Nuclear Engineering and Technology最新文献

Organ doses for monkey anatomy models with different postures exposed to external photons

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-21 DOI: 10.1016/j.net.2025.103603

Jae W. Jung , Daniel D. Lee , Ae-Kyoung Lee , Hyung-Do Choi

Background

Understanding how external radiation from nuclear accidents or radiological attacks affects internal human anatomy is essential to accurately assess health risks and develop effective treatments. we calculated a library of organ dose conversion coefficients for anatomical monkey models in a standing, crawling, and squatting postures for the first time by using Monte Carlo radiation transport methods combined with anatomical monkey models.

Methods

We adopted previously published anatomical monkey models with three different postures: crawling, squatting, and standing. Radiation doses to a total of 39 organs and tissues were calculated using a general-purpose Monte Carlo radiation transport code, MCNP6.2, for the photon fields with 33 mono-energy bins ranging from 0.01 to 20 MeV in six different irradiation geometries: antero-posterior (AP), postero-anterior (PA), left lateral (LLAT), right lateral (RLAT), rotational (ROT), and isotropic (ISO).

Results

We found that the dose conversion coefficients derived from the standing posture may overestimate organ dose by up to 13-fold compared to the crawling position (e.g., large intestine in AP irradiation geometry). Irradiation geometry has the most substantial impact on organ doses in the crawling posture compared to squatting and standing postures. Average coefficients of variation over different organs were 51 % in crawling posture compared to 16 % and 17 % for standing and squatting postures, respectively.

Conclusion

In the present research, we employed the Monte Carlo radiation transport techniques to develop a library of organ dose conversion coefficients for an anatomical monkey model considering various postures and six distinct irradiation geometries. We found that the existing dose conversion coefficients for the standing posture may substantially overestimate organ doses for monkeys in more natural postures. Our data should be useful for understanding the impact of radiation events to human anatomy by evaluating the impact on monkey's anatomy as a surrogate.

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引用次数: 0

Dynamic response of a freely rotating butterfly valve in the advanced test reactor – dynamic fluid-body interaction modeling 先进试验反应堆中自由旋转蝶阀的动态响应--动态流体-体相互作用建模

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-21 DOI: 10.1016/j.net.2025.103658

Changhu Xing, Carlos E. Estrada Perez, Casey J. Jesse, Lucas D. Zachow

To regulate primary coolant flow in the Advanced Test Reactor (ATR), a butterfly valve was installed between the primary coolant pumps and the reactor core. If the mechanical connection between the valve's disk and its shaft ever fails, the disk will rotate freely. Rapid disk rotation may induce pressure surges that could damage upstream pipes. In the present work, the rotational trajectory and pressure evolution during a disk free-rotation scenario were analyzed via the dynamic fluid-body interaction (DFBI) approach in STAR-CCM+, with the movement of a solid being driven by the forces and moment/torque imposed by its surrounding fluid. Assuming a large initial opening angle, the disk accelerates slowly, but swiftly passes the closed position. As a result of the sudden valve closure, a pressure surge occurs in the upstream pipes, exceeding their maximum allowable pressure. Furthermore, the disk does not stabilize at the closed position but continually oscillates due to the unsteady nature of the coolant flow. Because of the significant and continuous water hammer effect, a fix to the butterfly valve is being implemented to prevent rapid valve closure due to failure at the valve's disk/shaft mechanical connection.

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引用次数: 0

Hybrid machine learning model with optimization algorithm for predicting the incubation dose of void swelling in irradiated metals 混合机器学习模型与优化算法用于预测辐照金属空洞膨胀的培育剂量

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-21 DOI: 10.1016/j.net.2025.103661

Van-Thanh Pham, Kyoon-Ho Cha, Jong-Sung Kim

This study introduces novel hybrid machine learning (ML) models that integrate six state-of-the-art ML algorithms with the Harris Hawks Optimization (HHO) algorithm to enhance the prediction of the incubation dose in irradiated metals. A comprehensive database comprising 305 experimental samples with 24 input features is used to develop the models, with hyperparameters optimized through a combination of cross-validation method and HHO. Performance evaluation across various metrics identifies the hybrid model combining HHO and categorical gradient boosting (CGB), named HHO-CGB, as the most accurate and stable for predicting the incubation dose. To gain further insights, the Shapley Additive Explanations method is employed to assess the global and local contributions of input variables, revealing Fe (wt.%), temperature (K), dose rate (dpa/s), and V (wt.%) as the most influential factors. Finally, a user-friendly graphical interface tool and web application are developed based on the HHO-CGB model, providing a practical and cost-effective solution for predicting the incubation dose of irradiated metals.

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引用次数: 0

Time-of-flight based one-dimensional position estimation of radioactive sources using artificial neural network model

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-21 DOI: 10.1016/j.net.2025.103662

Jinhong Kim , Siwon Song , Jae Hyung Park , Seunghyeon Kim , Sangjun Lee , Seung Hyun Cho , Cheolhaeng Huh , Bongsoo Lee

This study presents a novel approach for one-dimensional gamma ray source position estimation by integrating plastic scintillating fiber technology, time-of-flight (ToF) measurements, and artificial neural network (ANN) techniques. The methodology employs a systematic signal processing framework consisting of constant fraction discrimination (CFD) for precise timing extraction, amplitude-based filtering for noise reduction, and statistical analysis of ToF data to enhance measurement consistency. A two-stage ANN architecture was developed incorporating dual hidden layers with ReLU activation functions and weighted correction factors to optimize spatial localization performance. The system was experimentally validated using a Cs-137 radiation source across a 10-m measurement range with data collected at both regular intervals and random positions to assess interpolation capabilities. Comparative analysis between the ANN-based approach and theoretical calculations demonstrated a 90.17 % enhancement in position estimation precision, achieving an average error of 0.0225 m compared to 0.2289 m with conventional methods. Standard deviations in position estimates remained consistently below 0.1 m across the operational range, indicating robust performance stability. These results substantiate that combining sophisticated timing measurements with machine learning strategies advances radiation detection systems applicable to environmental monitoring, nuclear safety protocols, and emergency response scenarios.

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引用次数: 0

Investigation of shielding properties and mechanisms of boron-containing magnesium-rich tailings for nuclear shielding application

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-20 DOI: 10.1016/j.net.2025.103660

Mengge Dong , G. Lakshminarayana , Xuefei Zhang , Xiangxin Xue

Efficient utilization of boron-containing magnesium-rich tailings (BCMRTs) represents a critical challenge for the sustainable development of boron industry. This study introduces an innovative approach to repurpose BCMRTs as shielding materials and systematically investigates their shielding properties and underlying mechanisms against thermal/fast neutrons, and gamma rays. The findings demonstrate that BCMRTs exhibit exceptional thermal neutron attenuation, achieving a shielding efficiency of up to 100 % with merely 1 cm of material, thereby surpassing the performance of certain commercially available shields. However, further optimization is necessary to enhance their efficiency against fast neutrons and gamma rays. Neutron attenuation mechanism is predominantly governed by absorption effect of boron in low-energy range, elements with higher atomic number contribute in middle energy range through elastic scattering, and both elastic and inelastic scattering in high energy range. Gamma ray attenuation mechanism is predominantly governed by elements with high atomic number, with distinct nuclear interactions dominating across various energy ranges. Furthermore, comprehensive attenuation parameters for both narrow-beam and wide-beam gamma rays within the 0.001–100,000 MeV range are presented. This research provides critical insights into the potential application of BCMRTs in the development of advanced shielding materials.

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引用次数: 0

Optimization of a water-intake system for monitoring radionuclides in aquatic environments

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-18 DOI: 10.1016/j.net.2025.103656

Dayeong Lee , Seongjin Maeng , Sang Hoon Lee

We designed and characterized a water-intake radiation monitoring system using a 3" × 3″ NaI(Tl) detector for real-time monitoring of, for example, nuclear power plant radioactive effluents. The MCNP6 code was used to determine the optimized container size and detector position for homogeneous ¹³¹I and ¹³⁷Cs volumetric sources. Based on the simulation results, the dimensions of the monitoring system were determined. The simulation model was initially verified by comparison with the measurement results of a paper filter certified reference materials in water. Subsequently, it was further validated by comparison with the detection efficiency for ⁴⁰K in a KCl volumetric source measurement experiment, which confirmed that the detection efficiency well matched experimental data for volumetric sources. Using the validated simulation model, the detection efficiency of ¹³¹I and ¹³⁷Cs volumetric sources in a water-filled container was assessed. To consider background radioactivity, three types of water samples—freshwater, brackish water, and seawater—were experimentally measured. Based on these measurements, the minimum detectable activity for ¹³¹I and ¹³⁷Cs volumetric sources was determined for each of the three water sample types.

我们设计并鉴定了一种使用 3" × 3″ NaI(Tl) 探测器的进水辐射监测系统，用于实时监测核电厂放射性流出物等。MCNP6 代码用于确定均质 131I 和 137Cs 容积源的优化容器尺寸和探测器位置。根据模拟结果，确定了监测系统的尺寸。通过与水中纸质过滤器认证参考材料的测量结果进行比较，初步验证了模拟模型。随后，通过与氯化钾体积源测量实验中 40K 的检测效率进行比较，进一步验证了模拟模型，结果证实检测效率与体积源的实验数据完全吻合。利用经过验证的模拟模型，评估了装水容器中 131I 和 137Cs 体积源的探测效率。为了考虑本底辐射，对淡水、苦咸水和海水三种水样进行了实验测量。根据这些测量结果，确定了 131I 和 137Cs 体积源在这三种水样中的最低可探测活度。

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引用次数: 0

Adjustment of reactor pressure vessel embrittlement trend curves using a mixed-effects model

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-17 DOI: 10.1016/j.net.2025.103654

Gyeong-Geun Lee, Bong-Sang Lee, Min-Chul Kim, Junhyun Kwon, Jong-Min Kim

This study presents a novel approach for adjusting the generic reactor pressure vessel embrittlement trend curve (ETC), ASTM E900-15, using a mixed-effects model based on Baseline22, a compiled dataset of surveillance test data from nuclear power plants worldwide. Using this statistical framework, systematic deviations owing to initial material properties, notch orientations, and other plant-specific factors were separated from measurement errors, providing a more accurate assessment of embrittlement trends. Two types of adjustment models were explored: an intercept-only model (AM3) and a combined intercept-slope model (AM6). The AM3 model, which estimates only group-specific intercepts, effectively reduces prediction errors compared to ASTM E900-15 model while maintaining interpretability and simplicity, making it particularly suitable for regulatory applications. AM6, which incorporates group-specific slopes and covariance terms, further improves predictive accuracy, but introduces estimation complexities, so its suitability for conservate regulatory applications requires further discussion. To facilitate the practical implementation of AM3, closed-form expressions for group-specific intercept adjustments were derived, enabling the estimation of adjustment factors without the need for Bayesian Markov chain Monte Carlo models or complex statistical tools. Additionally, the standard deviations of the intercept means and prediction intervals were formulated as functions of the group size, providing a straightforward method for assessing embrittlement trends as new surveillance test results became available. This study demonstrates that existing generic ETC models can be dynamically refined and updated using plant-specific surveillance test data, while maintaining robustness and regulatory applicability. These findings lay the groundwork for the future refinement of standard ETC models, potential integration with regulatory frameworks, and improved long-term integrity assessments of reactor pressure vessels in aging nuclear power plants.

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引用次数: 0

Optimization of operating conditions for Gamma Emission Tomography to improve partial-defect detection accuracy within PWR-type spent nuclear fuel

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-17 DOI: 10.1016/j.net.2025.103644

Hyung-Joo Choi , Hyun Joon Choi , Hyun Cheol Lee , Yong Hyun Chung , Chul Hee Min

The Spent Nuclear Fuel (SNF) contains a variety of nuclear material that can be diverted for military purposes and unauthorized proliferation. To ensure safety management and non-proliferation of SNF, an effective inspection method, such as Gamma Emission Tomography (GET) is necessary. In the previous study, the Yonsei Single-photon Emission Computed Tomography (YSECT) instrument was proposed and developed. To improve inspection accuracy in the central region containing the high-density SNF rod, the operating conditions, such as energy window and rotation interval, of the YSECT instrument are optimized in this study. The tomographic images were obtained under various operating conditions, and each condition was optimized by evaluating the quality of the tomographic image. Based on the results, the optimal energy window and rotation interval were determined to be 1274 keV region and 1-degree, respectively. The Signal-to-Noise Ratio (SNR) was improved 1.32-fold with optimized energy window compared to conventional energy window (6.98 of SNR for 662 keV region). Also, the streak artifact was reduced through the application of the optimized rotation interval. These optimized conditions improved inspection accuracy for partial-defect detection. In the future, the experimental study with the mock-up of SNF and pool will be conducted to validate the optimized operating conditions.

乏核燃料（SNF）中含有各种核材料，可能被转用于军事目的或未经授权的扩散。为确保乏核燃料的安全管理和不扩散，有必要采用有效的检测方法，如伽马射线发射断层扫描（GET）。之前的研究提出并开发了延世单光子发射计算机断层扫描（YSECT）仪器。为了提高包含高密度 SNF 棒的中心区域的检测精度，本研究对 YSECT 仪器的工作条件（如能量窗口和旋转间隔）进行了优化。在不同的操作条件下获得了断层扫描图像，并通过评估断层扫描图像的质量对每种条件进行了优化。根据结果，确定最佳能量窗口和旋转间隔分别为 1274 keV 区域和 1 度。与传统能量窗口相比，优化能量窗口的信噪比（SNR）提高了 1.32 倍（662 keV 区域的信噪比为 6.98）。此外，应用优化的旋转间隔还减少了条纹伪影。这些优化条件提高了部分缺陷检测的准确性。今后，将利用 SNF 和水池模型进行实验研究，以验证优化后的操作条件。

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引用次数: 0

Investigation of optical and radiation shielding properties in bismuth oxide-doped barium borate glasses

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-17 DOI: 10.1016/j.net.2025.103633

Mohammad H. Alhakami , A.S. Abouhaswa , Numa A. Althubiti , Taha Abdel Mohaymen Taha

This study presents a novel exploration of barium borate glasses doped with bismuth oxide (Bi₂O₃) to simultaneously enhance their optical and radiation shielding properties. Using a melting-quenching technique, a series of glasses with compositions of (65-x)B₂O₃ + 5WO₃ + 20BaO + 10Na₂O + xBi₂O₃ (where x = 0, 5, 10, 15, and 20 mol%) was produced. X-ray diffraction analysis (XRD) confirmed the amorphous nature of the samples, while Fourier-transform infrared spectroscopy (FTIR) revealed the conversion of trigonal [BO₃] to tetrahedral [BO₄] units in the glass structure. The incorporation of Bi₂O₃ led to a significant increase in density and molar volume. The optical band gap decreased from 3.96 eV to 3.30 eV with higher Bi₂O₃ concentrations. Notably, the refractive index also increased from 1.49 to 1.63 with the addition of Bi₂O₃. The elastic moduli (Young's modulus, shear modulus, and bulk modulus) decreased with increasing Bi₂O₃ content. Additionally, the analysis of radiation shielding effectiveness demonstrated that Bi₂O₃ significantly increased both the mass attenuation coefficient (MAC) and linear attenuation coefficient (LAC), particularly for low-energy photon interactions, making these glasses suitable for applications involving gamma and X-ray radiation protection. The results establish the potential of Bi₂O₃-doped barium borate glasses as advanced materials for radiation shielding, photonic devices, and other optoelectronic applications.

本研究对掺杂氧化铋（Bi2O3）的硼酸钡玻璃进行了新的探索，以同时增强其光学和辐射屏蔽性能。利用熔融淬火技术，制备了一系列成分为 (65-x)B2O3 + 5WO3 + 20BaO + 10Na2O + xBi2O3（其中 x = 0、5、10、15 和 20 mol%）的玻璃。X 射线衍射分析 (XRD) 证实了样品的无定形性质，而傅立叶变换红外光谱 (FTIR) 则显示了玻璃结构中三方 [BO3] 单元向四面体 [BO4] 单元的转化。加入 Bi2O3 后，密度和摩尔体积显著增加。随着 Bi2O3 浓度的增加，光带隙从 3.96 eV 下降到 3.30 eV。值得注意的是，随着 Bi2O3 的加入，折射率也从 1.49 增至 1.63。弹性模量（杨氏模量、剪切模量和体积模量）随着 Bi2O3 含量的增加而降低。此外，对辐射屏蔽效果的分析表明，Bi2O3 显著提高了质量衰减系数（MAC）和线性衰减系数（LAC），特别是在低能量光子相互作用时，使这些玻璃适用于涉及伽马射线和 X 射线辐射防护的应用。研究结果证明了掺杂 Bi2O3 的硼酸钡玻璃作为辐射屏蔽、光子器件和其他光电应用的先进材料的潜力。

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引用次数: 0

Development of robust nuclear safeguards methods for gas centrifuge enrichment plants

IF 2.6 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Technology

Pub Date : 2025-04-16 DOI: 10.1016/j.net.2025.103653

Donghyeok Koo , Junyoung Seo , Seung Min Woo , Byeongjun Kim , Kyunam Kim , Eunju Jun , Soon Heung Chang

The role of nuclear energy in reducing carbon emissions has becomes increasingly significant with the intensifying climate crisis. The supply of nuclear fuels, particularly high-assay low-enriched uranium, has gained prominence with the growing demand for nuclear energy. However, the development of this technology has been challenged by proliferation risks associated with enrichment facilities. Expanding nuclear energy while securing robust nonproliferation measures is essential for maximizing the potential of nuclear energy while ensuring its peaceful application. This study proposes advanced safeguards for gas centrifuge enrichment plants for mitigating these risks and enhancing the benefits of nuclear energy. This paper introduces eight measures, including the implementation of a remote shutdown system and an off-grid power system, which are advanced safeguards that have not been utilized previously. In addition, new convergence technologies such as the instrumentation cross-verification system, digital twin real-time nuclear material control and accounting system, and remotely piloted quasi-inspection drone robot were introduced for enhancing the safeguards. Further, enhanced verification, increased sample sizes, and resident inspectors aim to rigorously enforce the existing safeguards. When implemented in a coordinated manner, these safeguard measures have the potential to enhance proliferation resistance in uranium enrichment plants while promoting their peaceful use.

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引用次数: 0