Radiation Measurements最新文献

Photon energy estimation in diagnostic radiology using OSL dosimeters: Experimental validation and Monte Carlo simulations 在放射诊断中使用 OSL 剂量计估算光子能量：实验验证和蒙特卡罗模拟

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-20 DOI: 10.1016/j.radmeas.2024.107342

Bui Ngoc Huy, Pham Van Dung, Huynh Thi Tinh, Nguyen Thi Ha, Nguyen Minh Duc

The EGSnrc Monte Carlo software toolkit was used to evaluate the energy response and estimate the photon energy based on the E3/E4 ratio for the InLight XA Optical Luminescence Dosimeters (OSLDs).

The InLight XA OSLDs were irradiated with Cs-137 source and ISO 4037-1 narrow-spectrum series X-ray qualities (N40, N60, N80, and N100). The virtual OSLDs on the surface of the PMMA phantom were constructed in EGSnrc, energy response and ratio E3/E4 of the dosimeters was determined and compared to the physical measurements.

Good agreement was found between the simulated and measurement approaches in estimating the photon energy with a percentage difference of less than 6%. The E3/E4 ratio from simulation, physical measurements, and microStar system showed very good agreement results with the maximum difference of 9.3% and 10.94%, respectively. Furthermore, the OSLDs energy response varied significantly at energy below 100 keV due to the photoelectric effect.

The results of this study identify and address the over-response of OSLDs to low-energy photons, offering correction factors to minimize errors, especially in diagnostic radiology applications. These findings have the potential to improve dose accuracy for patients and radiation workers by providing more precise photon energy estimations, particularly at lower energy ranges, such as in diagnostic X-rays. The function used to evaluate photon energy using E3/E4 ratio has a great influence on the accuracy of such algorithms. It also ensures that imaging equipment is properly calibrated for the specific energy ranges needed, enhancing diagnostic accuracy. Furthermore, precise dose measurements are essential for maintaining regulatory compliance and long-term patient exposure records, ultimately promoting safer and more effective radiological practices.

使用 EGSnrc Monte Carlo 软件工具包对 InLight XA 光学发光剂量计 (OSLD) 进行能量响应评估，并根据 E3/E4 比率估算光子能量。在 EGSnrc 中构建了 PMMA 模体表面的虚拟 OSLD，确定了剂量计的能量响应和比率 E3/E4，并与物理测量结果进行了比较。模拟、物理测量和微星系统的 E3/E4 比值显示出非常好的一致性，最大差异分别为 9.3% 和 10.94%。此外，由于光电效应，OSLDs 的能量响应在能量低于 100 keV 时变化很大。这项研究的结果确定并解决了 OSLDs 对低能量光子的过度响应问题，提供了校正系数以尽量减少误差，尤其是在放射诊断应用中。这些发现有可能通过提供更精确的光子能量估计来提高患者和放射工作人员的剂量准确性，尤其是在较低能量范围，如诊断 X 射线中。使用 E3/E4 比率评估光子能量的功能对此类算法的准确性有很大影响。它还能确保成像设备针对所需的特定能量范围进行正确校准，从而提高诊断的准确性。此外，精确的剂量测量对于维护监管合规性和长期患者照射记录至关重要，最终可促进更安全、更有效的放射实践。

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引用次数: 0

Exploration of dosimetry characteristics of PVA/MWCNT-OH nanocomposite for intraoperative electron radiotherapy 用于术中电子放疗的 PVA/MWCNT-OH 纳米复合材料剂量学特性探讨

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-18 DOI: 10.1016/j.radmeas.2024.107345

Shahryar Malekie , Seyed Rashid Hosseini Aghdam , Seyed Mahmoud Reza Aghamiri , Armin Mosayebi , Suffian Mohamad Tajudin

This study investigates the dosimetric properties of a Polyvinyl Alcohol/Multi-Walled Carbon Nanotube Hydroxyl (PVA/MWCNT-OH) composite intended for intraoperative electron radiotherapy (IOeRT). A dosimeter was fabricated using a 0.02 wt% MWCNT-OH nanocomposite, featuring a thickness of 2 mm and a diameter of 2 cm. The electric charge recorded during irradiation served as the response for this real-time dosimeter. The dosimetry type-testing criteria for IOeRT at 8 MeV were evaluated, encompassing aspects such as linearity of response, dose rate, bias polarity, repeatability, field size, and dependency on electron energy. To assess energy dependency, the dosimeter's response was measured at various energies including 6, 8, 10, and 12 MeV utilizing a LIAC dedicated IOeRT machine. The results indicated a linear correlation in the dosimeter's response across absorbed doses up to 17 Gy. Furthermore, the various type-testing evaluations demonstrated compliance with IEC 60731 standard, with the exception of energy dependency, which necessitates the application of a suitable correction factor.

本研究调查了用于术中电子放射治疗（IOeRT）的聚乙烯醇/多壁碳纳米管羟基（PVA/MWCNT-OH）复合材料的剂量特性。使用 0.02 wt% MWCNT-OH 纳米复合材料制作了剂量计，其厚度为 2 毫米，直径为 2 厘米。辐照期间记录的电荷作为该实时剂量计的响应。对 8 MeV IOeRT 的剂量测定类型测试标准进行了评估，包括响应线性、剂量率、偏置极性、可重复性、磁场大小以及对电子能量的依赖性等方面。为了评估能量依赖性，利用 LIAC 专用 IOeRT 设备在不同能量（包括 6、8、10 和 12 MeV）下对剂量计的响应进行了测量。结果表明，在吸收剂量高达 17 Gy 时，剂量计的响应呈线性相关。此外，各种类型测试评估表明，除了能量依赖性需要应用适当的校正因子外，剂量计符合 IEC 60731 标准。

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引用次数: 0

Review of real time 2D dosimetry in external radiotherapy: Advancements and techniques 回顾体外放射治疗中的实时二维剂量测量：进展与技术

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-18 DOI: 10.1016/j.radmeas.2024.107344

Luana de Freitas Nascimento , Alessia Gasparini

The objective of this paper is to provide a comprehensive review of the advancements and techniques in real time two-dimensional (2D) dosimetry for external radiation therapy with emphasis in vivo dosimetry and patient specific quality assurance. External radiation therapy plays a crucial role in cancer treatment, delivering high-energy radiation beams to target tumours while minimizing damage to surrounding healthy tissues. Accurate dosimetry, as both the measurement of the dose and its delivered location, is paramount to ensure effective treatment outcomes and minimize potential side effects.

The planned content of this paper encompasses a thorough examination of the advancements made in 2D dosimetry techniques, including solid state and electronic systems. The evolution from traditional passive dosimetry to modern real time detectors, such as portal imaging, has revolutionized the field, offering enhanced precision, efficiency, and convenience. This review will discuss the principles, advantages, and limitations of these systems, along with their practical implementation and calibration procedures.

Furthermore, the paper will highlight novel technologies, such as luminescence coatings, for quality assurance (QA) and real-time dose verification during treatment. The use of innovative materials and designs in dosemeters, including high spatial resolution detectors and tissue-equivalent phantoms, will also be explored. Additionally, the incorporation of advanced data analysis techniques, such as machine/deep learning algorithms, for dose reconstruction and QA will be addressed.

The review will also explore the application of real time 2D dosimetry in modern clinical and pre-clinical modalities, including intensity-modulated radiation therapy and volumetric modulated arc therapy, stereotactic radiosurgery, image-guided radiation therapy, particle therapy, adaptive radiotherapy, electron and proton ultra-high dose rate therapy and very high energy electrons.

By providing an up-to-date overview of the state-of-the-art in real time 2D dosimetry in vivo dosimetry and patient specific quality assurance, this paper aims to inform and guide professionals in the field, facilitating the adoption of cutting-edge techniques and improving the accuracy and safety of external radiotherapy treatments.

本文旨在全面综述体外放射治疗实时二维（2D）剂量测定的进展和技术，重点是体内剂量测定和针对患者的质量保证。体外放射治疗在癌症治疗中起着至关重要的作用，它将高能辐射束射向目标肿瘤，同时最大限度地减少对周围健康组织的损伤。要确保有效的治疗效果并最大限度地减少潜在的副作用，精确的剂量测定（包括剂量及其投射位置的测量）至关重要。本文的计划内容包括对二维剂量测定技术（包括固态和电子系统）所取得的进展进行全面的研究。从传统的被动剂量测定到现代的实时探测器（如门式成像），这一领域发生了革命性的变化，精度、效率和便利性都得到了提高。本文将讨论这些系统的原理、优势和局限性，以及它们的实际应用和校准程序。此外，本文还将重点介绍用于治疗过程中质量保证（QA）和实时剂量验证的新技术，如发光涂层。论文还将探讨剂量计中创新材料和设计的使用，包括高空间分辨率探测器和组织等效模型。综述还将探讨实时二维剂量学在现代临床和临床前模式中的应用，包括调强放射治疗和容积调强弧治疗、立体定向放射外科、图像引导放射治疗、粒子治疗、自适应放射治疗、电子和质子超高剂量率治疗以及高能电子。本文概述了实时二维剂量测定、体内剂量测定和患者特定质量保证方面的最新技术，旨在为该领域的专业人员提供信息和指导，促进尖端技术的采用，提高体外放射治疗的准确性和安全性。

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引用次数: 0

Clinical evaluation of a new device for acceptance testing of Ru-106 plaques in ophthalmic brachytherapy 眼科近距离放射治疗 Ru-106 斑块验收测试新设备的临床评估

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-17 DOI: 10.1016/j.radmeas.2024.107343

María Martorell Ruiz , Roberto M. Sánchez Casanueva , Antonio Gañán Mora , José M. Fernández-Soto

Purpose

Ophthalmic brachytherapy treats eye lesions by stitching plaques containing a radionuclide (e.g. Ru-106) onto the sclera. Compliance with quality assurance standards is crucial, but practical limitations complicate independent source strength measurement in clinical practice. In this article, a new prototype for acceptance testing of Ru-106 plaques is assayed to assess its suitability for a hospital's medical physics department.

Methods and materials

The system designed for Ru-106 plaque assessment includes a phantom basin fillable with water, a Si-diode for electrons coupled with an electrometer, type-dependent plaque holders and a micrometre gauge. Testing involved the measurement of three plaque types (CCA, CIB, COB) by six medical physics experts and trainees, the assessment of inter and intra-observer variability and the suitability for measurement at the reference point, 2 mm.

Results

Measured absorbed dose rates in water at 2 mm from the plaque surface demonstrated compatibility across all testers for the three plaques. Intra and inter-observer variability was minimal (1.0% and 1.3% of the measured value, respectively), confirming system robustness in terms of operator influence.

Conclusions

The system proves suitable for Ru-106 plaque acceptance testing ensuring accurate plaque positioning and dose rate verification at 2 mm. These findings confirm its potential as a support for compliance with quality assurance standards. These results are subject to the issue of the corresponding calibration certificate for the Si-diode.

目的眼科近距离放射治疗通过在巩膜上缝合含有放射性核素（如 Ru-106）的斑块来治疗眼部病变。符合质量保证标准至关重要，但实际操作的局限性使临床实践中的独立源强度测量变得复杂。方法和材料为 Ru-106 斑块评估而设计的系统包括一个可注水的幻影盆、一个与电子计相连的电子二极管、根据斑块类型而定的支架和一个微米计。测试包括由六位医学物理专家和学员对三种斑块类型（CCA、CIB、COB）进行测量，评估观察者之间和观察者内部的可变性，以及在参考点（2 毫米）进行测量的适用性。观察者内部和观察者之间的变异性极小（分别为测量值的 1.0% 和 1.3%），证实了系统在操作者影响方面的稳健性。结论该系统适用于 Ru-106 斑块验收测试，可确保在 2 毫米处对斑块进行准确定位和剂量率验证。这些结果证实了该系统作为符合质量保证标准的支持系统的潜力。这些结果有待颁发相应的 Si-diode 校准证书。

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引用次数: 0

About thermal stability of the F+ centers in MgO single crystals irradiated by fast neutrons or energetic Ar ions 关于快中子或高能氩离子照射下氧化镁单晶中 F+ 中心的热稳定性

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-14 DOI: 10.1016/j.radmeas.2024.107335

Guldar Baubekova , Ruslan Assylbayev , Alise Podelinska , Viktor Seeman , Evgeni Shablonin , Evgeni Vasil'chenko , Aleksandr Lushchik

Single crystals of MgO have been exposed to 70-MeV argon ions with varying fluence of 4 × 10¹²-3 × 10¹⁴ cm⁻². The dependence of radiation-induced optical absorption (RIOA) at 1.7–6.5 eV on irradiation fluence has been analyzed. The EPR signal of the F⁺ center in ion-irradiated crystal has been detected and via the EPR parameters proved to be the same as in well-studied neutron-irradiated MgO crystals. The precise isothermal annealing of the F ⁺ EPR signal has been performed for the first time in a temperature range of 400–1100 K for both a fast neutron irradiated (2.7 × 10¹⁸ cm⁻²) and Ar-irradiated (3 × 10¹⁴ cm⁻²) MgO crystals. In both cases, the F ⁺ EPR decay starts only above 700 K and ends at 950–1060 K, depending on irradiation type. Using the same stepwise annealing procedure, the changes in RIOA for ion-irradiated samples have also been analyzed and possible reasons for the discrepancy in the thermal behaviour of optical and EPR F ⁺ -absorption have been considered.

氧化镁单晶体受到了 70-MeV 氩离子 4 × 1012-3 × 1014 cm-2 的不同辐照。分析了 1.7-6.5 eV 处辐射诱导光吸收（RIOA）与辐照通量的关系。在离子辐照晶体中检测到了 F+ 中心的 EPR 信号，并通过 EPR 参数证明其与经过充分研究的中子辐照氧化镁晶体相同。对于快中子辐照（2.7 × 1018 cm-2）和氩辐照（3 × 1014 cm-2）的氧化镁晶体，首次在 400-1100 K 的温度范围内对 F + EPR 信号进行了精确的等温退火处理。在这两种情况下，根据辐照类型的不同，F + EPR 衰变仅在 700 K 以上开始，在 950-1060 K 结束。使用相同的逐步退火程序，还分析了离子辐照样品的 RIOA 变化，并考虑了光学和 EPR F + - 吸收热行为差异的可能原因。

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引用次数: 0

Study on dosimetric characteristics of polycarbonate films irradiated by electron beam 电子束辐照聚碳酸酯薄膜的剂量特性研究

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-12 DOI: 10.1016/j.radmeas.2024.107333

Ke Wang , Zhizeng Pan , Longxiang Yin , Haifeng Zhang , Yuchen Zou , Xionghui Fei

In this study, the dosimetric characteristics (thickness applicability, dose linear response, signal fading characteristic, in-batch consistency, readout reproducibility, humidity dependence, and electron energy response) of engineering polycarbonate films irradiated by electron beam were studied using spectrophotometry. The results show that polycarbonate films of various thicknesses exhibit good dose linearity within their corresponding wavelength ranges. Specifically, the dose capture range of 0.3 mm polycarbonate film spans from 950 Gy to 1000 kGy. After irradiation, the net absorbance of polycarbonate films showed an exponential decline, which was dose-dependent. The average absolute deviation of net absorbance for polycarbonate films produced within the same batch is 1.49% at 100 kGy. After 15 repeated absorbance measurements, the coefficient of variation in net absorbance for the polycarbonate films is less than 1%. Additionally, the radiation response of the polycarbonate film is affected by the environment relative humidity (during irradiation and post-irradiation storage). At the same dose of 3.5–20 MeV electron beam irradiation, the net absorbance response deviation of polycarbonate films remains below 2.26%. These results provide a comprehensive reference for detecting high doses of electron beams using engineering polycarbonate films.

本研究利用分光光度法研究了电子束照射工程聚碳酸酯薄膜的剂量特性（厚度适用性、剂量线性响应、信号衰减特性、批量一致性、读出再现性、湿度依赖性和电子能量响应）。结果表明，不同厚度的聚碳酸酯薄膜在相应的波长范围内表现出良好的剂量线性。具体来说，0.3 毫米聚碳酸酯薄膜的剂量捕获范围从 950 Gy 到 1000 kGy。辐照后，聚碳酸酯薄膜的净吸光度呈指数下降，且与剂量有关。100 kGy 时，同一批次生产的聚碳酸酯薄膜净吸光度的平均绝对偏差为 1.49%。经过 15 次重复吸光度测量，聚碳酸酯薄膜的净吸光度变化系数小于 1%。此外，聚碳酸酯薄膜的辐射响应受环境相对湿度（辐照期间和辐照后储存）的影响。在相同剂量的 3.5-20 MeV 电子束辐照下，聚碳酸酯薄膜的净吸光度响应偏差保持在 2.26% 以下。这些结果为使用工程聚碳酸酯薄膜检测高剂量电子束提供了全面的参考。

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引用次数: 0

Modeling detector response curves for a high-fidelity uranium measurement for use in simulations 模拟高保真铀测量的探测器响应曲线建模

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-10 DOI: 10.1016/j.radmeas.2024.107332

Lohith Annadevula , S.K. Aghara , Chris Gazze , Kenneth Jarman , Claude Norman

Enrichment measurements using identiFinder2 (‘HM5’) detector are performed on two Material Testing Reactor (MTR) fuel assemblies - one with low-enriched uranium plates (LEU) and another with high-enriched uranium plates (HEU). The effectiveness of International Atomic Energy Agency (IAEA) inspection plans for verifying nuclear material strata, in the form of defect detection probability (DP), is evaluated using statistical models. These models use defect identification probability (IP) curves, which represent the probability that a measured item is identified as a defective item. This paper describes a new modeling procedure that converts the experimental measurements into IP curves and employing such experimentally derived IP curves within DP simulations will better represent the experimental conditions like material type, material distribution, and plate configuration. A comparison of experimental performance curves to a simple statistical model (Gaussian, 15% relative standard deviation RSD) shows that the DP results from the modeled response of HM5 measurements better captures the experimental conditions. This result highlights a need for further research into experimental error variables test model development as use of a simple model does not adequately capture true performance in either the LEU or HEU cases.

使用 identiFinder2（'HM5'）探测器对两个材料试验反应堆（MTR）燃料组件--一个装有低浓缩铀板（LEU），另一个装有高浓缩铀板（HEU）--进行了浓缩度测量。使用统计模型评估了国际原子能机构（IAEA）以缺陷检测概率（DP）形式核查核材料层的检查计划的有效性。这些模型使用缺陷识别概率 (IP) 曲线，表示测量项目被识别为缺陷项目的概率。本文介绍了一种新的建模程序，该程序可将实验测量结果转换为 IP 曲线，在 DP 模拟中采用这种由实验得出的 IP 曲线将更好地代表材料类型、材料分布和板配置等实验条件。实验性能曲线与简单统计模型（高斯，15% 相对标准偏差 RSD）的比较表明，HM5 测量模型响应的 DP 结果能更好地捕捉实验条件。这一结果凸显了进一步研究实验误差变量测试模型开发的必要性，因为使用简单模型并不能充分反映 LEU 或 HEU 的真实性能。

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引用次数: 0

Monte Carlo calculation of LiF:Mg,Cu,P thermoluminescent dosimeter correction factors for 18F, 131I and 90Y submersion dosimetry 用于 18F、131I 和 90Y 浸没剂量测定的 LiF：Mg、Cu、P 热释光剂量计校正因子的蒙特卡洛计算

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-09 DOI: 10.1016/j.radmeas.2024.107331

Ahad Ollah Ezzati , Farzane Mohajeri , Matthew Studenski

Accurate measurement of absorbed dose from beta-emitting therapeutic radionuclides is important to ensure safe and effective delivery to patients. Thermoluminescent dosimeters (TLDs) are a commercially available option to measure dose, but several confounding factors complicate this process. To preserve their integrity during the measurement, it is necessary to enclose TLDs in a waterproof envelope, which unavoidably attenuates the beta particles. Additionally, the exclusion of radioactivity in the volume occupied by the TLD, the finite volume effect, further complicates the measurement. The purpose of this study is to calculate the correction factors to convert the TLD measured dose to the absorbed dose in water, D_w, for three common radionuclides and the LiF:Mg,Cu,P TLD (Thermo Fisher Scientific™, Waltham, MA). Correction factors were calculated for four different size LiF:Mg,Cu,P TLD dosimeters inside a PMMA cylindrical phantom with ⁹⁰YCl₃, C₆H₁₁¹⁸FO₅, and Na¹³¹I aqueous solutions. Specific correction factors are required to account for finite volume, energy, and geometry for each LiF:Mg,Cu,P TLD size, radionuclide, and phantom geometry combination. Additionally, for the PMMA phantom, specific material correction factors are also required to account for the additional materials inside the phantom. The absorbed dose calculations performed with LiF:Mg,Cu,P TLDs showed good agreement with Monte Carlo simulations. Overall, these findings contribute to improving the accuracy of absorbed dose measurements from beta-emitting radionuclides in liquid solutions using TLDs.

准确测量β发射治疗放射性核素的吸收剂量对于确保向患者安全有效地提供治疗非常重要。热释光剂量计（TLD）是测量剂量的一种商用方法，但有几个干扰因素使测量过程变得复杂。为了在测量过程中保持热释光剂量计的完整性，有必要将其封装在防水外壳中，这不可避免地会削弱β粒子。此外，在 TLD 所占的体积内排除放射性，即有限体积效应，也使测量变得更加复杂。本研究的目的是计算校正因子，以便将三种常见放射性核素和 LiF:Mg,Cu,P TLD（Thermo Fisher Scientific™，马萨诸塞州沃尔瑟姆）的 TLD 测量剂量转换为水中吸收剂量 Dw。在含有 90YCl3、C6H1118FO5 和 Na131I 水溶液的 PMMA 圆柱形模型内，计算了四种不同尺寸的 LiF:Mg,Cu,P TLD 剂量计的校正因子。对于每种 LiF:Mg,Cu,P TLD 尺寸、放射性核素和模型几何组合，都需要特定的校正因子来考虑有限体积、能量和几何形状。此外，对于 PMMA 模体，还需要特定的材料修正系数来考虑模体内的额外材料。使用 LiF:Mg,Cu,P TLD 进行的吸收剂量计算与蒙特卡罗模拟结果显示出良好的一致性。总之，这些发现有助于提高使用 TLD 测量液态溶液中β发射放射性核素吸收剂量的准确性。

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引用次数: 0

Monte Carlo dosimetry for a EURADOS WG 10 and RENEB field test of retrospective dosimetry techniques in realistic exposure scenarios 为欧洲放射剂量评估系统第 10 工作组和 RENEB 在实际照射情况下对追溯剂量测定技术进行的蒙特卡洛剂量测定实地测试

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-09 DOI: 10.1016/j.radmeas.2024.107329

Hyoungtaek Kim , Min Chae Kim , Olivier Van Hoey , Jonathan Simon Eakins , Hyungjoon Yu , Hanjin Lee , Michael Discher , Jungil Lee , Lovisa Waldner , Clemens Woda , Francois Trompier , Céline Bassinet , Sergey Sholom , S.W.S. McKeever , Elizabeth A. Ainsbury

Computational dosimetry using Monte Carlo radiation transport simulations was applied for the 2019 European Radiation Dosimetry Group (EURADOS) and Running the European Network of Biological and retrospective Physical dosimetry (RENEB) field test, an exercise of retrospective dosimetry techniques for a realistic small-scale radiological accident. The simulations were performed at four institutes, using different codes and computerized anthropomorphic phantoms. Four exposure scenarios using Ir-192 were modeled: relatively homogeneous in a predominantly AP direction, heterogeneous in a predominantly anterior-posterior (AP) and left-lateral (LLAT) direction, and partially shielded. The items for dosimetry, such as mobile phones, blood tubes, and surface dosimeters, were designed and located based on the experimental pictures. Absorbed doses of dosimeters, such as thermoluminescence dosimeter (TLD), optically stimulated luminescence dosimeters (OSLD), radio-photoluminescence dosimeters (RPLD), and display glasses, inside and outside the phantoms were calculated and compared to the measured doses. In addition, photon energy spectra were calculated at different locations to correct the energy responses of the materials. The simulation results from the four institutes showed agreement with each other, showing an average relative difference of less than 14%. The Pearson's R-values for the linear fitting of the measured and calculated data ranged from 0.95965 to 0.68714, depending on the exposure scenario and institutes. Finally, the accuracy and limitations of the calculation techniques for the given exposure structures are discussed.

利用蒙特卡洛辐射传输模拟进行的计算剂量学应用于 2019 年欧洲辐射剂量学小组（EURADOS）和运行欧洲生物和回顾性物理剂量学网络（RENEB）的实地测试，这是一次针对真实小规模辐射事故的回顾性剂量学技术演习。模拟在四个机构进行，使用不同的代码和计算机化的拟人化模型。模拟了四种使用 Ir-192 的照射情况：以 AP 方向为主的相对均质照射、以前后（AP）和左侧（LLAT）方向为主的异质照射以及部分屏蔽照射。手机、血管和表面剂量计等剂量测定物品是根据实验图片设计和定位的。计算了热释光剂量计（TLD）、光刺激发光剂量计（OSLD）、无线电-光致发光剂量计（RPLD）和显示眼镜等剂量计在模型内外的吸收剂量，并与测量剂量进行了比较。此外，还计算了不同位置的光子能量谱，以校正材料的能量响应。四个研究所的模拟结果显示彼此一致，平均相对差异小于 14%。测量数据和计算数据线性拟合的皮尔逊 R 值介于 0.95965 到 0.68714 之间，具体取决于暴露情况和研究所。最后，讨论了针对特定暴露结构的计算技术的准确性和局限性。

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引用次数: 0

Characteristics of neutron fields around biological shielding of research nuclear reactors in Russia 俄罗斯研究核反应堆生物屏蔽周围的中子场特征

IF 1.6 3区物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Radiation Measurements

Pub Date : 2024-11-08 DOI: 10.1016/j.radmeas.2024.107325

M.D. Pyshkina, A.V. Vasilyev, E.I. Nazarov, A.A. Ekidin

The paper presents the results of a study of the neutron field characteristics surrounding biological shielding of Russian research nuclear reactors to establish their expected behavior and enhance personnel neutron monitoring. The study covered five nuclear research reactors: IVV-2M, IRT-T, IRT-MEPhI, RBT-6, and SM-3. All reactors are pool-typed; some (RBT-6 and SM-3) have pressurized water, while others (IVV-2M, IRT-T, and IRT-MEPhI) have water under normal pressure. The neutron fields analyzed are located at the tank cover of reactors, in front of the reactor core covered with biological shielding, and in front of the horizontal experimental channel. The spectrum average neutron energy ranges from 0.01 MeV (RBT-6) to 1.0 MeV (SM-3). The fluence-to-ambient dose conversion coefficient varies from 15 pSv

∙

cm² (RBT-6) to 260 pSv

∙

cm² (SM-3). The spectra at the other measurement points exhibit the energy distribution characteristics of the neutron radiation flux density behind the biological shielding.

本文介绍了对俄罗斯研究核反应堆生物屏蔽周围中子场特征的研究结果，以确定其预期行为并加强人员中子监测。研究涵盖五个核研究反应堆：IVV-2M、IRT-T、IRT-MEPhI、RBT-6 和 SM-3。所有反应堆都是水池式反应堆；其中一些（RBT-6 和 SM-3）采用加压水，而其他反应堆（IVV-2M、IRT-T 和 IRT-MEPhI）则采用常压水。所分析的中子场位于反应堆水箱盖、生物屏蔽覆盖的堆芯前方以及水平实验通道前方。频谱平均中子能量从 0.01 MeV（RBT-6）到 1.0 MeV（SM-3）不等。通量-环境剂量转换系数从 15 pSv ∙ cm2（RBT-6）到 260 pSv ∙ cm2（SM-3）不等。其他测量点的光谱显示了生物屏蔽后中子辐射通量密度的能量分布特征。

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