Nuclear Engineering and Technology最新文献_第6页

Simulation and RTA-driven assessment of SMR deployment and concrete waste recycling at retired Kori-1 NPP 退役的高丽1号核电站SMR部署和混凝土废物回收的模拟和rta驱动评估

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-29 DOI: 10.1016/j.net.2025.103889

Eui-Taek Lee , Chang-Lak Kim

{"title":"Simulation and RTA-driven assessment of SMR deployment and concrete waste recycling at retired Kori-1 NPP","authors":"Eui-Taek Lee , Chang-Lak Kim","doi":"10.1016/j.net.2025.103889","DOIUrl":"10.1016/j.net.2025.103889","url":null,"abstract":"<div><div>The repurposing of retired Kori-1 Nuclear Power Plant site for Small Modular Reactor (SMR) deployment presents unique challenges and opportunities in sustainable infrastructure reuse and waste management. This study integrates Reactor Technology Assessment (RTA), simulation-based analysis, and on-site concrete recycling methodologies to comprehensively evaluate feasibility from both a technology comparison and implementation planning perspective. The RTA was conducted for Korea's two representative SMRs, SMART and i-SMR, using a partially tailored framework aligned with certain site-specific conditions. Both SMRs showed competitive performance across key evaluation criteria. Simulation-based analyses utilized FlexSim software to model concrete recycling processes, focusing on logistics for large-scale material handling. The recycling system combined coarse and fine aggregate processing with fresh concrete production while identifying bottlenecks in critical processors. The results indicated manageable recycling timelines for both SMRs aligning well with the Kori-1 decommissioning schedule. Addressing bottlenecks was effective in enhancing system efficiency. The simulation analyses suggest that this approach can help identify project schedule challenges, resolve bottlenecks, and allocate resources effectively to ensure the project schedule by incorporating advanced on-site concrete recycling into SMR deployment scenarios. This study provides a robust framework for optimizing waste management and repurposing retired nuclear sites, advancing innovative strategies for nuclear infrastructure redevelopment.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103889"},"PeriodicalIF":2.6,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144933543","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

Ductile design of steel pipes for missile impact 导弹冲击钢管的延展性设计

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-29 DOI: 10.1016/j.net.2025.103890

Shen Wang

引用次数: 0

Computational analysis of propagation of geometrical uncertainties to tritium production in FNG WCLL experiment FNG WCLL实验中几何不确定性对氚产量影响的计算分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-29 DOI: 10.1016/j.net.2025.103812

Klemen Ambrožič , Gašper Žerovnik , Dieter Leichtle , Maurizio Angelone

{"title":"Computational analysis of propagation of geometrical uncertainties to tritium production in FNG WCLL experiment","authors":"Klemen Ambrožič , Gašper Žerovnik , Dieter Leichtle , Maurizio Angelone","doi":"10.1016/j.net.2025.103812","DOIUrl":"10.1016/j.net.2025.103812","url":null,"abstract":"<div><div>We present a computational sensitivity and uncertainty analysis of the effect of geometrical uncertainties on the measured reaction rates in the Water Cooled Lithium Lead experimental benchmark, which is a mock-up of a tritium breeding blanket for the future DEMO fusion facility. We used deterministic transport methods to determine the sensitivity of various parts of the geometry and Monte Carlo particle transport methods along with random sampling from geometrical uncertainties, to assess the expected uncertainty and sensitivity profiles, particularly to establish whether tritium self-sufficiency can be achieved within the uncertainty. We have established that most sensitive parts of the geometry are the source position and orientation, as well as the target detector pack position. We have established the uncertainty to be in the range of 8% to 25%, increasing with the distance from the source. We have also established the sensitivity to the displacement of the target detector pack to be roughly 5%mm<sup>-1</sup>, while the sensitivity to the perturbation of position of other detector packs and source position and orientation is generally below the 1%mm<sup>-1</sup>.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103812"},"PeriodicalIF":2.6,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145010929","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 radiation profiles for spent fuel verification using OFPS in wet storage pools 使用OFPS在湿储存池中验证乏燃料辐射剖面的建模和仿真

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-28 DOI: 10.1016/j.net.2025.103888

In Soo Kang , Juwan Kang , Seongyeon Lee , Yoon Soo Chung , Sung-Woo Kwak , Yong Hyun Chung

引用次数: 0

Conceptual design of dynamic emergency operating procedural system for NPPs: Integration of dynamic task management and safety monitoring 核电厂动态应急运行程序系统概念设计：动态任务管理与安全监测的融合

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-27 DOI: 10.1016/j.net.2025.103884

Jung Sung Kang, Seung Jun Lee

{"title":"Conceptual design of dynamic emergency operating procedural system for NPPs: Integration of dynamic task management and safety monitoring","authors":"Jung Sung Kang, Seung Jun Lee","doi":"10.1016/j.net.2025.103884","DOIUrl":"10.1016/j.net.2025.103884","url":null,"abstract":"<div><div>This study proposes a dynamic emergency operating procedural system to address the limitations of static, paper-based emergency operating procedures in nuclear power plants. Despite digital main control rooms, traditional procedures remain static and poorly suited to rapidly changing plant conditions. Operators must still search for relevant steps while ignoring those that do not apply, increasing workload and delaying decisions. The static format also hinders real-time tracking and verification, risking omission of safety-critical actions. To resolve these issues, this study developed the Emergency Guidance Intelligent System (EGIS), which provides real-time monitoring and required task blocks.</div><div>EGIS comprises three core functions: the Task Block Browser, which delivers only necessary tasks in real-time using a functional-hierarchical task grouping framework; the Critical Safety Function Score Evaluator, which evaluates critical safety functions using fuzzy logic; and the Plant Status Monitor, which visualizes system status and consequence through Multilevel Flow Modeling. EGIS was verified using the Compact Nuclear Simulator with a Loss of Coolant Accident scenario. The results demonstrated that EGIS reduced operation time compared to conventional procedures while effectively replacing the role of traditional paper-based procedures. EGIS is expected to enhance the safety and efficiency of emergency operating procedures in nuclear power plants.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103884"},"PeriodicalIF":2.6,"publicationDate":"2025-08-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145046315","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

Evolution of neutron transmutation doped germanium in research reactor HANARO 中子嬗变掺杂锗在HANARO研究堆中的演化

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-26 DOI: 10.1016/j.net.2025.103882

Jinyu Kim, Bo-Young Han, Gwang-Min Sun, Sung Hyo Lee, Seongpyo Hong

{"title":"Evolution of neutron transmutation doped germanium in research reactor HANARO","authors":"Jinyu Kim, Bo-Young Han, Gwang-Min Sun, Sung Hyo Lee, Seongpyo Hong","doi":"10.1016/j.net.2025.103882","DOIUrl":"10.1016/j.net.2025.103882","url":null,"abstract":"<div><div>Research on neutron transmutation-doped germanium (NTD-Ge) is underway in the High-flux Advanced Neutron Application Reactor (HANARO) with the aim of developing sensor materials for bolometers used in rare-event experiments such as neutrino-less double beta decay and dark matter searches. In the initial phase, disk-shaped germanium samples from a high-purity germanium (HPGe) crystal were irradiated at the HANARO neutron irradiation facility. The thermal responses and dose rates of the samples were monitored to assess their operational safety. Radioisotopes produced through neutron activation and their characteristic gamma-rays were identified using HPGe gamma-ray spectroscopy. To obtain the quantitative relationship between the neutron fluence and dopant incorporation, the doping concentration of the NTD-Ge samples was assessed through Hall effect measurements. The results showed that the mechanical and electrical integrity of the samples remained stable during irradiation. The gamma spectra of the activated samples were comprehensively analyzed. A doping concentration of approximately 10<sup>15</sup> cm<sup>−3</sup> was achieved at a neutron fluence of 10<sup>17</sup> n/cm<sup>2</sup>. This study explains the doping behavior and activation characteristics of NTD-Ge samples, thereby supporting the development of high-performance thermistors for low-temperature particle physics detectors.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103882"},"PeriodicalIF":2.6,"publicationDate":"2025-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144916629","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 key factors influencing public acceptance of nuclear facilities decommissioning projects 影响公众对核设施退役项目接受程度的关键因素研究

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-26 DOI: 10.1016/j.net.2025.103885

Zhao shuaiwei , Li jiyan , Guo lixiao , Zhang bingtao , Mao liang , Li zehua , Leng yangchun

{"title":"Research on key factors influencing public acceptance of nuclear facilities decommissioning projects","authors":"Zhao shuaiwei , Li jiyan , Guo lixiao , Zhang bingtao , Mao liang , Li zehua , Leng yangchun","doi":"10.1016/j.net.2025.103885","DOIUrl":"10.1016/j.net.2025.103885","url":null,"abstract":"<div><div>Public acceptance plays a crucial role in advancing nuclear facility decommissioning projects. Based on questionnaire survey data (n = 1001), this study evaluated public acceptance levels in a specific Chinese region and examines key influencing factors and their pathways. The results indicate that public acceptance in the surveyed region remains at a moderate level, with familiarity scoring the lowest. Both perceived benefits and perceived risks are also rated as moderate. Weighted factor analysis reveals that familiarity exerts a stronger influence on public acceptance than trust, perception risk, or perception benefit. Specifically, public acceptance is primarily shaped by three factors: personal relevance to the nuclear, cognitive understanding, and safety perceptions. This suggests that local residents base their decisions primarily on subjective perceptions, with particular emphasis on perceived risks associated with decommissioning. Furthermore, the study demonstrates that perceived risk has a significant negative impact on public acceptance, whereas perceived benefits show no statistically significant positive effect. Trust and familiarity not only directly enhance acceptance but also indirectly influence it by mediating perceived benefits and risks. In conclusion, efforts to improve public acceptance in this region should prioritize increasing public familiarity with nuclear decommissioning and implementing targeted communication strategies to mitigate excessive risk perception.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103885"},"PeriodicalIF":2.6,"publicationDate":"2025-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145011005","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

Public acceptance of spent nuclear fuel use for new energy in Japan 日本公众对使用乏核燃料作为新能源的接受程度

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-25 DOI: 10.1016/j.net.2025.103881

Yoon-Young Chun , Takeshi Fujiwara , Kyoko Ono

{"title":"Public acceptance of spent nuclear fuel use for new energy in Japan","authors":"Yoon-Young Chun , Takeshi Fujiwara , Kyoko Ono","doi":"10.1016/j.net.2025.103881","DOIUrl":"10.1016/j.net.2025.103881","url":null,"abstract":"<div><div>With the nations’ energy security under threat and prices rising, several countries are shifting back in their energy policy to nuclear energy. Leading the recent nuclear boom to dreams, not nightmares, will depend on how the waste issues are resolved. This study aims to understand and break down public acceptance, attitudes, and perceptions of new energy sourced from spent nuclear fuel in Japan. New energy sourced from spent nuclear fuel indicates a technology or application, such as nuclear batteries, that extracts and utilizes the remaining valuable energy from nuclear fuel already used. Based on a web survey of 1000 Japanese in 2022, we found no statistical difference in the absolute mean of public acceptance between new energy sourced from spent nuclear fuel and nuclear power. In addition, the simulation result predicts that acceptance will increase as assessed scientific knowledge on radioactive waste, radiation, and nuclear power-related information increases. Structural Equation Modeling showed that assessed scientific knowledge, trust in the government, and environmental awareness had significant effects on benefit and risk perceptions related to new energy, and both perceptions would directly impact new energy acceptance. The findings will provide insights into developing energy from or recycling technology for spent nuclear fuel.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"58 1","pages":"Article 103881"},"PeriodicalIF":2.6,"publicationDate":"2025-08-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144913999","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

Reliability modeling of field calibration data for pressure transmitters in nuclear power plants 核电站压力变送器现场标定数据的可靠性建模

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-25 DOI: 10.1016/j.net.2025.103878

Bingyue Liu , Shengwu Cai , Hua Su , Zhen Qiao , Can Wei , Xinwen Zhao , Jiahang Jiang , Meng Jiao , Feng Qin , Meiping He

引用次数: 0

Identification of low-count, low-resolution gamma spectral radionuclide using 2DCNN-BiLSTM neural network 利用2DCNN-BiLSTM神经网络识别低计数、低分辨率γ谱放射性核素

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-08-22 DOI: 10.1016/j.net.2025.103854

Shu-Xin Zeng , Rui Shi , Guang Yang , Xian-Guo Tuo , Xiong Zeng , Ya-Nan Shang , Zhou Wang , Heng Zhang

{"title":"Identification of low-count, low-resolution gamma spectral radionuclide using 2DCNN-BiLSTM neural network","authors":"Shu-Xin Zeng , Rui Shi , Guang Yang , Xian-Guo Tuo , Xiong Zeng , Ya-Nan Shang , Zhou Wang , Heng Zhang","doi":"10.1016/j.net.2025.103854","DOIUrl":"10.1016/j.net.2025.103854","url":null,"abstract":"<div><div>To address the challenges of feature extraction and low classification accuracy in low-count, low-resolution gamma spectra with emerging nuclide identification methods, we proposed a novel approach using a two-dimensional convolutional bidirectional long short-term memory neural network (2DCNN-BiLSTM). This method extracts spatial features from gamma spectrum gray images using two-dimensional convolution operations and analyzes temporal features with a bidirectional long short-term memory neural network, leveraging spatiotemporal dependencies for nuclide classification. In simulation experiments, we modeled a NaI(Tl) detector using Geant4 and simulated various types of gamma spectra. Results showed that the 2DCNN-BiLSTM model achieved an average identification accuracy of 96.58 %, surpassing the 95.70 %, 92.38 %, and 92.19 % accuracies of 2D-VGG16, 1D-CNN, and PCA-BPNN models, respectively. Additionally, 2DCNN-BiLSTM demonstrated superior performance in resolving overlapping peaks in multi-source gamma spectra, with parsing accuracies of 97.95 %, 96.38 %, and 93.17 %. The method also exhibited good generalization in low-count, background noise, and spectrum peak drift scenarios and showed usability on experimental data from a NaI(Tl) detector. These findings show that the proposed method can be applied to the task of nuclide identification in low-count, low-resolution gamma energy spectra obtained from short-term measurements, providing some insight into rapid nuclide identification.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 12","pages":"Article 103854"},"PeriodicalIF":2.6,"publicationDate":"2025-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144886897","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