Nuclear Engineering and Technology最新文献_第4页

The study of characteristics of flat panel detectors without semiconductor conversion layers for therapeutic high-energy X-ray radiation 治疗性高能x射线辐射无半导体转换层平板探测器特性研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-10 DOI: 10.1016/j.net.2025.103907

Dong Ho Lee , Sangmin Lee , Hyounggun Lee , Kyunghoon Yoon , Kang Heo , Yeong Jun Han , Dooho Kim , Jeyong Jeon , Hyeon Jae Yu , Dong Wook Kim , Jin Sung Kim

{"title":"The study of characteristics of flat panel detectors without semiconductor conversion layers for therapeutic high-energy X-ray radiation","authors":"Dong Ho Lee , Sangmin Lee , Hyounggun Lee , Kyunghoon Yoon , Kang Heo , Yeong Jun Han , Dooho Kim , Jeyong Jeon , Hyeon Jae Yu , Dong Wook Kim , Jin Sung Kim","doi":"10.1016/j.net.2025.103907","DOIUrl":"10.1016/j.net.2025.103907","url":null,"abstract":"<div><div>We evaluated a novel 2-D flat-panel detector (FPD) adapting it for megavoltage (MV) therapeutic imaging and radiation QA. The prototype uses a thick dielectric layer to create a semi-transmissive structure, changing and eliminating structure conventional semiconductor conversion layers. Performance was tested on a Harmony Pro LINAC (Elekta, Sweden) with a 20 × 20 cm<sup>2</sup> field at an SSD of 100 cm. Datasets were acquired at 50–300 MU for 6, 10, and 15 MV beams. Linearity with MU was excellent (R<sup>2</sup> = 0.99). Reproducibility and repeatability showed coefficients of variation of 1–2 %. In energy dependency, the 6/10 MV response ratio remained near 80 %, rising to 84 % at 300 MU, while the 6/15 MV ratio was 70.8 % at 50 MU and stabilized at 75–80 % thereafter, with R<sup>2</sup> > 0.99 for all energies. Spatial resolution satisfied AAPM TG-142 tolerances. The detector demonstrates performance characteristics comparable to those of conventional electronic portal imaging device (EPID), exhibiting robust durability in high-energy irradiation and excellent portability enabled by its compact design.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103907"},"PeriodicalIF":2.6,"publicationDate":"2025-09-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145045914","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Development and validation of the MCCI module in the SAFARI integrated severe accident analysis code SAFARI集成严重事故分析代码中MCCI模块的开发和验证

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-09 DOI: 10.1016/j.net.2025.103913

Jun Sung Choi , Tae Hwan Kim , Jin-Woo Kim , Eung Soo Kim , Hyun Sun Park

{"title":"Development and validation of the MCCI module in the SAFARI integrated severe accident analysis code","authors":"Jun Sung Choi , Tae Hwan Kim , Jin-Woo Kim , Eung Soo Kim , Hyun Sun Park","doi":"10.1016/j.net.2025.103913","DOIUrl":"10.1016/j.net.2025.103913","url":null,"abstract":"<div><div>This study presents the development and validation of the MCCI (Molten Core-Concrete Interaction) analysis module within the SAFARI (Safety Analysis Code For Severe Accident Risk Identification) code, a regulatory severe accident analysis tool under development in South Korea. The SAFARI code is designed to support Severe Accident Management (SAM) actions. As part of this code, a dedicated module has been developed using a Python-based computational framework specifically designed to perform MCCI analysis. Since MCCI plays a critical role in determining the progression and consequences of ex-vessel severe accidents, it is essential for the regulatory code to include a module capable of accurately analyzing MCCI behavior under a wide range of severe accident scenarios. Under these development objectives, the MCCI module incorporates multi-physics models capable of simulating key phenomena associated with corium-concrete interactions. Validation of the MCCI module was performed using experimental data from selected experiments, specifically ACE-L2, SURC-2, and CCI-2, covering validation scenarios for MCCI geometry, concrete type, and cavity conditions. The simulation results showed good agreement with experimental trends, demonstrating the module's reliability. Additionally, comparative analysis with other existing codes confirmed that the module delivers comparable performance, supporting its applicability in regulatory safety evaluations.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103913"},"PeriodicalIF":2.6,"publicationDate":"2025-09-09","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145106420","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on efficient calculation scheme for large domain of reactor core 反应堆堆芯大范围有效计算方案的研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-08 DOI: 10.1016/j.net.2025.103912

Yuchen Sun , Min Zhang , Guangliang Chen , Qiang Zhao , Hao Qian , Yizhi Tian , Gang Tan

{"title":"Research on efficient calculation scheme for large domain of reactor core","authors":"Yuchen Sun , Min Zhang , Guangliang Chen , Qiang Zhao , Hao Qian , Yizhi Tian , Gang Tan","doi":"10.1016/j.net.2025.103912","DOIUrl":"10.1016/j.net.2025.103912","url":null,"abstract":"<div><div>This paper proposes an efficient calculation scheme to address the issues of low computational accuracy and efficiency in traditional porous media models. These models often fail to clearly define fuel component characteristic regions and suffer from low computational efficiency. The scheme aims to establish a data transfer bridge from refining computational models to porous media models by finely decomposing fuel assemblies, thereby improving calculation accuracy and resolution. Additionally, a fast reconfiguration calculation module based on a flow field reconfiguration scheme is proposed. This module leverages existing cases to rapidly analyze changes under different conditions, offering high computational efficiency and the ability to process batch data. Compared to traditional porous media models, the proposed scheme significantly enhances computational efficiency, reducing the core calculation time to as little as 2–3 s. This work provides valuable reference for efficient calculation and analysis of large domains in reactor cores.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103912"},"PeriodicalIF":2.6,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145106416","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Quantifying the effectiveness of fixative coatings in reducing airborne release fractions under impact stress 量化固定涂层在冲击应力下减少空气中释放组分的有效性

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-08 DOI: 10.1016/j.net.2025.103911

Mellissa Komninakis , Joseph Sinicrope , James C. Nicholson , Leonel Lagos , Daniela Radu

{"title":"Quantifying the effectiveness of fixative coatings in reducing airborne release fractions under impact stress","authors":"Mellissa Komninakis , Joseph Sinicrope , James C. Nicholson , Leonel Lagos , Daniela Radu","doi":"10.1016/j.net.2025.103911","DOIUrl":"10.1016/j.net.2025.103911","url":null,"abstract":"<div><div>The decontamination and decommissioning (D&D) of nuclear facilities present significant challenges due to residual radioactive contamination, which threatens workers, the public, and the environment. Accurate airborne release fractions (ARFs) estimations are critical for safety assessments and regulatory compliance. However, the ARF values currently in DOE-HDBK-3010, are based on decades-old studies and do not account for modern contamination control technologies. Fixative coatings have emerged as a promising solution for stabilizing radioactive particles, preventing their resuspension, and minimizing airborne contamination risks. Despite their widespread use, no academic study to date has quantified a fixative's ability to reduce contamination release.</div><div>This study provides the first empirical data on ARF reductions for fixative-coated surfaces under mechanical impact stress. Controlled experimental methodologies comparing coated and uncoated surfaces show that fixative coatings reduce ARFs by two to three orders of magnitude, demonstrating their effectiveness in airborne contamination mitigation. These findings support incorporating a “fixative” designation into DOE-HDBK-3010 to refine regulatory risk assessments, optimize operational efficiency, and reduce unnecessary conservatism. Furthermore, this study contributes to the standardization of testing protocols through ASTM International, promoting broader adoption of fixative technologies in nuclear facility decommissioning. The results highlight fixatives’ potential to enhance safety and cost-effectiveness while ensuring regulatory compliance.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103911"},"PeriodicalIF":2.6,"publicationDate":"2025-09-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145106419","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Investigation of ensemble Kalman filter-based data assimilation for turbulent flow in a 3×3 rod bundle 基于集合卡尔曼滤波的3×3棒束湍流数据同化研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-07 DOI: 10.1016/j.net.2025.103899

Yuguan Jin , Guangliang Chen , Zhaofei Tian

{"title":"Investigation of ensemble Kalman filter-based data assimilation for turbulent flow in a 3×3 rod bundle","authors":"Yuguan Jin , Guangliang Chen , Zhaofei Tian","doi":"10.1016/j.net.2025.103899","DOIUrl":"10.1016/j.net.2025.103899","url":null,"abstract":"<div><div>Computational Fluid Dynamics (CFD) has advanced rapidly in reactor core thermal-hydraulics, serving as a vital tool for nuclear reactor safety and performance analysis. This study addresses uncertainties in complex turbulence simulations within reactor cores, proposing a novel approach to optimize Reynolds-Averaged Navier-Stokes (RANS) models using the Ensemble Kalman Filter (EnKF) data assimilation method. By simulating turbulent flow in a 3 × 3 rod bundle channel and using time-averaged velocity fields from Particle Image Velocimetry (PIV) as observational data, an observation operator maps local velocity measurements to full-field turbulence parameters, optimizing key RANS closure parameters. Results show that the EnKF-optimized RANS model significantly improves the accuracy of velocity and turbulent kinetic energy predictions, with relative errors below 1 % in most regions, outperforming the original model. This approach provides a data-driven optimization paradigm for high-fidelity reactor thermal-hydraulic simulations, supporting complex confined turbulence modeling and multi-physics coupling analysis. However, further validation is needed to explore additional factors affecting assimilation performance in nuclear reactor systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 2","pages":"Article 103899"},"PeriodicalIF":2.6,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145157132","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Multiphysics assessment including phase change evaluation under severe accident conditions for UO2 doped with burnable absorbers 含可燃吸收剂的UO2在严重事故条件下的相变多物理场评价

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-06 DOI: 10.1016/j.net.2025.103896

Mohamed Y.M. Mohsen , Shlash A. Luhaib , Nassar Alnassar , Mostafa M.A. Khater , A. Abdelghafar Galahom

{"title":"Multiphysics assessment including phase change evaluation under severe accident conditions for UO2 doped with burnable absorbers","authors":"Mohamed Y.M. Mohsen , Shlash A. Luhaib , Nassar Alnassar , Mostafa M.A. Khater , A. Abdelghafar Galahom","doi":"10.1016/j.net.2025.103896","DOIUrl":"10.1016/j.net.2025.103896","url":null,"abstract":"<div><div>Multiphysics analyses are crucial for accurately evaluating the performance of nuclear reactors beyond the limitations of traditional single-physics approaches. This study investigates novel fuel materials consisting of traditional UO<sub>2</sub> homogeneously doped with burnable absorbers (BAs). The effect of doping BAs with nuclear fuel on the VVER-1200 was analyzed from both neutronic and thermal-hydraulic perspectives. Initially, the optimal BA concentration for the candidates was determined based on its effectiveness in mitigating excess reactivity while extending the fuel cycle length compared to conventional UO<sub>2</sub> fuel. Then, a detailed neutronic analysis was performed on the optimized compositions to identify the most effective BA material. Utilizing the radial power distribution obtained, thermal-hydraulic analyses were conducted under normal operation, followed by transient simulation of a large LOCA scenario. Phase change modeling was implemented for both proposed fuels and cladding materials to evaluate their thermal resilience and failure thresholds at both beginning of fuel cycle (BOC) and mid of fuel cycle (MOC). Doping BAs with UO<sub>2</sub> achieved various benefits from a neutronic standpoint while quantifying its impact on thermal-hydraulic performance under both normal and severe transient conditions, offering insights into the feasibility of BA-doped fuels for enhanced reactor safety.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103896"},"PeriodicalIF":2.6,"publicationDate":"2025-09-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145027213","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Feasibility study on the core design of high-flux fast neutron research reactors 高通量快中子研究堆堆芯设计可行性研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-06 DOI: 10.1016/j.net.2025.103909

Miao Zhao , Xianan Du , Youqi Zheng , Mingyu Wu , Rui Yang , Li Xu , Liangzhi Cao , Hongchun Wu

引用次数: 0

Tetrahedral mesh Visible Monkey phantom for radiation dosimetry research 用于辐射剂量学研究的四面体网格可见猴影

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-06 DOI: 10.1016/j.net.2025.103903

Bangho Shin , Thang Tat Nguyen , Chansoo Choi , Wesley E. Bolch , Yeon Soo Yeom

{"title":"Tetrahedral mesh Visible Monkey phantom for radiation dosimetry research","authors":"Bangho Shin , Thang Tat Nguyen , Chansoo Choi , Wesley E. Bolch , Yeon Soo Yeom","doi":"10.1016/j.net.2025.103903","DOIUrl":"10.1016/j.net.2025.103903","url":null,"abstract":"<div><div>Although the Visible Monkey (VM) phantom in both voxel and polygon-mesh (PM) models was constructed based on anatomical color-sliced images of a rhesus monkey, the PM model advanced over the voxel model is not watertight, having various defects (e.g., holes, self-interaction, and overlaps), and therefore cannot be implemented in Monte Carlo (MC) codes for dose calculations. In the present study, the original PM monkey phantom was refined with anatomical improvements applied to the skeletal system and the walled organs. The model was then converted into a high-quality/fidelity tetrahedral mesh (TM) model which can be implemented in MC radiation transport codes. By performing the PHITS MC dose calculations coupled with the TM phantom, organ doses for photon external exposures (0.03–10 MeV) and specific absorbed fractions for electron internal exposures (0.01–10 MeV) were calculated and compared with those calculated from the original VM voxel model. For external exposures, the two phantoms showed similar organ doses (differences <25 %). On the other hand, for internal exposures, significant differences (differences up to a factor of 42) were observed due to the geometrical (smooth organ surface) and anatomical (updated skeletal system and classification of wall and contents) improvements for the TM-type phantom.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103903"},"PeriodicalIF":2.6,"publicationDate":"2025-09-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145106413","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Structured light-based 3D reconstruction in the radiation environment based on multi-frame iterative filtering and image feature-based point cloud registration 基于多帧迭代滤波和图像特征点云配准的辐射环境下基于结构光的三维重建

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-04 DOI: 10.1016/j.net.2025.103870

Minglei Zhu , Dawei Gong , Yuyang Zhao , Jiaoyuan Chen , Shijie Song

{"title":"Structured light-based 3D reconstruction in the radiation environment based on multi-frame iterative filtering and image feature-based point cloud registration","authors":"Minglei Zhu , Dawei Gong , Yuyang Zhao , Jiaoyuan Chen , Shijie Song","doi":"10.1016/j.net.2025.103870","DOIUrl":"10.1016/j.net.2025.103870","url":null,"abstract":"<div><div>In this paper, a novel 3D reconstruction method is proposed for radiation environments based on structured light technology. Firstly, throughout the principles of structured light-based 3D reconstruction, we see that the primary sources of error in radiation environments are the impacts of radiation noise and point-cloud registration errors. Then, considering the random nature of radiation noise, this paper proposes a multiframe iterative image-filtering algorithm that effectively and quickly removes radiation noise while preserving the phase information of the structured light. Additionally, a point-cloud initial registration method based on image features is introduced, which reduces the time required for initial matching and ensures accuracy. 3D reconstruction experiments were conducted at radiation dose rates of 60 Gy/h and 100 Gy/h. The results demonstrate that the proposed method maintains high modeling accuracy even in high-radiation environments, validating the reliability of the approach.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103870"},"PeriodicalIF":2.6,"publicationDate":"2025-09-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145027215","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Modeling and simulation of neutron-gamma density logging: Impact of mudcake thickness and barite content on measurement accuracy 中子-伽马密度测井建模与模拟：泥饼厚度和重晶石含量对测量精度的影响

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-09-04 DOI: 10.1016/j.net.2025.103883

Abolfazl Rafizade, Seyed Abolfazl Hosseini

{"title":"Modeling and simulation of neutron-gamma density logging: Impact of mudcake thickness and barite content on measurement accuracy","authors":"Abolfazl Rafizade, Seyed Abolfazl Hosseini","doi":"10.1016/j.net.2025.103883","DOIUrl":"10.1016/j.net.2025.103883","url":null,"abstract":"<div><div>This study investigates the influence of mudcake thickness and barite weight fraction on Neutron-Gamma Density (NGD) logging measurements, applying both NGD-FC and NGD-TC methods to simulate the interactions of fast neutrons and gamma rays in a wellbore environment. Initially, based on fast neutron and gamma diffusion theory and incorporating the build-up factor, a mathematical model of the well logging tool was constructed. To validate this model and enable more detailed analysis, simulations were conducted using the MCNP code, which provided the response of the tool under varying conditions. Simulated responses were then compared with theoretical predictions to ensure model accuracy.</div><div>The research examines mudcake conditions with thicknesses ranging from 3 to 12 mm and barite weight fractions of 10 %–30 %, highlighting that NGD-TC is particularly sensitive to mudcake thickness, as evidenced by a Max Error increasing from 22.36 % to 44.07 %. Conversely, NGD-FC maintains lower and more stable errors (15.91–19.58) under similar conditions, though it shows higher sensitivity to barite content due to fast neutron scattering influences.</div><div>Overall, this study emphasizes the importance of selecting the appropriate NGD method to ensure reliable measurements in complex wellbore environments. By fine-tuning calibration coefficients and understanding the interaction mechanisms that influence neutron and gamma flux, the research enhances the accuracy of NGD logging, thereby supporting improved decision-making in resource extraction and subsurface evaluations.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103883"},"PeriodicalIF":2.6,"publicationDate":"2025-09-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144989010","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0