Nuclear Engineering and Technology最新文献_第4页

Strippable coatings from polysaccharide-based gel for the removal of radioactive contamination from metal surfaces 可剥离的涂层，由多糖类凝胶制成，用于去除金属表面的放射性污染

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-27 DOI: 10.1016/j.net.2025.103722

Alberto A. Pujol Pozo , Fabiola Monroy-Guzmán , María de los Ángeles Ruiz Rivera , Diana R. Gómora-Herrera , Rafael Basurto Sánchez

{"title":"Strippable coatings from polysaccharide-based gel for the removal of radioactive contamination from metal surfaces","authors":"Alberto A. Pujol Pozo , Fabiola Monroy-Guzmán , María de los Ángeles Ruiz Rivera , Diana R. Gómora-Herrera , Rafael Basurto Sánchez","doi":"10.1016/j.net.2025.103722","DOIUrl":"10.1016/j.net.2025.103722","url":null,"abstract":"<div><div>This paper proposes the use of polysaccharide-based gels as decontamination agents for metal surfaces contaminated with radioactive material to eliminate radioactive contamination of facilities, reduce the radiation dose and reduce the volume of equipment and materials that need to be disposed of. To decontaminate metal surfaces contaminated with radionuclides, polysaccharide-based gels have been formulated that can form easily strippable coatings. Anionic polysaccharides (pectin, sodium alginate, gum Arabic, xanthan gum, Guar gum, etc.) were prepared under different conditions. Strippable Coating forming gels were selected and applied to different metal specimens (stainless steel, aluminum, Inconel and Zircaloy) previously contaminated with different radionuclides and their respective decontamination factors were determined. The gels with the best decontamination performance and the coatings formed were characterized. The pectin-based gels showed the best decontamination performance of radioactive cations deposited on metal surfaces. The decontamination process with polysaccharide-based gels is based on the retention of the contaminant by the formation of complexes between the radioactive cations and the free functional groups in the polysaccharide structure.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103722"},"PeriodicalIF":2.6,"publicationDate":"2025-05-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144338981","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

Theoretical prediction of electronic, mechanical, and thermodynamic properties of layered ternary compounds (UC)nM3C2 (M=Si or Al; n=1,2) and two-dimensional U2C 层状三元化合物（UC）nM3C2 （M=Si或Al）电子、力学和热力学性质的理论预测n=1,2)和二维U2C

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-26 DOI: 10.1016/j.net.2025.103719

Yaxian Shi , Chengzhen Miao , Yujuan Zhang , Jianhui Lan , Xuwen Zhao , Changchun Ge , Xinggang Li

{"title":"Theoretical prediction of electronic, mechanical, and thermodynamic properties of layered ternary compounds (UC)nM3C2 (M=Si or Al; n=1,2) and two-dimensional U2C","authors":"Yaxian Shi , Chengzhen Miao , Yujuan Zhang , Jianhui Lan , Xuwen Zhao , Changchun Ge , Xinggang Li","doi":"10.1016/j.net.2025.103719","DOIUrl":"10.1016/j.net.2025.103719","url":null,"abstract":"<div><div>Following the 2011 Fukushima Daiichi nuclear catastrophe, there has been a significant surge in interest towards innovative materials capable of enhancing the safety, performance, and efficiency of nuclear reactors. This study introduces a new class of layered ternary compounds, specifically (UC)<sub>n</sub>Si<sub>3</sub>C<sub>2</sub> (n = 1,2), and derived two-dimensional (2D) U<sub>2</sub>C, discovered through first-principles calculations. We predict the electronic, mechanical, and thermodynamic properties of these compounds within the PBE and PBE + <em>U</em> frameworks, with a comparative analysis of the (UC)<sub>n</sub>Al<sub>3</sub>C<sub>2</sub> (n = 1,2) series. Our findings reveal that the USi<sub>3</sub>C<sub>3</sub> and U<sub>2</sub>Si<sub>3</sub>C<sub>4</sub> compounds exhibit mechanical and dynamic stabilities, suggesting their potential for experimental synthesis under specific conditions. These compounds demonstrate superior mechanical and thermal properties as nuclear fuels, including higher elastic moduli and improved ductility compared to (UC)<sub>n</sub>Al<sub>3</sub>C<sub>2</sub> compounds. The mechanical and dynamical stabilities of 2D U<sub>2</sub>C are confirmed, and the calculated thermal conductivity and mechanical properties position it as a promising candidate for high-performance nuclear fuel applications. We anticipate that the present work will bolster future experimental endeavors and help explore the practical applications of these novel materials in future nuclear systems.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103719"},"PeriodicalIF":2.6,"publicationDate":"2025-05-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144177912","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

A simple accident management support tool based on source-term category using RNN-LSTM 基于RNN-LSTM的简单事故管理支持工具

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-24 DOI: 10.1016/j.net.2025.103716

Wonjun Choi , Sung Joong Kim

{"title":"A simple accident management support tool based on source-term category using RNN-LSTM","authors":"Wonjun Choi , Sung Joong Kim","doi":"10.1016/j.net.2025.103716","DOIUrl":"10.1016/j.net.2025.103716","url":null,"abstract":"<div><div>Severe accidents in nuclear power plants can cause significant damage to both human life and property. Due to the inherent complexity and uncertainty of severe accident progression, managing such accidents is challenging for operators. Consequently, computational aids are crucial in supporting their decision-making processes. Among these computational tools, data-driven approaches hold considerable promise by suggesting expected plant states. However, these methods often require large datasets to cover a wide range of scenarios. In this study, a simplified data-driven accident management support tool was proposed using Recurrent Neural Networks with Long Short-Term Memory (RNN-LSTM). The model predicts the consequences of severe accidents in terms of source-term categories based on nuclear power plant monitoring parameters. To assess the effectiveness and robustness of the suggested model, sensitivity analyses were conducted focusing on sensor failure, sampling intervals, duration, and noise levels. Results showed that the model's performance degraded with sensor failures, data scarcity, and increased noise but maintained meaningful performance overall. A notable observation was that denser time intervals generally enhance model performance; however, overly dense intervals can make the system vulnerable to errors. Thus, an optimal sampling interval for monitoring parameters is crucial to achieve the best performance.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103716"},"PeriodicalIF":2.6,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184977","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

The control system for SHINE SHINE的控制系统

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-24 DOI: 10.1016/j.net.2025.103714

Huihui Lv, Guanghua Chen, Jianguo Ding, Jianfeng Chen, Chunlei Yu, Pengxiang Yu, Haifeng Miao, Qingru Mi, Huan Zhao, Dangping Bai, Heyun Wang, Ming Li, Qingwen Xiao, Xiaomin Liu, Rui Wang, Yaming Gao, Yingbing Yan

{"title":"The control system for SHINE","authors":"Huihui Lv, Guanghua Chen, Jianguo Ding, Jianfeng Chen, Chunlei Yu, Pengxiang Yu, Haifeng Miao, Qingru Mi, Huan Zhao, Dangping Bai, Heyun Wang, Ming Li, Qingwen Xiao, Xiaomin Liu, Rui Wang, Yaming Gao, Yingbing Yan","doi":"10.1016/j.net.2025.103714","DOIUrl":"10.1016/j.net.2025.103714","url":null,"abstract":"<div><div>As the first hard X-ray free electron laser facility in China, Shanghai HIgh repetition rate XFEL aNd Extreme light facility (SHINE) has been under construction since 2018. The control system is responsible for the facility-wide device control, data acquisition, machine protection, timing, high-level applications, as well as network and computing platform. The whole facility is constructed 29m underground and has a total length of 3.11 km. The large installation geography and the excellent performance parameters necessitate the control system solving a wide breadth of technical challenges. The control system has been designed and implemented using the framework of the Experimental Physics and Industrial Control System (EPICS). Our own software and scripts for high-level application makes this framework easy to use and deploy. The Machine Protection System (MPS) based on Field Programmable Gate Array (FPGA) provides a global interlock system designed to monitor the accelerator operating conditions. The timing system based on White Rabbit provides precise clock pulse signals and hardware bunch numbers. This paper presents details of the development of the control system for SHINE, as well as some valuable monitoring and maintenance applications, technologies and methods.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103714"},"PeriodicalIF":2.6,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184979","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

Analysis of enhanced heat transfer characteristics in a bionic fish scale tube for turbulent flow 仿生鱼鳞管紊流强化传热特性分析

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-24 DOI: 10.1016/j.net.2025.103715

Xiaoya Liu , Xinwen Zhao , Lingke Ran , Hongguang Xiao , Yongfa Zhang , Yinxing Zhang , Yiqiang Liu , Nan Zhang , Ming Ding

{"title":"Analysis of enhanced heat transfer characteristics in a bionic fish scale tube for turbulent flow","authors":"Xiaoya Liu , Xinwen Zhao , Lingke Ran , Hongguang Xiao , Yongfa Zhang , Yinxing Zhang , Yiqiang Liu , Nan Zhang , Ming Ding","doi":"10.1016/j.net.2025.103715","DOIUrl":"10.1016/j.net.2025.103715","url":null,"abstract":"<div><div>The miniaturization and compactness of heat exchangers are of great significance to marine power plant. Combining bionic technologies and passive technologies, a bionic fish scale tube (BFST) is proposed to enhance convective heat transfer coefficient of tube. The numerical simulation on flow and heat transfer characteristics of BFST is deliberated in turbulent flow region. Effects of various vertical heights, horizontal gaps, circumferential numbers and distance of adjacent fish scales have been investigated. Furthermore, the entropy generation and field synergy are also analyzed and correlations for Nusselt number and friction factor are obtained. These results suggest that local velocity increment, vortexes formed at the behind of fish scales and swirling of the flow are three main factors to improve the tube inner convective heat transfer coefficient. The Nusselt number is also significantly increased with the increment of vertical height, horizontal gap and circumferential numbers. Moreover, the maximum value of performance evaluation criteria at the ranges of studied can be up to 1.352 for BFST. <em>S</em>/<em>S</em><sub>0</sub> of BFST are aggrandize with the Reynolds number increasing, which vary from 1.66 to 16.75. At last, the Nusselt number and friction factor correlations can predict the numerical data within R-square of 0.9910 and 0.9712 respectively.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 11","pages":"Article 103715"},"PeriodicalIF":2.6,"publicationDate":"2025-05-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144297022","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

Mechanically-milled YBaCo4O7+δ for oxygen sorbents: insights into oxygen contamination and surface structure 机械磨YBaCo4O7+δ氧吸附剂：洞察氧污染和表面结构

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-23 DOI: 10.1016/j.net.2025.103713

Byoungjin So, Seok-Min Hong, Chang Hwa Lee

引用次数: 0

A novel directional radiation monitoring system for real-time nuclide identification and source localization using DOI method 一种基于DOI方法的实时核素识别与源定位定向辐射监测系统

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-20 DOI: 10.1016/j.net.2025.103710

Yoon Soo Chung, Min Kyu Baek, Seongyeon Lee, Juwan Kang, Yong Hyun Chung

{"title":"A novel directional radiation monitoring system for real-time nuclide identification and source localization using DOI method","authors":"Yoon Soo Chung, Min Kyu Baek, Seongyeon Lee, Juwan Kang, Yong Hyun Chung","doi":"10.1016/j.net.2025.103710","DOIUrl":"10.1016/j.net.2025.103710","url":null,"abstract":"<div><div>To effectively respond to accidents at radiation-utilizing facilities and nuclear power plants, radiation monitoring and emergency response systems must be further strengthened. This requires a monitoring system capable of rapidly providing nuclide identification and source direction information. In this study, the principles and feasibility of a directional radiation monitoring system utilizing a single crystal and depth-of-interaction (DOI) method were verified. The system consists of a cylindrical crystal, photomultiplier tubes attached at both ends, and a collimator with eight independent slots. Each slot is designed in a different direction based on height, allowing radiation to interact at a specific height depending on the source direction. The DOI method is used to measure the interaction height, enabling the acquisition of directional information. Monte Carlo simulations, including optical and radiation transport, were conducted to verify the system's principle and feasibility. The results demonstrated that the system achieved a DOI resolution of 6.11 mm, an angular resolution of 60°, and a sensitivity of 26.65 cps/MBq at 1 m. The feasibility of the system was further verified by evaluating its ability to provide real-time nuclide identification and directional information for multiple sources with a 360-degree field of view, using simulations of two scenarios.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103710"},"PeriodicalIF":2.6,"publicationDate":"2025-05-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144189397","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

Path planning in radioactive environment of nuclear facilities based on modified A-star algorithm and search neighborhood optimization 基于改进a星算法和搜索邻域优化的核设施放射性环境路径规划

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-20 DOI: 10.1016/j.net.2025.103711

Biao Zhang , Xingfu Cai , Guoqiang Li , Xiaomeng Li , Minjun Peng , Haowei Wang

{"title":"Path planning in radioactive environment of nuclear facilities based on modified A-star algorithm and search neighborhood optimization","authors":"Biao Zhang , Xingfu Cai , Guoqiang Li , Xiaomeng Li , Minjun Peng , Haowei Wang","doi":"10.1016/j.net.2025.103711","DOIUrl":"10.1016/j.net.2025.103711","url":null,"abstract":"<div><div>An improved A-star algorithm is proposed in this paper for path planning in the radioactive environment of nuclear facilities. The heuristic function is defined as the estimated dose from the current node to the end point. A dynamic weighting scheme is introduced to balance the actual cost and the estimated cost, and it is applied to the actual cost function. This modification improves the efficiency of path search while maintaining a low cumulative dose for staff. The effect of the number of search neighborhoods (3–8) on path planning is then studied. The results show that the cumulative dose of the modified algorithm is comparable to the traditional A-star algorithm, but the average execution point is reduced by 53.06 % and the computation time is shortened by 24.23 %. Compared with the Probabilistic Roadmap Method (PRM), PRM has the shortest computation time due to its random sampling characteristics, but the cumulative dose and path length are higher than the two A-star algorithms. For models of varying complexity, optimizing the number of search neighborhoods further enhances search efficiency without affecting path planning results. This improvement significantly enhances the application efficiency of the A-star algorithm in the radioactive environment of nuclear facilities, providing a more effective solution for path planning in complex radioactive environments.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103711"},"PeriodicalIF":2.6,"publicationDate":"2025-05-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144184975","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

Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design 可溶无硼小堆全堆芯燃料分析：颗粒包层相互作用问题及通过装载模式设计提高燃料安全性

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-20 DOI: 10.1016/j.net.2025.103709

Chansoo Lee , Kyuseok Shim , Hyuntaek Rho , Jooil Yoon , Heejeong Jeong , Youho Lee

{"title":"Full-core fuel analysis of a soluble boron-free SMR: Pellet-cladding interaction issue and enhancing fuel safety through loading pattern design","authors":"Chansoo Lee , Kyuseok Shim , Hyuntaek Rho , Jooil Yoon , Heejeong Jeong , Youho Lee","doi":"10.1016/j.net.2025.103709","DOIUrl":"10.1016/j.net.2025.103709","url":null,"abstract":"<div><div>The full-core fuel behavior of the Soluble Boron-Free (SBF) Small Modular Reactor (SMR) was analyzed and compared with conventional pressurized water reactors (PWRs) and Soluble Boron-Using (SBU) SMRs to evaluate unique pellet-cladding interaction (PCI) risks. Unlike PWRs and SBU SMRs, SBF SMRs rely on control rods for reactivity control, leading to localized power increases during late-cycle withdrawal. This significantly elevates cladding hoop stress, particularly in fuel rods near control rods, increasing PCI risks even at moderate burnups. The maximum local cladding hoop stress due to PCI in SBF SMRs exceeds that of conventional PWRs, posing new fuel safety and qualification challenges despite being SMR fuel characteristics, such as lower power density, and extended relative fuel plenum length. Comparisons with boiling water reactors (BWRs) highlight the heightened PCI risk in SBF SMRs due to differences in core design and control strategies. A fuel loading strategy that positions high-burnup rods away from lead control rod banks effectively reduces peak cladding stress. However, PCI remains a concern, particularly for long-cycle cores with LEU+ fuel. These findings emphasize the need to integrate fuel performance considerations early in SBF SMR development to ensure safety, regulatory compliance, and adaptability for future LEU+ fuels.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103709"},"PeriodicalIF":2.6,"publicationDate":"2025-05-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144195944","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

Neutronics benchmark calculations of the NuScale-like SMR core using SCALE/KENO-VI 基于SCALE/KENO-VI的类似于nuscale的SMR核的中子基准计算

IF 2.6 3区工程技术

Nuclear Engineering and Technology Pub Date : 2025-05-19 DOI: 10.1016/j.net.2025.103712

Thi Dung Nguyen , Duy Long Ta , Thanh Mai Vu , Shinichi Namizono , Huu Thuan Mai , Huu Quyet Nguyen , Nhu Viet Ha Pham

{"title":"Neutronics benchmark calculations of the NuScale-like SMR core using SCALE/KENO-VI","authors":"Thi Dung Nguyen , Duy Long Ta , Thanh Mai Vu , Shinichi Namizono , Huu Thuan Mai , Huu Quyet Nguyen , Nhu Viet Ha Pham","doi":"10.1016/j.net.2025.103712","DOIUrl":"10.1016/j.net.2025.103712","url":null,"abstract":"<div><div>A neutronics benchmark for a NuScale-like core has been proposed under the Euratom McSAFER project using Monte Carlo solutions from Serpent 2 (v2.2) and the nuclear data library ENDF/B-VII.1. The benchmark aims to facilitate code-to-code comparisons in neutronics calculations for light-water cooled small modular reactors (LW-SMRs), driven by growing global interest in their deployment due to advanced technology, licensing progress, and commercial viability. This highlights the need for high-fidelity analyses to assess the design, safety, and operational features of these reactors. This study focuses on performing neutronics benchmarking calculations of the proposed NuScale-like core using SCALE/KENO-VI, evaluating k-eff, control rod worths, and power distributions with ENDF/B-VII.1 continuous energy (CE) and 252-group libraries. The impact of ENDF/B-VII.0, VII.1, and VIII.0 libraries on neutronics results was also assessed using Serpent 2 (v2.1.31). Results show that SCALE/KENO-VI with ENDF/B-VII.1 CE and 252-group libraries aligns well with the reference, with discrepancies within 44 pcm for reactivity prediction and generally less than 2 % for power distribution, except for the all-rods-in scenario using the 252-group library, which shows a reactivity deviation of 139 pcm. In addition, Serpent 2 with ENDF/B-VIII.0 produced notable differences in the k-eff values compared to ENDF/B-VII.0 and VII.1. Consequently, this work provides valuable and significant neutronics reference data for the proposed NuScale-like core model. Moreover, the NuScale-like core model developed here using SCALE/KENO-VI can serve as a basis for future neutronics and core performance analyses for NuScale-like reactors and other similar LW-SMR designs.</div></div>","PeriodicalId":19272,"journal":{"name":"Nuclear Engineering and Technology","volume":"57 10","pages":"Article 103712"},"PeriodicalIF":2.6,"publicationDate":"2025-05-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144170598","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