Applied Radiation and Isotopes最新文献_第3页

Development and quality control studies of radiolabelled nanostructured lipid formulations with Ga-68 Ga-68放射性标记纳米结构脂质制剂的研制与质量控制研究。

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-20 DOI: 10.1016/j.apradiso.2026.112453

Emine Selin Demi̇r, Evren Atlıhan Gündoğdu, Emre Özgenç

Objective

This study aims to radiolabel a nanoparticle formulation containing donepezil with Ga-68 radionuclide with high efficiency for diagnosing Alzheimer's disease. In order to develop lipid carrier systems with biocompatible contents in nanoparticle structures, extensive formulation studies were conducted. These systems were subsequently radiolabeled with Ga-68 radionuclide to evaluate their radiolabeling efficiencies. The results are highly encouraging, suggesting that effective radiolabeling is indeed possible. These findings are particularly significant as they open up a range of applications for targeted drug delivery, medical imaging, and diagnostics. Overall, this study represents a valuable contribution to the expanding body of knowledge on lipid carrier systems in healthcare.

Material and method

Nanocarrier formulations were prepared. The radiolabeling parameters of the prepared formulations were studied comparatively. A Ga-68 radionuclide with a half-life of 68 min was used for this. Incubation time, amount of radioactivity, and pH parameters were studied.

Results and discussion

The radiolabeling incubation time, pH of the experimental medium, and amount of radioactivity were tested, and the optimal parameters were identified. According to the results of the radiolabeling studies, optimal radiolabeling with Ga-68 radionuclide was obtained in an acid medium (pH: 5), with a 60 min incubation time, and using 5 mCi of activity in the DOTA-functionalized nanolipid formulations, achieving 89.17 % efficiency. Furthermore, quantitative in vivo PET/CT imaging in nude mice (n = 3/group) demonstrated that the optimized Ga-68-DNP-NLC formulation achieved statistically significant and higher brain uptake compared to the free Ga-68 control, confirming its ability to cross the blood-brain barrier.

目的：利用Ga-68核素对多奈哌齐纳米颗粒制剂进行放射性标记，对阿尔茨海默病进行高效诊断。为了开发在纳米颗粒结构中具有生物相容性的脂质载体系统，进行了广泛的配方研究。随后用Ga-68放射性核素对这些系统进行放射性标记，以评估其放射性标记效率。结果非常令人鼓舞，表明有效的放射性标签确实是可能的。这些发现尤其重要，因为它们为靶向药物输送、医学成像和诊断开辟了一系列应用。总的来说，这项研究代表了一个有价值的贡献，以扩大知识体脂质载体系统在医疗保健。材料与方法：制备纳米载体。比较研究了各制剂的放射性标记参数。使用了半衰期为68分钟的Ga-68放射性核素。对孵育时间、放射线量和pH参数进行了研究。结果与讨论：测试了放射性标记的孵育时间、实验介质的pH、放射性的量，并确定了最佳参数。根据放射性标记研究的结果，Ga-68放射性核素在酸性介质（pH: 5）中获得最佳放射性标记，孵育时间为60 min，在dota功能化纳米脂制剂中使用5 mCi的活性，效率为89.17%。此外，裸鼠体内定量PET/CT成像（n = 3/组）表明，优化后的Ga-68- dnp - nlc配方与游离Ga-68对照相比，具有统计学意义和更高的脑摄取，证实了其穿越血脑屏障的能力。

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引用次数: 0

Age-specific assessment of annual effective dose and excess lifetime cancer risk from radon in tap water of Mueang Ubon Ratchathani, Thailand 泰国Mueang Ubon Ratchathani自来水中氡的年有效剂量和超额终身癌症风险的年龄特异性评估

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-20 DOI: 10.1016/j.apradiso.2026.112455

Ing-orn Sittitanadol , Khanuengnij Prakhammin , Junthara Somtua , Vitsanusat Atyotha

The purpose of this study is to evaluate the level of radon in tap water and its associated health impacts in Mueang District, Ubon Ratchathani Province, Thailand. The condition focuses on the annual effective dose (AED), excess lifetime cancer risk (ELCR), and lung cancer cases per year per million persons (LCC) in different age groups, including infants (0–1 year old), children (2–17 years old), and adults (above 17 years old). A total of 27 samples is collected from different areas of Ubon Ratchathani, and the measurement is done with the RAD7 radon detector and accessories of RAD H₂O. The average radon level in tap water in Ubon Ratchathani is at 0.40 ± 0.09 Bq/L, which is quite lower as compared to the guideline value suggested by the United States Environmental Protection Agency (US EPA). It should be noted that the measured values are close to the detection limit of the RAD7 & H₂O system, and the uncertainty at such low concentrations is relatively high. The annual effective dose, excess lifetime cancer risks, and lung cancer cases per year per million persons vary among each age group. Infants have the highest average annual effective dose, followed by adults and children, of 2.13 ± 0.48 μSv/y, 0.78 ± 0.18 μSv/y, and 1.03 ± 0.23 μSv/y, respectively. A similar trend is also found in excess lifetime cancer risk and lung cancer cases per year per million persons. This finding shows that the radon level in the tap water in the area of study is lower than the level recommended by the World Health Organization (WHO); however, continuous monitoring is required to prevent health risks for the population.

本研究的目的是评估泰国乌汶拉差他尼省Mueang地区自来水中的氡水平及其相关的健康影响。该条件侧重于不同年龄组(包括婴儿（0-1岁）、儿童（2-17岁）和成人（17岁以上）的年有效剂量（AED）、超额终身癌症风险（ELCR）和每年每百万人肺癌病例（LCC）。在乌汶拉差他尼不同地区共采集27份样品，使用RAD7型氡探测器和radh2o配件进行测量。乌汶拉差他尼自来水的平均氡含量为0.40±0.09 Bq/L，与美国环境保护署建议的指导值相比，这是相当低的。需要注意的是，测量值接近RAD7 &； H2O体系的检出限，在如此低的浓度下，不确定度相对较高。每个年龄组的年有效剂量、终生癌症风险和每年每百万人的肺癌病例有所不同。婴儿的年平均有效剂量最高，其次是成人和儿童，分别为2.13±0.48 μSv/y、0.78±0.18 μSv/y和1.03±0.23 μSv/y。在每百万人每年的终生癌症风险和肺癌病例中也发现了类似的趋势。这一发现表明，研究地区自来水中的氡水平低于世界卫生组织（世卫组织）建议的水平；但是，需要持续监测，以防止对人口造成健康风险。

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引用次数: 0

Characterization of a HER-2 targeted silica-gold nanoshells for breast cancer radio-photothermal therapy HER-2靶向二氧化硅-金纳米壳用于乳腺癌放射光热治疗的表征

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-17 DOI: 10.1016/j.apradiso.2026.112454

Omid Talaee , Mahboobeh Mehrabifard , Bahman Alipour , Solmaz Derakhshan , Vahid Asghariazar , Navid kheradmand , Hamed Zamani , Emad khoshdel , Reza Malekzadeh , Tohid Mortezazadeh

Background

The combination of nanoparticles (NPs) with X-ray radiation, laser and chemotherapy offers a promising strategy to enhance breast cancer (BC) treatment efficacy. This study investigates the therapeutic potential of Trastuzumab-loaded Au@SiO₂ nanoshells (TZ-Au@SiO₂ NSs) for SKBr-3 (HER-2⁺) and MCF-7 (HER-2^-) BC cells.

Methods

Au and SiO₂ NPs were prepared via the citrate reduction and sol-gel method, respectively. TZ-Au@SiO₂ NSs were formed by conjugating TZ to Au@SiO₂ NSs. Nano-complex characterization was performed using FT-IR, DLS, TEM, SEM, UV–Vis, XRD, and drug loading efficiency analysis. Cell viability was assessed using the MTT assay after treatment with Au@SiO₂ NSs, TZ, TZ-Au@SiO₂ NSs, NIR laser (808 nm), and X-ray radiation (6 MV, 2 Gy). Moreover, gene expression was analyzed using RT-qPCR to measure apoptosis-related genes.

Results

The synthesized TZ-Au@SiO₂ NSs (around 70 nm) presented significant ability of temperature increase. The combination of TZ-Au@SiO₂ NSs with laser and X-ray radiation resulted in a significant decrease in cell viability. In SKBR-3 cells, TZ-Au@SiO₂ NSs alone reduced viability from 100 % to 71.5 % at 200 μg/mL. After laser treatment, viability decreased to 46 % at the highest dose (350 J/cm²), while X-ray radiation reduced the viability to 63 %. The combined treatment with laser + X-ray resulted in 50 % viability in SKBR-3 and 57 % in MCF-7 cells. Gene expression analysis revealed upregulation of TP53, indicating the induction of apoptosis.

Conclusion

TZ-Au@SiO₂ NSs significantly enhance the cytotoxic effects of X-ray radiation and photothermal-chemotherapy, especially in SKBR-3 BC cells, suggesting their potential as effective radio-sensitizers and photo-sensitizers for improved BC treatment.

纳米粒子（NPs）与x射线、激光和化疗的联合治疗为提高乳腺癌（BC）的治疗效果提供了一种很有前景的策略。本研究探讨了载曲妥珠单抗Au@SiO2纳米壳（TZ-Au@SiO2 NSs）对SKBr-3 （HER-2+）和MCF-7 (HER-2-) BC细胞的治疗潜力。方法分别采用柠檬酸还原法和溶胶-凝胶法制备sau和SiO2纳米颗粒。将TZ与Au@SiO2 NSs偶联形成TZ-Au@SiO2 NSs。采用FT-IR、DLS、TEM、SEM、UV-Vis、XRD和载药效率分析对纳米配合物进行表征。用Au@SiO2 NSs、TZ、TZ-Au@SiO2 NSs、近红外激光（808 nm）和x射线（6 MV, 2 Gy）处理后，采用MTT法评估细胞活力。此外，利用RT-qPCR分析基因表达，检测凋亡相关基因。结果合成的TZ-Au@SiO2 NSs（约70 nm）具有明显的升温能力。TZ-Au@SiO2 NSs联合激光和x射线辐射导致细胞活力显著下降。在SKBR-3细胞中，TZ-Au@SiO2 NSs单独在200 μg/mL时将细胞存活率从100%降低到71.5%。激光治疗后，在最高剂量（350 J/cm2）下，存活率下降到46%，而x射线辐射将存活率降低到63%。激光+ x射线联合治疗SKBR-3细胞存活率为50%，MCF-7细胞存活率为57%。基因表达分析显示TP53上调，提示诱导细胞凋亡。ConclusionTZ-Au@SiO2 NSs显著增强x射线和光热化疗的细胞毒性作用，特别是对SKBR-3 BC细胞，表明它们有潜力作为有效的放射增敏剂和光敏剂改善BC治疗。

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引用次数: 0

Optimization design of tritium target for compact DT neutron generator 小型DT中子发生器氚靶的优化设计。

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-16 DOI: 10.1016/j.apradiso.2026.112442

Siqi Liu , Shiwei Jing , Fuquan Jia , Sijia Zhou , Zebin Li , Yue Sun , Yuxuan Gu , Hailong Xu , Jiayu Li , Shangrui Jiang , Tian Zhang , Guofeng Qu , Zhihua Gao

Neutron generator is a small accelerator neutron source, and its yield is limited by the heating effect caused by the increase of ion beam intensity. The high beam power will cause the target to overheat, and hydrogen will be released after exceeding the limit. A water-cooled target system was designed in order to improve the neutron yield and control the target temperature below the hydrogen release temperature (considered to be 200 °C). The parts of the target film, substrate and cooling system were studied. A large number of solid-fluid coupling calculations and heat transfer analysis were used to determine the final optimized target system structure. A copper-molybdenum alloy substrate was selected and a cooling system was placed. The target film was coated with a magnesium target Ni protective layer, which effectively reduced the irradiation damage of the magnesium film while increasing the yield. The yield of the optimized DT neutron generator reaches 10¹¹n/s when the ion beam intensity is 500 μA and the incident energy is 200 keV, and the operating temperature is not more than 200 °C. This avoids the risk of tritium loss in the target due to hydrogen release.

中子发生器是一种小型的加速器中子源，其产率受到离子束强度增加引起的热效应的限制。远光灯功率会导致目标过热，超过极限后会释放氢气。为了提高中子产率并将靶温控制在氢释放温度（假定为200℃）以下，设计了水冷靶系统。对靶膜、衬底和冷却系统等部件进行了研究。通过大量的固流耦合计算和传热分析，确定了最终优化的目标系统结构。选择了铜钼合金衬底，并设置了冷却系统。在靶膜上包覆一层镁靶Ni保护层，有效降低了镁膜的辐照损伤，同时提高了产量。优化后的DT中子发生器在离子束强度为500 μA、入射能量为200 keV、工作温度不超过200℃的条件下，产率达到1011n/s。这避免了由于氢的释放而在靶中损失氚的风险。

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引用次数: 0

Validation of MCNP6 and FISPACT-II calculations to predict the activation of selected beta emitters produced in the Budapest Research Reactor 验证MCNP6和FISPACT-II计算，以预测布达佩斯研究堆中产生的选定β发射器的激活

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-16 DOI: 10.1016/j.apradiso.2026.112450

Boglárka Maróti , Zoltán Kis , Noémi Anna Buczkó , Katalin Gméling , László Szentmiklósi

Activation calculations were completed on the production of emerging beta-emitting radionuclides in the Budapest Research Reactor (BRR) for medical applications. MCNP6 was utilized to characterize the neutron field at the irradiation positions, while FISPACT-II software was used to predict the activities of the produced radionuclides. Target materials with natural isotopic compositions were irradiated in three different vertical channels of the BRR, and the specific activities of the radionuclides ¹⁶¹Tb, ¹¹¹Ag, ¹⁹⁹Au and ¹⁷⁷Lu were determined using gamma-ray spectrometry. The validation has been successfully completed using ENDF/B-VIII.0 and TENDL-2017 nuclear data libraries. A few discrepant cases were identified which require further investigation.

在布达佩斯研究反应堆（BRR）中完成了用于医疗用途的新出现的β -放射放射性核素的活化计算。利用MCNP6对辐照位置的中子场进行表征，利用FISPACT-II软件对产生的放射性核素的活度进行预测。在BRR的三个不同垂直通道中辐照具有天然同位素组成的靶材料，用伽马射线能谱法测定了放射性核素161Tb、111Ag、199Au和177Lu的比活度。使用ENDF/B-VIII已成功完成验证。0和TENDL-2017核数据库。发现了一些不一致的情况，需要进一步调查。

引用次数: 0

Editorial. 社论。

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-14 DOI: 10.1016/j.apradiso.2026.112440

引用次数: 0

Sensitivity gains and quality control in radioxenon monitoring via laboratory Re-measurements 实验室重测法监测放射性氙的灵敏度增益和质量控制

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-14 DOI: 10.1016/j.apradiso.2026.112427

Mattias Aldener, Tomas Fritioff, Catharina Söderström

As a part of the Comprehensive Nuclear Test Ban Treaty (CTBT) the International Monitoring System (IMS), to monitor the compliance of member states to CTBT, is currently being established. The IMS consists of different monitoring techniques, of which the sampling and detection of radioactive noble gases, mainly radioxenon, is one. As a complement to the monitoring stations, a number of radionuclide laboratories are included in the IMS. Samples collected at a station can be sent to a laboratory for further analysis. However, due to the short half-lives of radioxenon isotopes, the benefits of conducting re-measurements in the laboratory are unclear, as the isotope may decay significantly during transport.

The FOI facilities in Sweden host a SAUNA III IMS system and a radioxenon laboratory. The laboratory is equipped with a SAUNA Laboratory system for re-analysis of xenon samples collected using the IMS systems. To investigate both the advantages and limitations of laboratory re-measurements, several radioxenon samples from the IMS station are re-measured at the laboratory system, and compared to the SAUNA III results.

This work shows that, in addition to ensuring quality control of the sampling and xenon purification process, laboratory re-measurements also provide a better detectability for most of the radioxenon isotopes. For ¹³³Xe and ^131mXe the detectability at the laboratory is as good as at the IMS station up to at least a week after the collection period, and can be improved further by increasing the measurement time at the laboratory. The higher sensitivity at the laboratory measurements also results in a better estimation of the isotopic ratios, which is important for classification of the detection.

作为《全面禁止核试验条约》的一部分，目前正在建立监测成员国遵守《全面禁止核试验条约》情况的国际监测系统。IMS由不同的监测技术组成，其中对放射性惰性气体（主要是放射性氙）的采样和检测是一种。作为对监测站的补充，一些放射性核素实验室被列入监测系统。在站点收集的样本可以送到实验室进行进一步分析。然而，由于放射性氙同位素的半衰期很短，在实验室进行重新测量的好处尚不清楚，因为同位素可能在运输过程中显著衰减。瑞典的FOI设施拥有一个桑拿III IMS系统和一个放射性氙实验室。该实验室配备了桑拿实验室系统，用于重新分析使用IMS系统收集的氙气样品。为了研究实验室重测的优点和局限性，在实验室系统中对IMS站的几个放射性氙样品进行了重测，并与桑拿III的结果进行了比较。这项工作表明，除了确保采样和氙净化过程的质量控制外，实验室重新测量也为大多数放射性氙同位素提供了更好的可探测性。对于133Xe和131mXe，在实验室的可探测性至少在采集期后一周内与IMS站一样好，并且可以通过增加实验室的测量时间进一步提高。实验室测量的高灵敏度也导致对同位素比率的更好估计，这对检测的分类很重要。

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引用次数: 0

Monte Carlo sensitivity analysis of the Vinten 671 ionization chamber activity calibration coefficients Vinten 671电离室活度标定系数的蒙特卡罗灵敏度分析

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-14 DOI: 10.1016/j.apradiso.2026.112437

A. Bourgouin, R.W. Townson, R. Galea

Accurate calibration coefficients (CCs) are essential for radionuclide calibrators employed in nuclear medicine and radiopharmacy applications. These coefficients depend on multiple experimental and modelling parameters, including sample composition, geometry, and positioning within the ionization chamber (IC). This work investigates the sensitivity of CCs for the National Physical Laboratory (NPL) Vinten 671 well-type IC, whose design is represented in the widely used NPL Fidelis calibrator. A comprehensive sensitivity analysis was conducted using the EGSnrc Monte Carlo (MC) model to evaluate the impact of both physical and computational parameters on CC determination. Variables examined included detector and vial geometry, nuclear decay data libraries, and simulation energy cut-off values.

The results demonstrate that CCs are largely stable under minor variations in vial volume and vertical positioning but exhibit notable sensitivity to the nuclear data selection and the aluminium inner wall thickness of the chamber. Accurate modelling of the vial and holder, particularly in the axial plane, is crucial. Parameters such as nitrogen pressure and aluminium wall thickness, even with minimal changes, demonstrate a significant impact, with optimization offering potential improvements in agreement between experimental and simulated values. Future efforts should refine the EGSnrc model, with experimental validation enhancing model reliability.

准确的校准系数（CCs）对于核医学和放射药学应用中使用的放射性核素校准器至关重要。这些系数取决于多个实验和建模参数，包括样品组成、几何形状和电离室（IC）内的位置。这项工作研究了国家物理实验室（NPL） Vinten 671井型集成电路的CCs灵敏度，其设计在广泛使用的NPL Fidelis校准器中得到了体现。采用EGSnrc蒙特卡罗（MC）模型进行综合敏感性分析，以评估物理参数和计算参数对CC测定的影响。检查的变量包括探测器和小瓶几何形状、核衰变数据库和模拟能量截止值。结果表明，在小瓶体积和垂直位置的微小变化下，CCs基本稳定，但对核数据选择和腔室铝内壁厚度表现出显著的敏感性。准确建模的小瓶和持有人，特别是在轴向平面，是至关重要的。氮压力和铝壁厚度等参数即使变化很小，也会产生重大影响，优化后的实验值和模拟值之间的一致性可能得到改善。未来的工作应该完善EGSnrc模型，通过实验验证来提高模型的可靠性。

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引用次数: 0

Impact of arc therapy in boron neutron capture therapy (BNCT) on dose uniformity and motion robustness 硼中子俘获治疗中电弧治疗对剂量均匀性和运动稳健性的影响

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-13 DOI: 10.1016/j.apradiso.2026.112439

Junyan Wang , Haiyun Kong , Wangxuan Li , Deming Li

Monte Carlo simulations were conducted to evaluate the dose distribution characteristics and motion robustness of fixed-angle versus arc irradiation techniques in boron neutron capture therapy (BNCT), using a head phantom. For fixed-angle irradiation, an anterior-posterior (AP) beam was oriented towards the facial plane. In contrast, the arc technique involved a continuous 180° rotation, from the left to the right, around the central axis traversing the face. The target was located in the nasal cavity region. Results demonstrated the dosimetric superiority of the arc technique, which increased the mean tumor dose by 0.7 Gy-Eq and improved the dose homogeneity index from 0.67 to 0.74. For the head phantom in this study, the arc technique showed enhanced motion robustness, reducing dose deviations across five critical motion directions including anterior translation (AT), left translation (LT), right translation (RT), inferior rotation (IR), and superior rotation (SR). The maximum improvement was a 15.3 % reduction in the E2 % metric (dose error for the 2 % volume after motion-induced perturbations) at the RT direction. The largest average dose error reduction was achieved in the AT direction, reaching 8.2 %. These findings confirm that arc irradiation confers distinct advantages in BNCT cases affected by motion errors, owing to its superior dose conformity and stability.

采用蒙特卡罗模拟方法，对硼中子俘获治疗（BNCT）中固定角度与电弧照射技术的剂量分布特性和运动鲁棒性进行了评估。对于固定角度照射，前后（AP）束朝向面平面。相比之下，圆弧技术涉及一个连续的180°旋转，从左到右，围绕中心轴穿过脸。目标位于鼻腔区域。结果表明，弧技术的剂量学优势，使平均肿瘤剂量增加0.7 Gy-Eq，剂量均匀性指数从0.67提高到0.74。对于本研究中的头部幻像，弧技术显示出增强的运动稳健性，减少了五个关键运动方向上的剂量偏差，包括前平移（AT）、左平移（LT）、右平移（RT）、下旋转（IR）和上旋转（SR）。最大的改善是在RT方向上E2 %度量（运动引起的扰动后2%体积的剂量误差）减少15.3%。AT方向的平均剂量误差减小幅度最大，达到8.2%。这些发现证实了电弧照射在受运动误差影响的BNCT病例中具有明显的优势，因为它具有优越的剂量一致性和稳定性。

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引用次数: 0

The EURAMET.RI(II)-S9 interlaboratory comparison of the radionuclide calibrators EURAMET。RI(II)-S9放射性核素校准器的实验室间比较

IF 1.8 3区工程技术 Q3 CHEMISTRY, INORGANIC & NUCLEAR

Applied Radiation and Isotopes

Pub Date : 2026-01-13 DOI: 10.1016/j.apradiso.2026.112434

Arūnas Gudelis , Andrei Antohe , Eszter Bodnár , Robert Bretner-Messler , Pavel Dryák , Andrej Javorník , Kristyna Kohoutova , Petr Kovář , Matej Krivošík , Ioana Lalau , Patrick Lobner , Liviu-Cristian Mihailescu , Anita Peka , Miguel Roteta , Jan Rusnák , Vladimír Sochor , Jana Sochorová , Jiri Šuráň , Laszlo Szücs , Isabelle Taschwer , Martin Volesak

At EURAMET TC-IR meeting in Madrid, March 1, 2023, it was proposed to organize a comparison on radionuclide calibrators to measure the activity of short-lived radionuclides used in nuclear medicine: F-18, Ga-67, Y-90, Tc-99 m, In-111, I-123, I-131, Sm-153, Lu-177 and Tl-201. The technical protocol was elaborated in June 2023 and after comments received from CCRI(II) and KCWG (II) it was finally approved in August 2023.

The comparison took place in Prague at CMI headquarters 11–15 September 2023.

Original solutions provided by manufacturers were used to prepare working solutions with which 2 mL ampoules, 5 mL ampoules, P6 vials, and Schott 10 R type1+ vials were filled. For control measurements by the gamma-ray spectrometry with a HPGe detector, samples were prepared using the same solution. For radionuclides Ga-67, Sm-153, and Lu-177, special solutions were produced, and 3.6 mL ampoules required by SIR were filled. Activity values were determined gravimetrically from activity concentration values measured by the primary method.

The comparison reference values were determined from activity measurement results of a selection of participants by using the Power Moderated Mean approach.

2023年3月1日在马德里举行的EURAMET TC-IR会议上，提议组织对放射性核素校准器进行比较，以测量核医学中使用的短寿命放射性核素：F-18、fa -67、Y-90、Tc-99 m、in -111、I-123、I-131、Sm-153、Lu-177和Tl-201的活度。技术协议在2023年6月详细阐述，在收到CCRI（II）和KCWG （II）的意见后，最终于2023年8月获得批准。比较于2023年9月11日至15日在布拉格CMI总部进行。使用制造商提供的原始溶液配制工作溶液，分别装2ml安瓿、5ml安瓿、P6瓶和Schott 10r type1+瓶。对于使用HPGe探测器的伽马射线能谱法进行的对照测量，样品使用相同的溶液制备。对于放射性核素Ga-67、Sm-153和Lu-177，制作特殊溶液，并填充SIR所需的3.6 mL安瓿。活性值由原方法测得的活性浓度值用重量法测定。比较参考值是通过使用功率调节平均方法从选定的参与者的活动测量结果确定的。

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引用次数: 0