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Hot Hydrogen Testing of W-Coated UN Kernels in a Mo30W Matrix 在 Mo30W 基质中对 W 涂层 UN 内核进行热氢测试
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-15 DOI: 10.1080/00295639.2024.2332001
Arne Cröll, Jamelle K. P. Williams, Brian Taylor, Martin P. Volz, Christopher McKinney, Timothy Coons, Jhonathan Rosales
{"title":"Hot Hydrogen Testing of W-Coated UN Kernels in a Mo30W Matrix","authors":"Arne Cröll, Jamelle K. P. Williams, Brian Taylor, Martin P. Volz, Christopher McKinney, Timothy Coons, Jhonathan Rosales","doi":"10.1080/00295639.2024.2332001","DOIUrl":"https://doi.org/10.1080/00295639.2024.2332001","url":null,"abstract":"Ceramic uranium mononitride (UN) is being considered as a reactor fuel for nuclear thermal propulsion. To avoid or reduce the dissociation of UN at the high temperatures needed, embedding it in a m...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"54 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140590995","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 Multilevel Approach for Direct Core Calculation Schemes 直接核心计算方案的多层次方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-15 DOI: 10.1080/00295639.2024.2329838
Antonio Galia
{"title":"A Multilevel Approach for Direct Core Calculation Schemes","authors":"Antonio Galia","doi":"10.1080/00295639.2024.2329838","DOIUrl":"https://doi.org/10.1080/00295639.2024.2329838","url":null,"abstract":"A method of dynamic homogenization was recently proposed as an alternative technique for three-dimensional (3D) core calculations using a direct approach. This technique allows for producing homoge...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"1 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591152","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
Convergence Study of 2D Transport Method for Multigroup k-Eigenvalue Problems with High-Order Scattering Source Using Fourier Analysis 利用傅立叶分析法对具有高阶散射源的多组 k 特征值问题的二维传输方法的收敛性研究
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-12 DOI: 10.1080/00295639.2024.2310391
Boran Kong, Longfei Xu, Baiwen Li
{"title":"Convergence Study of 2D Transport Method for Multigroup k-Eigenvalue Problems with High-Order Scattering Source Using Fourier Analysis","authors":"Boran Kong, Longfei Xu, Baiwen Li","doi":"10.1080/00295639.2024.2310391","DOIUrl":"https://doi.org/10.1080/00295639.2024.2310391","url":null,"abstract":"The convergence behavior of a two-dimensional (2D) transport method has been derived by Fourier analysis for single-group problems with isotropic sources. However, in real calculation, to pursue pr...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"37 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591146","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
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor 比较压水重水反应堆的泵驱动瞬态耦合多物理场模拟
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-12 DOI: 10.1080/00295639.2024.2331906
Santiago Bazzana, Juan I. Beliera, Dumitru Serghiuta, Alexandre Trottier
{"title":"Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor","authors":"Santiago Bazzana, Juan I. Beliera, Dumitru Serghiuta, Alexandre Trottier","doi":"10.1080/00295639.2024.2331906","DOIUrl":"https://doi.org/10.1080/00295639.2024.2331906","url":null,"abstract":"Comparison of results for global responses predicted by different multiphysics simulations of benchmark problems may fail to reveal potentially significant local modeling issues. An examination of ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"215 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591151","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
Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses 展示在核临界安全分析中减少过度保守的定量和系统方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-10 DOI: 10.1080/00295639.2024.2323866
Sharbrenai Anise Holyk, Robert B. Hayes
{"title":"Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses","authors":"Sharbrenai Anise Holyk, Robert B. Hayes","doi":"10.1080/00295639.2024.2323866","DOIUrl":"https://doi.org/10.1080/00295639.2024.2323866","url":null,"abstract":"Although reducing conservatism would alleviate unnecessary constraints in processing, storage, transportation, and disposal of nuclear materials, excessively conservative approaches are still utili...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"67 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591229","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
Predicting Model Biases of the APOLLO3 Neutronics Code Using Machine Learning: Toward a Multiscale and Multifidelity Approach 利用机器学习预测 APOLLO3 中子代码的模型偏差：采用多尺度和多保真度方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-10 DOI: 10.1080/00295639.2024.2329837
Claire Terrazzoni, Laurent Buiron, Jean-Marc Palau
{"title":"Predicting Model Biases of the APOLLO3 Neutronics Code Using Machine Learning: Toward a Multiscale and Multifidelity Approach","authors":"Claire Terrazzoni, Laurent Buiron, Jean-Marc Palau","doi":"10.1080/00295639.2024.2329837","DOIUrl":"https://doi.org/10.1080/00295639.2024.2329837","url":null,"abstract":"As part of the verification, validation, and uncertainty quantification process applied to neutronics deterministic codes, there is a requirement to expand the validation domain, especially to acco...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"65 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591132","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 Diffusion Scale Approximation for Stochastic Fission Chains with State Feedback 具有状态反馈的随机裂变链的扩散尺度近似值
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-04 DOI: 10.1080/00295639.2024.2324532
Chen Dubi, Anil K. Prinja
{"title":"A Diffusion Scale Approximation for Stochastic Fission Chains with State Feedback","authors":"Chen Dubi, Anil K. Prinja","doi":"10.1080/00295639.2024.2324532","DOIUrl":"https://doi.org/10.1080/00295639.2024.2324532","url":null,"abstract":"Modeling and simulation of stochastic fission chains, often referred to as zero power reactor noise or stochastic transport, is a central topic in nuclear science and engineering, with important pr...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"26 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591150","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
Some Results Concerning the Singular Solution of the Conservative Transport Equation in Spherical Geometry 关于球形几何中保守输运方程奇异解的一些结果
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-03 DOI: 10.1080/00295639.2024.2328931
R. D. M. Garcia
{"title":"Some Results Concerning the Singular Solution of the Conservative Transport Equation in Spherical Geometry","authors":"R. D. M. Garcia","doi":"10.1080/00295639.2024.2328931","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328931","url":null,"abstract":"We examine in this work one of the exact solutions of the conservative transport equation for isotropic scattering in spherical geometry, specifically the solution that is singular at the origin an...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"86 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591130","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
Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4® TRIPOLI-4® 中通用扰动理论功能的实施与测试
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-03 DOI: 10.1080/00295639.2024.2323225
Alexis Jinaphanh, Giorgio Valocchi, Andrea Zoia
{"title":"Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4®","authors":"Alexis Jinaphanh, Giorgio Valocchi, Andrea Zoia","doi":"10.1080/00295639.2024.2323225","DOIUrl":"https://doi.org/10.1080/00295639.2024.2323225","url":null,"abstract":"In this paper, we describe the implementation, verification, and numerical validation of Generalized Perturbation Theory (GPT) capabilities in the TRIPOLI4® Monte Carlo code. The GPT is applied to ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"37 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140591078","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
Prototyping of a Machine Learning–Based Burnup Measurement Capability for Pebble Bed Reactor Fuel 基于机器学习的卵石堆燃料燃耗测量能力原型验证
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-04-02 DOI: 10.1080/00295639.2024.2328937
Nick Rollins, India Allan, Jason Hou
{"title":"Prototyping of a Machine Learning–Based Burnup Measurement Capability for Pebble Bed Reactor Fuel","authors":"Nick Rollins, India Allan, Jason Hou","doi":"10.1080/00295639.2024.2328937","DOIUrl":"https://doi.org/10.1080/00295639.2024.2328937","url":null,"abstract":"The pebble bed reactor is a unique reactor design due to its capacity for continuous multipass circulation of the fuel elements, without causing interruption to reactor operation, with the assistan...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":"80 1","pages":""},"PeriodicalIF":1.2,"publicationDate":"2024-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140590994","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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