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Toward Robotic Nuclear Decommissioning: Deep Learning-Based Object Classification and Pose Estimation from Partial-View Scans 实现机器人核退役：基于深度学习的物体分类和局部视角扫描的姿态估计
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-05-08 DOI: 10.1080/00295639.2024.2340171
Sungmoon Joo
{"title":"Toward Robotic Nuclear Decommissioning: Deep Learning-Based Object Classification and Pose Estimation from Partial-View Scans","authors":"Sungmoon Joo","doi":"10.1080/00295639.2024.2340171","DOIUrl":"https://doi.org/10.1080/00295639.2024.2340171","url":null,"abstract":"This study introduces a novel framework for the robotic decommissioning of nuclear facilities, that focuses on object classification and six degrees of freedom pose estimation from partial-view thr...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"96 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-05-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140933571","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
Mitigating Spatial Error in the Iterative Quasi–Monte Carlo (iQMC) Method for Neutron Transport Simulations with Linear Discontinuous Source Tilting and Effective Scattering and Fission Rate Tallies 利用线性不连续源倾斜和有效散射及裂变率总计法减轻中子输运模拟迭代准蒙特卡罗（iQMC）方法中的空间误差
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-05-06 DOI: 10.1080/00295639.2024.2332007
Samuel Pasmann, Ilham Variansyah, C. T. Kelley, Ryan G. McClarren
{"title":"Mitigating Spatial Error in the Iterative Quasi–Monte Carlo (iQMC) Method for Neutron Transport Simulations with Linear Discontinuous Source Tilting and Effective Scattering and Fission Rate Tallies","authors":"Samuel Pasmann, Ilham Variansyah, C. T. Kelley, Ryan G. McClarren","doi":"10.1080/00295639.2024.2332007","DOIUrl":"https://doi.org/10.1080/00295639.2024.2332007","url":null,"abstract":"The iterative Quasi–Monte Carlo (iQMC) method is a recently proposed method for neutron transport simulations. iQMC can be viewed as a hybrid between deterministic iterative techniques, Monte Carlo...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"24 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-05-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140881763","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
Numerical Investigation of Air-Steam Condensation in a Vertically Enhanced Tube with Concave and Convex Surfaces 具有凹面和凸面的垂直增强管中空气-蒸汽冷凝的数值研究
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-05-06 DOI: 10.1080/00295639.2024.2340145
Jiyu Zheng, Liang Zhang, Zheng Liang, Bojia Wei, Zhongchao Yan, Xin Chen
{"title":"Numerical Investigation of Air-Steam Condensation in a Vertically Enhanced Tube with Concave and Convex Surfaces","authors":"Jiyu Zheng, Liang Zhang, Zheng Liang, Bojia Wei, Zhongchao Yan, Xin Chen","doi":"10.1080/00295639.2024.2340145","DOIUrl":"https://doi.org/10.1080/00295639.2024.2340145","url":null,"abstract":"Condensation heat transfer enhancement technology is an important problem for heat exchangers. The air-steam condensation inside a vertically enhanced tube with concave and convex surfaces is analy...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"46 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-05-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140881766","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 of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations 在连续能量蒙特卡洛损耗模拟中开发耦合损耗扰动理论方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-05-01 DOI: 10.1080/00295639.2024.2332010
Benjamin R. Murphy, Christopher M. Perfetti
{"title":"Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations","authors":"Benjamin R. Murphy, Christopher M. Perfetti","doi":"10.1080/00295639.2024.2332010","DOIUrl":"https://doi.org/10.1080/00295639.2024.2332010","url":null,"abstract":"This work develops a depletion perturbation theory methodology coupled with generalized perturbation theory to produce fully coupled nuclide number density sensitivity coefficients for cross sectio...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"81 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140881748","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
Simulating Fuel Assembly Bowing: A Neutron-Diffusion Method Based on Arbitrary Quadrilateral Node and Conformal Mapping Technique 模拟燃料组件弯曲：基于任意四边形节点和共形映射技术的中子扩散方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-05-01 DOI: 10.1080/00295639.2024.2334988
Hongchun Wu, Lin Guo, Chenghui Wan
{"title":"Simulating Fuel Assembly Bowing: A Neutron-Diffusion Method Based on Arbitrary Quadrilateral Node and Conformal Mapping Technique","authors":"Hongchun Wu, Lin Guo, Chenghui Wan","doi":"10.1080/00295639.2024.2334988","DOIUrl":"https://doi.org/10.1080/00295639.2024.2334988","url":null,"abstract":"Fuel assembly bowing, widely observed in a pressurized water reactor (PWR), often results in an asymmetrical power distribution. This paper proposes a neutron-diffusion method that integrates the a...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"33 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140933225","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
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig 自然循环沸腾整体压水堆型 SMR 试验装置中工艺参数对流动振荡影响的数值研究
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-05-01 DOI: 10.1080/00295639.2024.2328967
Muhammad Ishaq, Muhammad Zaman, Muhammad Ilyas, Alam Nawaz Khan Wardag, Mansoor H. Inayat
{"title":"Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig","authors":"Muhammad Ishaq, Muhammad Zaman, Muhammad Ilyas, Alam Nawaz Khan Wardag, Mansoor H. Inayat","doi":"10.1080/00295639.2024.2328967","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328967","url":null,"abstract":"Innovative reactor designs like small modular reactors (SMRs) have the potential to operate in a natural circulation (NC) boiling mode, but this mode introduces flow oscillations that pose a risk t...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"16 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-05-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140881536","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
Uncertainty Benchmarks for Time-Dependent Transport Problems 时间相关传输问题的不确定性基准
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-26 DOI: 10.1080/00295639.2024.2333092
W. Bennett, R. G. McClarren
{"title":"Uncertainty Benchmarks for Time-Dependent Transport Problems","authors":"W. Bennett, R. G. McClarren","doi":"10.1080/00295639.2024.2333092","DOIUrl":"https://doi.org/10.1080/00295639.2024.2333092","url":null,"abstract":"Verification solutions for uncertainty quantification (UQ) are presented for time-dependent transport problems where , the scattering ratio, is uncertain. The method of polynomial chaos expansions ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"16 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140881735","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
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code 优化 APOLLO3® 确定性中子输运代码的加速轴向多项式特性法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-22 DOI: 10.1080/00295639.2024.2328962
Arthur Le Bars, Andrea Gammicchia, Simone Santandrea
{"title":"Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code","authors":"Arthur Le Bars, Andrea Gammicchia, Simone Santandrea","doi":"10.1080/00295639.2024.2328962","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328962","url":null,"abstract":"For some years now, the TDT (two- and three-dimensional transport) solver of the APOLLO3® deterministic neutron transport code has been able to perform lattice calculations on three-dimensional ext...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"50 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140637141","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
On the Possibility of Achieving Optimal Operating Modes of Hyperspeed Model Gas Centrifuges: 3D Numerical Simulation 超高速模型气体离心机实现最佳运行模式的可能性：三维数值模拟
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-22 DOI: 10.1080/00295639.2024.2332021
S. V. Bogovalov, I. V. Tronin, A. V. Vasilyev
{"title":"On the Possibility of Achieving Optimal Operating Modes of Hyperspeed Model Gas Centrifuges: 3D Numerical Simulation","authors":"S. V. Bogovalov, I. V. Tronin, A. V. Vasilyev","doi":"10.1080/00295639.2024.2332021","DOIUrl":"https://doi.org/10.1080/00295639.2024.2332021","url":null,"abstract":"In this paper, numerical simulation methods are used to study issues related to the optimal operating modes of hyperspeed (rotor velocity 1000 m/s and above) model gas centrifuges (GCs) of various ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"8 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140637241","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 Fission Matrix Databases with Nonuniform Fuel Temperature Profiles for Static and Transient Calculations 用于静态和瞬态计算的非均匀燃料温度曲线裂变矩阵数据库分析
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-22 DOI: 10.1080/00295639.2024.2328944
Maximiliano Dalinger, William Walters
{"title":"Analysis of Fission Matrix Databases with Nonuniform Fuel Temperature Profiles for Static and Transient Calculations","authors":"Maximiliano Dalinger, William Walters","doi":"10.1080/00295639.2024.2328944","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328944","url":null,"abstract":"Monte Carlo codes are the most accurate way to solve the neutronics in a reactor core but can be computationally expensive, especially for when feedback effects are considered or for transient calc...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"96 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140637242","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
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