Nuclear Engineering and Technology最新文献_第5页

Verification and Validation of CFD analysis for 1/7th scale model of APR1400 for CVAP

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.08.061

Giwon La , Kunwoo Yi , Doyoung Ko , Kyuhyung Kim

引用次数: 0

Algorithm for estimating Cr coating thickness for accident tolerant fuel cladding using a pancake ECT sensor

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.09.019

Jeong Won Park , Daegyun Ko , Hun Jang , Hoyoung Kim , Jaebeom Lee , Wonjae Choi

{"title":"Algorithm for estimating Cr coating thickness for accident tolerant fuel cladding using a pancake ECT sensor","authors":"Jeong Won Park , Daegyun Ko , Hun Jang , Hoyoung Kim , Jaebeom Lee , Wonjae Choi","doi":"10.1016/j.net.2024.09.019","DOIUrl":"10.1016/j.net.2024.09.019","url":null,"abstract":"<div><div>The accident-tolerance of nuclear fuel rods has been a topic of continued interest since the Fukushima disaster. A notable advance in this area involves the development of Cr-coated nuclear fuel rods. This coating confers several benefits compared with conventional HANA-6 fuel rods, including superior corrosion resistance, enhanced durability, and increased thermal efficiency. The efficacy of the Cr coating is contingent upon maintaining an optimal thickness, which necessitates precise measurement technologies. In this context, the present study employs the eddy current testing (ECT) technique to ascertain the thickness of the Cr coating on nuclear fuel rods. A pancake ECT sensor was designed and fabricated to conduct thickness measurements in the confined spaces of multiple fuel assemblies. Nuclear fuel rods of various thicknesses were manufactured, and the thicknesses of the nuclear fuel rods were measured using a destructive method to provide the standard thickness for ECT measurement. Selection of the optimal frequency was driven by analysis of the measurement signals, and a dedicated algorithm for thickness measurement was subsequently formulated based on these findings. The application of this algorithm to predict the coating thickness in 10 out of 30 specimens demonstrated high accuracy without prior knowledge of conductivity of the materials.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103216"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099917","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Safeguards-related event detection in surveillance video using semi-supervised learning approach

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.09.009

Se-Hwan Park, Byung-Hee Won, Seong-Kyu Ahn

{"title":"Safeguards-related event detection in surveillance video using semi-supervised learning approach","authors":"Se-Hwan Park, Byung-Hee Won, Seong-Kyu Ahn","doi":"10.1016/j.net.2024.09.009","DOIUrl":"10.1016/j.net.2024.09.009","url":null,"abstract":"<div><div>We develop a deep learning model employing a semi-supervised learning approach, which can detect automatically safeguards-related events in nuclear facility from surveillance video. Our model is designed after a comprehensive analysis of the trends in artificial intelligence-based models to identify abnormal events in video. Our model incorporates a reconstruction module and a prediction module independently. The reconstruction module is trained to generate video frames within a sliding window, while the prediction module is trained to predict future motion feature based on the motion features within the video frames in a sliding window. Each module utilizes an autoencoder with a memory module positioned between an encoder and an decoder of the autoencoder. We evaluate the model's performance using a benchmark dataset and a self-produced dataset obtained from facility related to pyroprocessing. Our model's performanace is comparable to or superior to that of the prevous models from the benchmark dataset analysis, and all the abnormal events can be detected without false positive error from the self-produced dataset analysis.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103206"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099926","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Radon an indoor risk: In the Urban Devarakonda, Telangana state, India

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.09.005

M. Srinivas Reddy , G. Suman , K. Vinay Kumar Reddy , M. Sreenath Reddy , Ch Gopal Reddy , P. Yadagiri Reddy

{"title":"Radon an indoor risk: In the Urban Devarakonda, Telangana state, India","authors":"M. Srinivas Reddy , G. Suman , K. Vinay Kumar Reddy , M. Sreenath Reddy , Ch Gopal Reddy , P. Yadagiri Reddy","doi":"10.1016/j.net.2024.09.005","DOIUrl":"10.1016/j.net.2024.09.005","url":null,"abstract":"<div><div>Natural background radiation risk owing to radon and its progeny at indoors to the general public is a significant issue. The concern about indoor radon risk has been increasing at national and international level since its role to the overall dose is well known. The current study aims to assess the <sup>222</sup>Rn and its progeny in different type of indoors with a passive (SSNTD) and active technique (RAD-7). The area of investigation (urban Devarakonda), is located near the proposed uranium mineralization area. The estimated radon levels in the indoors were ranging from 20 to 437 Bq. m<sup>−3</sup> and with a geometric mean of 66 Bq.m<sup>−3</sup>. The estimated EERC values are ranging from 22 to 82 Bq.m<sup>−3</sup> and these are higher than the range limit prescribed by ICRP. The computed average EF value in the present study (0.58) is relatively higher than the world average value of 0.4. An effort has been made to comprehend the radon distribution among the representative locations. Annual effective inhalation dose was also estimated using the occupancy factor 0.8 and it is found in the range of 0.52–11.00 m Sv y<sup>−1</sup> with geometric mean of 2.20 mSv.y<sup>−1</sup>. The diurnal variation of <sup>222</sup>Rn levels was studied using RAD-7 in a dwelling and seasonal variation of radon levels was also to be discussed in this paper.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103202"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099954","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

The design and implementation of automated maintenance system for the first-wall based on dual-arm manipulator 基于双臂机械手的第一道墙自动维护系统的设计与实施

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.08.039

Ke Wu , Jun Zhang , Yong Cheng , Qingxi Yang , Hongtao Pan , Tao Wang , Aiming Liu , Hao Han

引用次数: 0

A model for operational risk of industrial facilities including ageing/test degradation effects and maintenance effectiveness 工业设施运行风险模型，包括老化/测试退化效应和维护效果

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.08.065

S.F. Quintão Ribeiro , J.J. Rivero

{"title":"A model for operational risk of industrial facilities including ageing/test degradation effects and maintenance effectiveness","authors":"S.F. Quintão Ribeiro , J.J. Rivero","doi":"10.1016/j.net.2024.08.065","DOIUrl":"10.1016/j.net.2024.08.065","url":null,"abstract":"<div><div>The paper presents a model for operational risk of industrial facilities with applications to nuclear power plants and uranium mining. The traditional models update the risk profile for specific operational conditions setting to one the failure probability of components which are known to be unavailable by failure or maintenance, while constant mean unavailability values from the original Probabilistic Safety Analysis (PSA) are kept for the rest. The proposed methodology considers the time dependency of standby failure probabilities through instantaneous unavailability models, depending on the specific standby time for each component at the given moment, instead of using the same constant values. It also incorporates ageing, testing degradation effects and maintenance effectiveness, not explicitly considered in traditional models, as well as the instantaneous reevaluation of common cause failure probabilities. The results show significant risk underestimations when components specific standby times, ageing, testing degradation effects and maintenance effectiveness are not considered.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103196"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207209","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Numerical investigation of welding deformation diminution for double shell structure using the layered inherent strain 利用分层固有应变的双壳结构焊接变形减小数值研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.09.011

Cheng Li , Hua Zhai , Lianwei Zhu , Zhihong Liu , Jianguo Ma , Xiaofeng Zhu , Qiong Liu

{"title":"Numerical investigation of welding deformation diminution for double shell structure using the layered inherent strain","authors":"Cheng Li , Hua Zhai , Lianwei Zhu , Zhihong Liu , Jianguo Ma , Xiaofeng Zhu , Qiong Liu","doi":"10.1016/j.net.2024.09.011","DOIUrl":"10.1016/j.net.2024.09.011","url":null,"abstract":"<div><div>Cyclotron is a key scientific tool and indispensable research platform for conducting cutting-edge research in nuclear equipment development as well as innovative applications of nuclear technology. The shell component has a double-layer thick-walled structure with intricate ribs and high-density, full-penetration welded joints. The mitigation of welding deformation is of profound significance to the performance of the cyclotron. The thick plate joint has many welding layers which will be divided into several steps to complete the backing, filler, and cap welding. The equivalent transverse and longitudinal plastic strains of different layers were extracted by the thermo-elastic-plastic method. The welding deformation generated by each layer of weld can be predicted by using the equivalent plastic strain, and the total distortion can be accumulated layer by layer. Numerical simulation and experimental studies were conducted on the welding deformation of the double shell specimen, and the welding sequence and design of the welding fixture were discussed in detail. The digital photogrammetry system was used to monitor the deformation state of the welded parts in real-time. The measured deformation was compared with the simulation results. Ultimately, the deformation of the specimen is controlled at 2.64 mm. The proposed method can flexibly evaluate the impact of each welding layer on welding deformation for multiple welds, which can provide technical guidance for cyclotron engineering manufacturing.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103208"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142207207","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Quantum mechanical study of the influence of noble metals on the process of reduction of uranium oxides

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.09.020

A.S. Vorob'ev, A.Y. Galashev, Yu P. Zaikov

引用次数: 0

Evaluating the Kerma coefficients relevant to various water-equivalent materials at different photon energies

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.08.043

Zahra Abdi, Hamid Reza Baghani, Reza Shamsabadi

{"title":"Evaluating the Kerma coefficients relevant to various water-equivalent materials at different photon energies","authors":"Zahra Abdi, Hamid Reza Baghani, Reza Shamsabadi","doi":"10.1016/j.net.2024.08.043","DOIUrl":"10.1016/j.net.2024.08.043","url":null,"abstract":"<div><div>To investigate the water equivalency of some solid phantoms, relevant Kerma coefficients were determined through both Monte Carlo (MC) simulation and analytical approaches over a wide range of photon energies ranging from 1 keV to 20 MeV.</div><div>MCNPX MC Code was employed to simulate the Kerma coefficients for A-150, PMMA, Polystyrene, Solid Water (RMI 457), Solid Phantom (RW3), Virtual water, Solid Water (WT1), and Water Equivalent (Wte) solid phantoms. Kerma coefficients were also theoretically calculated using the mass energy absorption coefficients at different photon energies ranging from 1 keV to 20 MeV. Obtained Kerma coefficients for considered solid phantoms were also compared with those of water to find which material shows the best water-equivalency.</div><div>Calculated Kerma coefficients by MC simulation were in a good agreement with those calculated via an analytical method which no statistically significant differences were observed among simulated and analytically calculated Kerma coefficients (p-value>0.05). Solid water (RMI 457) showed the best water-equivalency among studied plastic phantoms for radiology and radiotherapy quality assurance purposes. From the results, the Kerma coefficients for solid phantoms are highly dependent on photon energy.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103174"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099927","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on transient hydraulic characteristics of the whole process of reactor coolant pump under shaft stuck accident

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-02-01 DOI: 10.1016/j.net.2024.09.021

Qichao Xia , Xiuli Wang , Yuanyuan Zhao , Rongsheng Zhu , Zhichen Wang , Shenpeng Yang , Wei Xu

{"title":"Research on transient hydraulic characteristics of the whole process of reactor coolant pump under shaft stuck accident","authors":"Qichao Xia , Xiuli Wang , Yuanyuan Zhao , Rongsheng Zhu , Zhichen Wang , Shenpeng Yang , Wei Xu","doi":"10.1016/j.net.2024.09.021","DOIUrl":"10.1016/j.net.2024.09.021","url":null,"abstract":"<div><div>In order to explore the transient hydraulic characteristics of reactor coolant pump (RCP) under shaft stuck accident (SSA), it takes CAP1400 RCP as the research object. The applicability of three turbulence simulation methods and the different accident conditions are analyzed by numerical simulations and experiments. Combined with the appropriate turbulence simulation method and significant SSA conditions, the transient hydraulic characteristics of the whole process are studied. The results show that the numerical simulations align well with experiments during the SSA transition process, with deviations mainly concentrate in the early-middle stage. Large Eddy Simulation (LES) performs well in terms of external characteristics, with the maximum deviations below 10 %. The shorter stuck shaft transition time implies more severe accident damage, with greater the parameters decrease, more drastic specific pressure energy change. Under the kz1 and kz2 conditions, the head and torque decrease first fast and then slow down, while they decrease slowly in the early stage, then decrease sharply, reaching −92.2 % and −75.6 % of the rated value when the impeller stops under the kz3 condition. In the whole process, the head and torque decrease first and then increase, while the vorticity and specific pressure energy increase first and then decrease, all of which change dramatically in the transition process and stabilize in the subsequent response stage. The results provide theoretical and technical guidance for the optimization and improvement, enhancing the capability of accident prevention and mitigation.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 2","pages":"Article 103218"},"PeriodicalIF":2.6,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143099948","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0