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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 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, Dw, 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 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 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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引用次数: 0
Dosimetry for FLASH and other non-standard radiotherapy sources FLASH 和其他非标准放射治疗源的剂量测定
IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-11-08 DOI: 10.1016/j.radmeas.2024.107330
Duncan J. Butler , Micah Barnes , Malcolm R. McEwen , Michael L.F. Lerch , Suzie L. Sheehy , Yaw-Ren E. Tan , Ivan M. Williams , Jacinta S.L. Yap
We review current dosimetry practices for non-standard radiotherapy sources. We classify radiotherapy sources as established, variations of established, or novel. Our review concentrates on novel sources including ultra-high dose-rate (FLASH) sources and some that have yet to be used for clinical radiotherapy. Factors which differentiate non-standard sources include dose-rate, temporal pulse structure, spatial fractionation, focussing, the presence of magnetic fields, and energy range. For the most part we exclude techniques which use materials inside the tumor to modify the dose. Dosimetry techniques include ionization chambers, film, alanine, calorimetry, and solid-state detectors. We review dosimetry only, neglecting other issues such as beam monitoring, patient delivery systems and treatment planning.
我们回顾了当前非标准放射治疗源的剂量测定方法。我们将放射疗法源分为已确立的放射疗法源、已确立放射疗法源的变体或新型放射疗法源。我们的综述主要针对新型放射源,包括超高剂量率(FLASH)放射源和一些尚未用于临床放射治疗的放射源。区分非标准放射源的因素包括剂量率、时间脉冲结构、空间分割、聚焦、磁场的存在以及能量范围。在大多数情况下,我们不包括使用肿瘤内部材料来改变剂量的技术。剂量测定技术包括电离室、胶片、丙氨酸、热量计和固态探测器。我们只审查剂量测定,而忽略了其他问题,如光束监测、病人输送系统和治疗计划。
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引用次数: 0
Thermal stability of the bleachable and unbleachable components of the ESR signals in sedimentary quartz 沉积石英中 ESR 信号的可漂和不可漂成分的热稳定性
IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-11-07 DOI: 10.1016/j.radmeas.2024.107327
Naoya Obata , Shin Toyoda
The thermal stability of the bleachable and unbleachable components of the electron spin resonance signals in quartz grains from modern fluvial sediments were investigated. It was found that the unbleachable Al center is thermally more stable than the bleachable component, hence the unbleachable component can be extracted by heating. Protocols for equivalent dose evaluation with preheating are proposed, in which the procedure of bleaching is replaced by “partial annealing” (heating at 280 °C for 15 min) for the Al center and by “annealing” (heating at 400 °C for 1 h) for the Ti-Li and Ti-H centers. The dose recovery test confirmed that the proposed protocol works practically, and that the regenerative protocol is better than the additive dose protocol in the aspect of the statistical errors. Appropriate partial annealing conditions to extract the unbleachable Al centers may need to be investigated for each sample.
研究了现代河流沉积物中石英颗粒电子自旋共振信号中可漂白和不可漂白成分的热稳定性。研究发现,不可漂白的铝中心的热稳定性高于可漂白成分,因此可通过加热提取不可漂白成分。提出了预热等效剂量评估方案,其中铝中心用 "部分退火"(在 280 °C 下加热 15 分钟)代替漂白过程,钛-锂和钛-氢中心用 "退火"(在 400 °C 下加热 1 小时)代替漂白过程。剂量恢复试验证实,所建议的方案切实可行,而且在统计误差方面,再生方案优于加剂量方案。为提取不可漂白的铝中心,可能需要针对每个样品研究适当的部分退火条件。
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引用次数: 0
Deep learning-based alpha particles spectroscopy with solid-state nuclear track detector CR-39 利用固态核轨道探测器 CR-39 进行基于深度学习的阿尔法粒子光谱分析
IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-11-06 DOI: 10.1016/j.radmeas.2024.107326
G. Amit , N. Guy-Ron , O. Even-Chen , N.M. Yitzhak , N. Nissim , R. Alimi
A novel approach for alpha particles energy spectroscopy utilizing a sophisticated deep learning machine learning algorithm is introduced. The approach we employ classifies the alpha particles trajectories on a CR-39 detector into six discrete energy levels: 0.5 MeV, 1.5 MeV, 2.5 MeV, 3.5 MeV, 4.5 MeV, and 5.4 MeV. Some 57 different CR-39 detectors were exposed to alpha particles of the stated energy levels using a241Am source. The dosimeters were then subjected to etching and imaging utilizing a Landauer Neutrak© system. A self-developed computer vision method was used to separate the energy-tagged alpha tracks from the CR-39 images. These tracks images were then inputted into an artificial neural network (ANN) algorithm for training. After completing the training, a test dataset was run to assess the algorithm's performance. An average accuracy rate exceeding 98% was attained across the six energy levels.
This algorithm has the potential to enhance the precision of alpha particle dosimetry. Furthermore, once generalized to a continuous energy spectrum, as well as for other types of particles such as protons, this algorithm is anticipated to prove highly beneficial for analyzing the outcomes of various laser-driven high-energy particle experiments in general, and specifically for fusion experiments.
本文介绍了一种利用复杂的深度学习机器学习算法进行阿尔法粒子能谱分析的新方法。我们采用的方法将 CR-39 探测器上的α粒子轨迹分为六个离散能级:0.5 MeV、1.5 MeV、2.5 MeV、3.5 MeV、4.5 MeV 和 5.4 MeV。使用 241Am 源将大约 57 个不同的 CR-39 探测器暴露于所述能级的阿尔法粒子中。然后利用兰道尔 Neutrak© 系统对这些剂量计进行蚀刻和成像。使用自行开发的计算机视觉方法从 CR-39 图像中分离出能量标记的阿尔法轨迹。然后将这些轨迹图像输入人工神经网络 (ANN) 算法进行训练。完成训练后,运行测试数据集以评估算法的性能。该算法有望提高α粒子剂量测定的精确度。此外,该算法一旦推广到连续能谱以及质子等其他类型的粒子,预计将非常有利于分析各种激光驱动的高能粒子实验的结果,特别是核聚变实验的结果。
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引用次数: 0
Development of a compact active neutron monitor to measure the H∗(10): Design, simulation and validation 开发用于测量 H∗(10)的紧凑型主动中子监测器:设计、模拟和验证
IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-11-05 DOI: 10.1016/j.radmeas.2024.107328
Lokendra Singh , P.Y. Bansode , Sabyasachi Paul , S.S. Ghodke , S.P. Borkar , S. Anand
The rapid advancement of radiation technology underscores the need for effective radiation protection and monitoring. Neutron dose equivalent (NDE) meters play a crucial role in measuring the ambient dose equivalent, H∗(10), in neutron radiation environments. However, traditional NDE meters, while effective, tend to be bulky and less suitable for use in anisotropic neutron fields and confined spaces. This study presents the development of a compact, portable NDE meter designed to overcome these challenges. The device, featuring a cylindrical design with a diameter of 14.8 cm, a length of 30.5 cm, and weighing under 4 kg, is optimized for ease of use in constrained spaces. It incorporates a BF3 thermal neutron detector encased within a high-density polyethylene moderation assembly, calibrated to replicate ICRP-74 dose conversion coefficients. The design was optimized using Monte Carlo simulations using FLUKA, emphasizing neutron response uniformity and effective moderation. Experimental validation in standard neutron reference fields confirmed the accuracy of the simulated performance, with dose rate estimates deviating by less than 8% from reference values. The NDE meter's response was consistent with that of commercially available devices, showing relative energy response variations of less than 20% for both 241Am-Be and 252Cf sources. It demonstrated reliable energy response up to 5 MeV and consistent angular response (up to ∼ 60°), highlighting its potential for practical radiation protection applications in diverse and constrained environments.
辐射技术的飞速发展凸显了有效辐射防护和监测的必要性。中子剂量当量(NDE)测量仪在测量中子辐射环境中的环境剂量当量 H∗(10)方面发挥着至关重要的作用。然而,传统的 NDE 测量仪虽然有效,但往往比较笨重,不太适合在各向异性的中子场和密闭空间中使用。本研究介绍了一种紧凑型便携式无损检测仪的开发情况,旨在克服这些挑战。该设备采用圆柱形设计,直径为 14.8 厘米,长度为 30.5 厘米,重量不到 4 千克,经过优化,便于在狭窄空间中使用。它包含一个 BF3 热中子探测器,封装在一个高密度聚乙烯调制组件内,并根据 ICRP-74 剂量转换系数进行了校准。设计是通过使用 FLUKA 进行蒙特卡罗模拟来优化的,强调中子响应的均匀性和有效调节。在标准中子参考场中进行的实验验证证实了模拟性能的准确性,剂量率估计值与参考值的偏差小于 8%。无损检测仪的响应与市售设备一致,对 241Am-Be 和 252Cf 源的相对能量响应变化均小于 20%。它显示了高达 5 MeV 的可靠能量响应和一致的角度响应(高达 ∼ 60°),突出了其在各种受限环境中实际辐射防护应用的潜力。
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引用次数: 0
Accumulation of oxygen interstitial-vacancy pairs under irradiation of corundum single crystals with energetic xenon ions 用高能氙离子辐照刚玉单晶时氧间隙空位对的积累
IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-28 DOI: 10.1016/j.radmeas.2024.107324
Guldar Baubekova , Ruslan Assylbayev , Eduard Feldbach , Aleksei Krasnikov , Irina Kudryavtseva , Alise Podelinska , Viktor Seeman , Evgeni Shablonin , Evgeni Vasil'chenko , Aleksandr Lushchik
Single crystals of α-Al2O3 with broad sides oriented perpendicular to the c crystal axis have been irradiated by 231-MeV xenon ions with fluence varying from 5 × 1011 to 1014 ions/cm2. The spectra of radiation-induced optical absorption (absorption of a pristine crystal is subtracted) have been decomposed into Gaussians serving as a measure of oxygen-related Frenkel defects (interstitial-vacancy pairs). The concentration of all structural defects considered – vacancy-type F and F+ centers as well as oxygen interstitials – continuously increases with ion fluence. Therefore, radiation-induced origin of elementary absorption bands at 5.6 and 6.6 eV tentatively ascribed earlier to charged and neutral oxygen interstitials has been proved for the first time. The concentrations of charged interstitials (in the form of superoxide ions) have been directly determined by the EPR method. The evolution of cathodoluminescence bands typical of self-trapped excitons (VUV band at 7.6 eV) and F-type defects (bands peaked around 3.0 and 3.8 eV) with the rise of Xe-ion-irradiation fluence has been measured and analyzed.
α-Al2O3单晶体的宽边方向垂直于晶体的c轴,受到231-MeV氙离子的辐照,离子流量从5×1011到1014个/cm2不等。辐射诱导的光吸收光谱(原始晶体的吸收被减去)被分解成高斯谱,作为与氧有关的弗伦克尔缺陷(间隙空位对)的测量值。所考虑的所有结构缺陷(空位型 F 和 F+ 中心以及氧间隙)的浓度都会随着离子通量的增加而不断增加。因此,之前暂定为带电和中性氧间隙的 5.6 和 6.6 eV 基本吸收带在辐射诱导下的起源首次得到了证实。带电间隙的浓度(以超氧离子的形式)已通过 EPR 方法直接测定。测量并分析了自俘获激子(7.6 eV 处的紫外波段)和 F 型缺陷(3.0 eV 和 3.8 eV 附近的波段峰值)的阴极发光带随 Xe 离子辐照通量的增加而发生的演变。
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引用次数: 0
Gel dosimetry: An overview of dosimetry systems and read out methods 凝胶剂量测定:剂量测定系统和读出方法概述
IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-28 DOI: 10.1016/j.radmeas.2024.107321
Yves De Deene , Andrew Jirasek
<div><div>Gel dosimetry has emerged over the past three decades in response to a growing need in high-precision radiotherapy to assess, in three dimensions, the absorbed radiation dose, as would be administered in cancer patients.</div><div>Radiation-induced reaction mechanisms are dependent on the class of gel dosimeter, with four classes emerging as primary dosimeters for use in radiation therapy dose verification: (i) Fricke gel dosimeters contain a Fricke solution consisting of ammonium iron (II) sulfate in an acidic solution of sulfuric acid. In Fricke systems an oxidation of ferrous ions results in a change in the nuclear magnetic resonance (NMR) relaxation rate, which enables reading out Fricke gel dosimeters by use of MRI. The radiation-induced oxidation in Fricke gel dosimeters can also be visualized by adding a redox indicator. (ii) Polymer gel dosimeters exploit the radiation induced polymerization reaction of vinyl monomers and are predominantly read out by quantitative MRI or X-ray CT. (iii) Radiochromic dosimeters do not demonstrate a significant radiation-induced change in NMR properties but can be scanned by use of optical scanners (optical CT). In contrast to Fricke gel dosimeters, radiochromic gel dosimeters do not rely on the oxidation of a metal ion but exhibit a color change upon radiation. (iv) Radiofluorogenic dosimeters become fluorescent when exposed to ionizing radiation and can be read out with a planar scanning light beam.</div><div>Likewise, the imaging modality used to extract quantitative dose information depends on the class of dosimeter being used, and three primary imaging modalities have emerged in this context: quantitative MRI, x-ray CT, and optical CT imaging. The accuracy and precision of the dose information extracted from gel dosimetry systems depends on both the dosimetric properties of the gel dosimeters and the readout technique, and the optimal readout method depends on the gel dosimeter response.</div><div>Despite remaining an active field of research and illustrations of the application of gel dosimetry for the validation of clinical dose distributions, the utilization of gel dosimetry as a routine clinical dosimeter has been rather limited. However, with the introduction of new radiotherapy techniques that focus on organ motion compensation, new fractionation schemes, and extreme dose rates, the need for 3D radiation dosimetry is apparent. Even with the need for 3D dosimetry being apparent, gel dosimetry faces continued challenges in areas regarding the extraction of reproducible, accurate, and precise dose information.</div><div>This review paper focuses on an introduction to gel dosimeter classes; a detailed examination of the three readout techniques with emphasis on the achievable accuracy, precision, and optimization of readout parameters; an outlook on future applications in emerging new radiotherapy techniques. We note that the introduction of theragnostic hybrid MRI-Linacs that combine an MR
辐射诱导反应机制取决于凝胶剂量计的类别,有四类剂量计成为放射治疗剂量验证的主要剂量计:(i) 弗里克凝胶剂量计含有弗里克溶液,由硫酸酸性溶液中的硫酸铁(II)铵组成。在 Fricke 系统中,亚铁离子的氧化会导致核磁共振(NMR)弛豫速率的变化,从而可以利用核磁共振读出 Fricke 凝胶剂量计。通过添加氧化还原指示剂,也可观察到辐射在弗里克凝胶剂量计中引起的氧化。(ii) 聚合物凝胶剂量计利用乙烯基单体的辐射诱导聚合反应,主要通过磁共振成像或 X 射线 CT 定量读出。(iii) 放射性变色剂量计的核磁共振特性不会因辐射而发生显著变化,但可通过光学扫描仪(光学 CT)进行扫描。与弗里克凝胶剂量计不同,放射性变色凝胶剂量计不依赖金属离子的氧化,而是在辐射时显示颜色变化。(同样,用于提取定量剂量信息的成像模式取决于所使用的剂量计类别,在这方面出现了三种主要的成像模式:定量核磁共振成像、X 射线 CT 和光学 CT 成像。从凝胶剂量计系统中提取的剂量信息的准确性和精确度取决于凝胶剂量计的剂量学特性和读出技术,而最佳读出方法取决于凝胶剂量计的响应。尽管凝胶剂量计在临床剂量分布验证方面的应用仍是一个活跃的研究领域和例证,但凝胶剂量计作为常规临床剂量计的应用却相当有限。然而,随着以器官运动补偿为重点的新放疗技术、新的分割方案和极高剂量率的引入,对三维放射剂量测定的需求显而易见。本综述主要介绍凝胶剂量计的种类;详细研究三种读出技术,重点是可实现的准确度、精确度和读出参数的优化;展望未来在新兴放射治疗技术中的应用。我们注意到,将核磁共振成像扫描仪和临床直线加速器结合在一起的混合核磁共振成像-直线加速器为在线聚合物凝胶剂量测定创造了新的机会。同样,在直线加速器上使用锥形束 CT 也为在直线加速器上读出凝胶剂量计提供了可能。多种光学 CT 设计表明,光学 CT 凝胶剂量测定能够从临床相关的治疗方案中提供高质量的剂量信息。因此,凝胶剂量测定为三维辐射剂量测定提供了令人兴奋的机会,而这在几年前是无法实现的。正确执行凝胶剂量测定工作流程的独特功能集可以提取三维剂量信息,这是其他任何剂量测定系统都无法做到的,因此凝胶剂量测定为辐射剂量测量领域的临床和研究工作提供了令人兴奋的机会。
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引用次数: 0
Evaluation of a portable OSL/IRSL reader for radiation dose assessment of NaCl pellets – In situ individualised screening during R/N emergencies 评估用于氯化钠颗粒辐射剂量评估的便携式 OSL/IRSL 阅读器--R/N 紧急情况下的现场个性化筛查
IF 1.6 3区 物理与天体物理 Q2 NUCLEAR SCIENCE & TECHNOLOGY Pub Date : 2024-10-26 DOI: 10.1016/j.radmeas.2024.107323
Maria Karampiperi, Christopher L. Rääf, Christian Bernhardsson
Household salt, Sodium Chloride (NaCl), has been suggested as an appropriate material for retrospective and prospective optically stimulated luminescence (OSL) radiation dosimetry. The current paper investigates the potential application of NaCl pellets during a radiological and/or nuclear emergency, together with an existing portable reader, for application as a novel tool for in situ screening of individual doses in exposed populations.
The evaluation of the portable reader's performance was assessed based on OSL and infra-red stimulated luminescence (IRSL) methods and the results were compared to two research readers, Risø TL/OSL (DA-20 and DA-15). For the studied absorbed dose range (0.63–487 mGy), it was found that five pellets are needed in the portable reader to achieve a similar OSL signal magnitude as using one pellet in the two research readers. The OSL results of the three readers show similar minimum detectable dose (MDD) values and similar linear trends for the obtained OSL dose response curves, within the studied dose range. The IRSL results show a lower IRSL signal for the portable reader, leading to higher MDD values compared to the stationary readers. The MDD can reach down to 2.3 and 47 μGy, respectively, for OSL and IRSL measurements of NaCl with the SUERC portable reader.
Furthermore, sensitization tests show a dose dependent increase in the OSL and IRSL signals. In addition, the possibility of reading the same pellets more than once was confirmed through an advanced protocol, which combines multiple read-outs, and a time delay test. If a combination of OSL and IRSL measurements is applied, it is important to adjust the stimulation length if the first is OSL, while in the case that the first measurement is IRSL, the OSL signal is independent of the IRSL stimulation length.
家用盐氯化钠(NaCl)被认为是一种适用于回顾性和前瞻性光激发发光(OSL)辐射剂量测定的材料。本文研究了在辐射和/或核紧急情况下将氯化钠颗粒与现有的便携式读数器结合使用的可能性,并将其作为一种新型工具用于对受辐射人群的个人剂量进行现场筛查。根据 OSL 和红外激发发光(IRSL)方法对便携式读数器的性能进行了评估,并将评估结果与两台研究型读数器 Risø TL/OSL (DA-20 和 DA-15)进行了比较。研究发现,在所研究的吸收剂量范围(0.63-487 mGy)内,便携式阅读器需要使用五个颗粒才能获得与两台研究型阅读器使用一个颗粒相似的 OSL 信号幅度。在所研究的剂量范围内,三种阅读器的 OSL 结果显示出相似的最小可检测剂量 (MDD) 值和相似的 OSL 剂量响应曲线线性趋势。IRSL 结果显示,便携式阅读器的 IRSL 信号较低,导致 MDD 值高于固定式阅读器。使用 SUERC 便携式读取器对氯化钠进行 OSL 和 IRSL 测量时,MDD 分别可低至 2.3 和 47 μGy。此外,通过结合多次读出和时间延迟测试的先进方案,确认了对同一颗粒进行多次读取的可能性。如果结合使用 OSL 和 IRSL 测量,如果第一次测量的是 OSL,则必须调整刺激长度;如果第一次测量的是 IRSL,则 OSL 信号与 IRSL 刺激长度无关。
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Radiation Measurements
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