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Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks 利用确定性和概率性深度神经网络监测静态源驱动亚临界系统的反应堆物理特性
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-01 DOI: 10.1080/00295639.2024.2328957
Ronald Daryll E. Gatchalian, Pavel V. Tsvetkov
{"title":"Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks","authors":"Ronald Daryll E. Gatchalian, Pavel V. Tsvetkov","doi":"10.1080/00295639.2024.2328957","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328957","url":null,"abstract":"Reactivity measurement methods, like the Amplified Source Method (ASM), link observable quantities to integral physics parameters characterizing subcritical assemblies (SCAs). These methods were mo...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"5 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591079","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
Experimental Covariance Determination for Critical Integral Experiments 临界积分实验的实验协方差确定
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-01 DOI: 10.1080/00295639.2024.2328452
Eric Aboud, Jesse Norris, Daniel Siefman
{"title":"Experimental Covariance Determination for Critical Integral Experiments","authors":"Eric Aboud, Jesse Norris, Daniel Siefman","doi":"10.1080/00295639.2024.2328452","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328452","url":null,"abstract":"Integral benchmarks for criticality safety and nuclear data validation require expensive uncertainty quantification studies. In general, uncertainty quantification techniques ignore correlations be...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"2018 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591297","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
Coupled Neutronics-Thermal-Hydraulic Modeling of a Molten Salt Reactor: The Aircraft Reactor Experiment 熔盐反应堆的中子-热-水耦合建模：飞机反应堆实验
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-01 DOI: 10.1080/00295639.2024.2328964
François Martin, André Bergeron, Guillaume Campioni, Yannick Gorsse, Nathan Greiner, Elsa Merle
{"title":"Coupled Neutronics-Thermal-Hydraulic Modeling of a Molten Salt Reactor: The Aircraft Reactor Experiment","authors":"François Martin, André Bergeron, Guillaume Campioni, Yannick Gorsse, Nathan Greiner, Elsa Merle","doi":"10.1080/00295639.2024.2328964","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328964","url":null,"abstract":"The CEA multiphysics tool combining the deterministic neutronics code APOLLO3® and the computational fluid dynamics (CFD) platform TRUST/TrioCFD is used to model the first-ever-built molten salt nu...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"16 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591076","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 Assumptions Behind Statistical Sampling: A 235U Fission Yield Uncertainty Propagation Case Study 关于统计取样背后的假设：235U 裂变当量不确定性传播案例研究
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-03-19 DOI: 10.1080/00295639.2024.2323217
Enrica Belfiore, Federico Grimaldi, Luca Fiorito, Pablo Romojaro, Gašper Žerovnik, Pierre-Etienne Labeau, Sandra Dulla
{"title":"On the Assumptions Behind Statistical Sampling: A 235U Fission Yield Uncertainty Propagation Case Study","authors":"Enrica Belfiore, Federico Grimaldi, Luca Fiorito, Pablo Romojaro, Gašper Žerovnik, Pierre-Etienne Labeau, Sandra Dulla","doi":"10.1080/00295639.2024.2323217","DOIUrl":"https://doi.org/10.1080/00295639.2024.2323217","url":null,"abstract":"Monte Carlo sampling is frequently employed for uncertainty quantification in depletion calculations. Several assumptions are needed to perform this analysis. In this work, an assessment of these a...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"3 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140172882","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
Three-Dimensional Full-Core BEAVRS Using OpenMOC with Transport Equivalence 使用具有传输等效性的 OpenMOC 的三维全核心 BEAVRS
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-03-19 DOI: 10.1080/00295639.2024.2321661
G. Giudicelli, B. Forget, K. Smith
{"title":"Three-Dimensional Full-Core BEAVRS Using OpenMOC with Transport Equivalence","authors":"G. Giudicelli, B. Forget, K. Smith","doi":"10.1080/00295639.2024.2321661","DOIUrl":"https://doi.org/10.1080/00295639.2024.2321661","url":null,"abstract":"Using an optimized implementation of the three-dimensional (3D) method of characteristics for neutron transport, along with a novel equivalence method for transport calculations that was designed t...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"78 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-03-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140201543","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
Multiscale Modeling of Flow in Rod Bundles: From Direct Numerical Simulation and Subchannel to Coarse-Mesh CFD 杆束流动的多尺度建模：从直接数值模拟和子通道到粗网格 CFD
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-03-14 DOI: 10.1080/00295639.2024.2318837
Adam R. Kraus, Elia Merzari
{"title":"Multiscale Modeling of Flow in Rod Bundles: From Direct Numerical Simulation and Subchannel to Coarse-Mesh CFD","authors":"Adam R. Kraus, Elia Merzari","doi":"10.1080/00295639.2024.2318837","DOIUrl":"https://doi.org/10.1080/00295639.2024.2318837","url":null,"abstract":"Fast and accurate evaluation of flow and heat transfer phenomena in rod bundles is a problem of long-standing interest in nuclear engineering. Computational fluid dynamics (CFD) can provide accurat...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"69 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140151639","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
Improved Collision Probability Analysis of the Double-Heterogeneity Problem Based on Matrix Chord Length Correction 基于矩阵弦长校正的双异质问题碰撞概率分析改进
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-03-14 DOI: 10.1080/00295639.2024.2311595
Zhaoyu Liang, Ding She, Yutong Wen, Lei Shi, Zuoyi Zhang
{"title":"Improved Collision Probability Analysis of the Double-Heterogeneity Problem Based on Matrix Chord Length Correction","authors":"Zhaoyu Liang, Ding She, Yutong Wen, Lei Shi, Zuoyi Zhang","doi":"10.1080/00295639.2024.2311595","DOIUrl":"https://doi.org/10.1080/00295639.2024.2311595","url":null,"abstract":"Dispersion fuel exhibits excellent safety performance and effectively reduces the risk of radioactive leakage, making it widely applied in high-temperature gas-cooled reactors (HTGRs) and other adv...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"22 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140151635","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 Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities 商用核电设施实物保护系统设计的后果知情许可路径选择
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-03-12 DOI: 10.1080/00295639.2024.2316930
Thomas Freyman, Karen Vierow Kirkland
{"title":"A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities","authors":"Thomas Freyman, Karen Vierow Kirkland","doi":"10.1080/00295639.2024.2316930","DOIUrl":"https://doi.org/10.1080/00295639.2024.2316930","url":null,"abstract":"The survivability of the domestic nuclear power industry depends on the cost-competitiveness of safe and secure nuclear power generation. Advanced reactor design concepts aim to have increased safe...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"9 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-03-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140127510","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
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation 部分衍生物横截面模型的误差分析-I：推导
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-03-05 DOI: 10.1080/00295639.2023.2288308
Thomas Folk, Siddhartha Srivastava, Dean Price, Krishna Garikipati, Brendan Kochunas
{"title":"Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation","authors":"Thomas Folk, Siddhartha Srivastava, Dean Price, Krishna Garikipati, Brendan Kochunas","doi":"10.1080/00295639.2023.2288308","DOIUrl":"https://doi.org/10.1080/00295639.2023.2288308","url":null,"abstract":"Accurate assessment of uncertainties in cross-section data is crucial for reliable nuclear reactor simulations and safety analyses. In this study, we focus on the interpolation procedure of the par...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"132 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140071891","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
User Impressions and Gait Analysis of Exoskeleton Device Usage in Generalized Tank Farm Activities 外骨骼设备在普通油罐区活动中的用户印象和步态分析
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-03-05 DOI: 10.1080/00295639.2024.2316948
Janelle Bottom, David Wood, Tamzidul Mina, Savannah Bradley, Michal Rittikaidachar, Alexandria Miera, Jason Wheeler
{"title":"User Impressions and Gait Analysis of Exoskeleton Device Usage in Generalized Tank Farm Activities","authors":"Janelle Bottom, David Wood, Tamzidul Mina, Savannah Bradley, Michal Rittikaidachar, Alexandria Miera, Jason Wheeler","doi":"10.1080/00295639.2024.2316948","DOIUrl":"https://doi.org/10.1080/00295639.2024.2316948","url":null,"abstract":"Tank farm workers involved in nuclear cleanup activities perform physically demanding tasks, typically while wearing heavy personal protective equipment (PPE). Exoskeleton devices have the potentia...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"27 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-03-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140047415","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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