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Coolability of a Corium Pool in a Debris Bed: Impact of Debris Size, Steam, and Liquid Flow Rate; Tilting Angle; and Pressure on Critical Heat Flux—First Numerical Evaluations 碎片床中铈池的可冷却性：碎片大小、蒸汽和液体流速、倾斜角度和压力对临界热通量的影响--首次数值评估
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-20 DOI: 10.1080/00295639.2024.2357943
C. Sartoris, J.-A. Zambaux, F. Fichot
{"title":"Coolability of a Corium Pool in a Debris Bed: Impact of Debris Size, Steam, and Liquid Flow Rate; Tilting Angle; and Pressure on Critical Heat Flux—First Numerical Evaluations","authors":"C. Sartoris, J.-A. Zambaux, F. Fichot","doi":"10.1080/00295639.2024.2357943","DOIUrl":"https://doi.org/10.1080/00295639.2024.2357943","url":null,"abstract":"In case of a severe accident in a light water reactor, a debris bed may form in the core and possibly melt, as happened in Three Mile Island Unit 2. Knowledge about the coolability of such a molten...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141532521","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
Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM OpenMC 代码中的工具开发：与 OpenFOAM 耦合的相关采样和瞬态裂变矩阵方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-20 DOI: 10.1080/00295639.2024.2357422
Axel Laureau, Thibault Le Meute, Thomas Ligonnet, Elsa Merle
{"title":"Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM","authors":"Axel Laureau, Thibault Le Meute, Thomas Ligonnet, Elsa Merle","doi":"10.1080/00295639.2024.2357422","DOIUrl":"https://doi.org/10.1080/00295639.2024.2357422","url":null,"abstract":"This article outlines the advancements made in broadening the application scope of the OpenMC neutron transport code to include thermohydraulic coupling and nuclear data uncertainty propagation. Th...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141530947","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
Parametric Sensitivity Analysis of Stability Margins of Holos-Quad Microreactor Holos-Quad 微型反应器稳定裕度的参数敏感性分析
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-20 DOI: 10.1080/00295639.2024.2352661
Shai Kinast, Dean Price, Claudio Filippone, Brendan Kochunas
{"title":"Parametric Sensitivity Analysis of Stability Margins of Holos-Quad Microreactor","authors":"Shai Kinast, Dean Price, Claudio Filippone, Brendan Kochunas","doi":"10.1080/00295639.2024.2352661","DOIUrl":"https://doi.org/10.1080/00295639.2024.2352661","url":null,"abstract":"An analysis of the stability margins of the innovative Holos-Quad microreactor design is presented. This high-temeprature gas-cooled reactor (HTGR) system is designed to operate fully autonomously ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141515847","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 Quantification for the Doppler Reactivity Feedback Coefficient of MYRRHA MYRRHA 多普勒反应反馈系数的不确定性量化
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-20 DOI: 10.1080/00295639.2024.2353987
Luca Fiorito, Matteo Zanetti, Federico Grimaldi, Gert van den Eynde
{"title":"Uncertainty Quantification for the Doppler Reactivity Feedback Coefficient of MYRRHA","authors":"Luca Fiorito, Matteo Zanetti, Federico Grimaldi, Gert van den Eynde","doi":"10.1080/00295639.2024.2353987","DOIUrl":"https://doi.org/10.1080/00295639.2024.2353987","url":null,"abstract":"Safety analyses of MYRRHA require calculating the reactor temperature feedback coefficients of reactivity associated with power operation. Within this framework, a significant emphasis is put on th...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141515845","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 Stochastic Calculus Approach to Boltzmann Transport 波尔兹曼输运的随机微积分方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-18 DOI: 10.1080/00295639.2024.2350086
J. Darby Smith, Rich Lehoucq, Brian Franke
{"title":"A Stochastic Calculus Approach to Boltzmann Transport","authors":"J. Darby Smith, Rich Lehoucq, Brian Franke","doi":"10.1080/00295639.2024.2350086","DOIUrl":"https://doi.org/10.1080/00295639.2024.2350086","url":null,"abstract":"Traditional Monte Carlo methods for particle transport utilize source iteration to express the solution, the flux density, of the transport equation as a Neumann series. Our contribution is to show...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141515848","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
Symmetry Determining Equations and Lie Groups of the Neutron Transport Equation 中子输运方程的对称性决定方程和列组
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-18 DOI: 10.1080/00295639.2024.2343119
Patrick F. O’Rourke, Scott D. Ramsey
{"title":"Symmetry Determining Equations and Lie Groups of the Neutron Transport Equation","authors":"Patrick F. O’Rourke, Scott D. Ramsey","doi":"10.1080/00295639.2024.2343119","DOIUrl":"https://doi.org/10.1080/00295639.2024.2343119","url":null,"abstract":"The Grigoriev-Meleshko Method, an indirect Lie group theory method, is used to derive the symmetry determining equations (SDEs) of the neutron transport equation (NTE) and the coupled delayed neutr...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141504868","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 Modified Implicit Monte Carlo Method for Frequency-Dependent Three Temperature Radiative Transfer Equations 频率相关三温辐射传递方程的修正隐式蒙特卡洛法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-14 DOI: 10.1080/00295639.2024.2363089
Min Gao, Yi Shi
{"title":"A Modified Implicit Monte Carlo Method for Frequency-Dependent Three Temperature Radiative Transfer Equations","authors":"Min Gao, Yi Shi","doi":"10.1080/00295639.2024.2363089","DOIUrl":"https://doi.org/10.1080/00295639.2024.2363089","url":null,"abstract":"","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141344863","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
High-Resolution Modeling Without Computation Slowdown for PETALE in CROCUS 为 CROCUS 中的 PETALE 进行高分辨率建模而不降低计算速度
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-14 DOI: 10.1080/00295639.2024.2357963
Thomas Ligonnet, A. Laureau, A. Pautz, V. Lamirand
{"title":"High-Resolution Modeling Without Computation Slowdown for PETALE in CROCUS","authors":"Thomas Ligonnet, A. Laureau, A. Pautz, V. Lamirand","doi":"10.1080/00295639.2024.2357963","DOIUrl":"https://doi.org/10.1080/00295639.2024.2357963","url":null,"abstract":"","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141342160","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
Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors 验证 PARCS/TWOPORFLOW 与小型模块化反应堆棒喷射事故计算的耦合代码
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-13 DOI: 10.1080/00295639.2024.2357953
Alejandro Campos-Muñoz, V.H. Sanchez-Espinoza, E. Redondo-Valero, C. Queral
{"title":"Verification of the Coupled Code PARCS/TWOPORFLOW with Rod Ejection Accident Calculations for Small Modular Reactors","authors":"Alejandro Campos-Muñoz, V.H. Sanchez-Espinoza, E. Redondo-Valero, C. Queral","doi":"10.1080/00295639.2024.2357953","DOIUrl":"https://doi.org/10.1080/00295639.2024.2357953","url":null,"abstract":"","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141349029","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
Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels 高燃耗和扩展浓缩燃料临界安全分析中核数据引起的不确定性
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-06-13 DOI: 10.1080/00295639.2024.2360309
W. A. Metwally, M. N. Dupont, W. J. Marshall, C. Celik, V. Karriem, A. Lang, K. L. Fassino, A. Shaw
{"title":"Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels","authors":"W. A. Metwally, M. N. Dupont, W. J. Marshall, C. Celik, V. Karriem, A. Lang, K. L. Fassino, A. Shaw","doi":"10.1080/00295639.2024.2360309","DOIUrl":"https://doi.org/10.1080/00295639.2024.2360309","url":null,"abstract":"","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-06-13","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141345443","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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