kg，超过370 Bq/kg的国际标准。这种差异是由于地质差异和放射性钍物质的存在、不同的行为和代谢所致。虽然放射性核素危害指数表明，社区是安全的，不受辐射影响，但低剂量辐射照射的长期影响可能造成健康问题，因此建议经常监测沉积物和水中的放射性水平。

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引用次数: 0

Chemical separation of uranium-233 from neutron-irradiated 232ThO2 targets using a dual-column technique 用双柱技术从中子辐照的232ThO2靶中分离铀-233

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100157

Yu Sun, Muxiao Wu, Jijun Guo, Qingchuan Lin, Jun Tu, Xiang Xie

Uranium-233 (²³³U) is an important synthetic isotope and used as isotope dilution references for safeguards, non-proliferation, and nuclear forensics measurements. In this work, the chemical separation of ²³³U from irradiated ²³²ThO₂ targets has been evaluated by a dual-column technique, where a stacked columns of Dowex 1 × 8 anion exchange resin and Dowex 50 × 8 cation exchange resin were applied. The dual-column method is simple with an overall ²³³U recovery yield of 98 ± 1 %. The isotope purity of ²³³U (>99 %) was confirmed and meeting the recommendations according to the quality requirements of isotope dilution mass spectrometry references.

铀-233 （233U）是一种重要的合成同位素，用作保障、不扩散和核取证测量的同位素稀释参考。本文采用Dowex 1 × 8阴离子交换树脂和Dowex 50 × 8阳离子交换树脂的双柱技术，对辐照232ThO2靶中233U的化学分离进行了研究。双柱法操作简单，总回收率为98±1%。根据同位素稀释质谱参考文献的质量要求，确认233U的同位素纯度为99%，符合推荐值。

引用次数: 0

Alpha emitter in samples of antibiotics commonly used in pediatric age groups 儿童年龄组常用抗生素样本中的α发射器

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100154

Ahmed Abdul Hadi Mohsen , Ali Saeed jassim , Ali Abid Abojassim , Abdulhussein A. Alkufi

This investigation is aimed to assess the level of ²²²Rn (radon-222), ²²⁶Ra (radium-226), ²³⁸U (uranium-238), ²¹⁸Po (Polonium-218), ²¹⁴Po (Polonium-214) in antibiotics that are commonly utilized for pediatrics in Al-Najaf, governorate. Alpha emitters were measured using a CN-85 detector. Additionally, “Annual Average Internal Effective Dose” (AAIED) and “Risk of an Excess Cancer Fatality Per Million Person” (RECFPMP) resulting from ²²²Rn, ²²⁶Ra, and ²³⁸U in samples of antibiotics were assessed. The average ²²²Rn, ²²⁶Ra, and ²³⁸U values were found to be 2.840, 0.173, and 2.830 Bq/kg, respectively. Moreover, the average AAIED and RECFPMP values which associated with alpha emitters assessment in all medical plant samples were 55.526 nSv/y and 0.214 × 10⁻⁶, respectively. Finally, the average levels of ²¹⁸Po and ²¹⁴Po were recorded as 15.926 and 6.716 Bq/m³, respectively. After conducting a thorough examination for the resulted data and comparing them with the globally accepted and permissible (²¹⁸Po, ²¹⁴Po) limits, it was found that the radiation levels in samples of selected antibiotic medications prescribed for pediatrics were entirely natural and fall within the recommended range. Consequently, there is no cause for concern regarding the radioactive component of these drugs and their safe consumption by children.

本调查旨在评估Al-Najaf省儿科常用抗生素中222Rn（氡-222）、226Ra（镭-226）、238U（铀-238）、218Po（钋-218）、214Po（钋-214）的含量。用CN-85探测器测量α发射体。此外，还评估了抗生素样本中222Rn、226Ra和238U导致的“年平均内有效剂量”（AAIED）和“每百万人过量癌症死亡风险”（RECFPMP）。222Rn、226Ra和238U的平均值分别为2.840、0.173和2.830 Bq/kg。此外，所有药用植物样品中与α排放物评估相关的平均AAIED和RECFPMP值分别为55.526 nSv/y和0.214 × 10 - 6。218Po和214Po的平均浓度分别为15.926 Bq/m3和6.716 Bq/m3。在对结果数据进行彻底检查并将其与全球公认和允许的（218Po, 214Po）限值进行比较后，发现为儿科处方的选定抗生素药物样品中的辐射水平完全是自然的，并在建议范围内。因此，没有理由担心这些药物的放射性成分及其对儿童的安全食用。

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引用次数: 0

Evaluating the level of 226Ra, 232Th and 40K in different building materials 评价不同建筑材料中226Ra、232Th和40K的含量

Nuclear Analysis

Pub Date : 2025-03-01 DOI: 10.1016/j.nucana.2025.100158

Aqeel A. Elewee , Mohammed S. Alsaffar , Shatha F. Alhous , Murtadha Sh Aswood

This study evaluates the levels of ²²⁶Ra, ²³²Th, and ⁴⁰K in various building materials, including brick, cement, sand, gravel, and gypsum, sourced from Al-Shatra in the Dhi-Qar Governorate of Iraq. Measurements were conducted using a NaI (Tl) detector, which is an effective tool for gamma-ray spectrometry. The average activity concentrations measured were 19.70 ± 6.7 Bqkg⁻¹ for ²²⁶Ra, 20.14 ± 3.3 Bqkg⁻¹ for ²³²Th, and 232.24 ± 91 Bqkg⁻¹ for ⁴⁰K. The calculated mean radium equivalent activity was found to be 66.63 Bqkg⁻¹, which is below the internationally accepted threshold of 370 Bqkg⁻¹. Both the internal hazard index (Hin) and the external hazard index (Hex) were determined to be less than unity (<1), in accordance with the safe levels recognized by UNSCEAR. Additionally, the average values for the absorbed dose rate (nGyh⁻¹), indoor annual effective dose (mSvy⁻¹), outdoor annual effective dose (mSvy⁻¹), and gamma-ray exposure rate (μRh⁻¹) were estimated to be 59.09, 0.29, 0.07, and 138.83, respectively. These parameters are within acceptable limits when compared to the world-permitted values. Therefore, all types of building materials assessed in this study are considered safe and do not pose a significant threat to public health.

本研究评估了各种建筑材料（包括砖、水泥、沙子、砾石和石膏）中226Ra、232Th和40K的含量，这些材料来自伊拉克迪卡尔省的al - qar省。使用NaI （Tl）探测器进行测量，这是伽马射线能谱的有效工具。226Ra、232Th和40K的平均活性浓度分别为19.70±6.7 Bqkg - 1、20.14±3.3 Bqkg - 1和232.24±91 Bqkg - 1。计算出的平均镭当量活度为66.63 Bqkg - 1，低于国际公认的370 Bqkg - 1的阈值。内部危害指数（Hin）和外部危害指数（Hex）均小于1 (<1)，符合UNSCEAR认可的安全水平。吸收剂量率（nGyh−1）、室内年有效剂量（mSvy−1）、室外年有效剂量（mSvy−1）和γ射线暴露率（μRh−1）的平均值分别为59.09、0.29、0.07和138.83。与世界允许的值相比，这些参数在可接受的范围内。因此，本研究评估的所有类型的建筑材料都被认为是安全的，不会对公众健康构成重大威胁。

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引用次数: 0