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Hazard Identification Risk Assessment Onsite Survey for External Human-Induced Events Aspect of the Nuclear Power Plant in West Kalimantan, Indonesia 印度尼西亚西加里曼丹核电站外部人为事件方面的危害识别风险评估现场调查
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-26 DOI: 10.1080/00295450.2024.2374660
Khusnul Khotimah, Widjanarko, Siti Alimah, Budi Santoso, Sriyana, Kurnia Anzhar, Joko Waluyo, Gustini H. Sayid, Rismiyanto, Hadi Suntoko, Fepriadi, Nicholas Bertony Saputra, Agus Teguh Pranoto, Yulaida Maya Sari, Ika Wahyu Setya Andani
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引用次数: 0
A RELAP5-3D Model of the Lobo Lead Loop 罗布引线环路的 RELAP5-3D 模型
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-26 DOI: 10.1080/00295450.2024.2374661
Jonathan L. Barthle, Nicholas A. Meehan, G. I. Maldonado, Nicholas R. Brown
{"title":"A RELAP5-3D Model of the Lobo Lead Loop","authors":"Jonathan L. Barthle, Nicholas A. Meehan, G. I. Maldonado, Nicholas R. Brown","doi":"10.1080/00295450.2024.2374661","DOIUrl":"https://doi.org/10.1080/00295450.2024.2374661","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141799934","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Computational Optimization of 133 m Xe Production in the Washington State University TRIGA Reactor 华盛顿州立大学 TRIGA 反应器 133 m Xe 生产的计算优化
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-24 DOI: 10.1080/00295450.2024.2377026
Taylor S. Kimball, Glenn E. Sjoden, Meng-Jen (Vince) Wang, M. Watrous
{"title":"Computational Optimization of\u0000 \u0000 133\u0000 m\u0000 \u0000 Xe Production in the Washington State University TRIGA Reactor","authors":"Taylor S. Kimball, Glenn E. Sjoden, Meng-Jen (Vince) Wang, M. Watrous","doi":"10.1080/00295450.2024.2377026","DOIUrl":"https://doi.org/10.1080/00295450.2024.2377026","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141807813","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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 the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1 福岛第一核电站 1 号机组熔融岩心与干混凝土之间的长期相互作用分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-24 DOI: 10.1080/00295450.2024.2371267
Marco Pellegrini, Christophe Journeau, Nathalie Seiler, Luis E. Herranz, M. García, Claus Spengler, Charlaine Bouillet, Marc Barrachin, David Luxat, Lucas Albright
{"title":"Analysis of the Long-Term Interaction Between Molten Core and Dry Concrete at Fukushima Daiichi Unit 1","authors":"Marco Pellegrini, Christophe Journeau, Nathalie Seiler, Luis E. Herranz, M. García, Claus Spengler, Charlaine Bouillet, Marc Barrachin, David Luxat, Lucas Albright","doi":"10.1080/00295450.2024.2371267","DOIUrl":"https://doi.org/10.1080/00295450.2024.2371267","url":null,"abstract":"The latest investigations of Fukushima Daiichi Unit 1 have demonstrated that corium attack to the pedestal walls and pedestal floor has occurred in Fukushima Daiichi Unit 1 to a certain extent. The...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141886191","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Design and Development of a Portable Neutron Detection System Based on a 6 Li-Doped ZnS(Ag) Scintillator 基于 6 锂掺杂 ZnS(Ag)闪烁体的便携式中子探测系统的设计与开发
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-23 DOI: 10.1080/00295450.2024.2370701
Tuğçe Gürdal, Haluk Yücel
{"title":"Design and Development of a Portable Neutron Detection System Based on a\u0000 6\u0000 Li-Doped ZnS(Ag) Scintillator","authors":"Tuğçe Gürdal, Haluk Yücel","doi":"10.1080/00295450.2024.2370701","DOIUrl":"https://doi.org/10.1080/00295450.2024.2370701","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141810428","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants 应用于核电站被动冷却系统的水热管性能分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-23 DOI: 10.1080/00295450.2024.2372509
Ye Yeong Park, I. Bang
{"title":"Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants","authors":"Ye Yeong Park, I. Bang","doi":"10.1080/00295450.2024.2372509","DOIUrl":"https://doi.org/10.1080/00295450.2024.2372509","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141812421","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Performance Analysis of U 3 Si 2 -Al Fuel with Density of 2.96 gU/cm 3 and Burnup of 56% 密度为 2.96 gU/cm 3、燃烧率为 56% 的 U 3 Si 2 -Al 燃料的性能分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-23 DOI: 10.1080/00295450.2024.2365485
Maman Kartaman Ajiriyanto, Aslina Br. Ginting, Sungkono, Supardjo, Juan Carlos Sihotang
{"title":"Performance Analysis of U\u0000 3\u0000 Si\u0000 2\u0000 -Al Fuel with Density of 2.96 gU/cm\u0000 3\u0000 and Burnup of 56%","authors":"Maman Kartaman Ajiriyanto, Aslina Br. Ginting, Sungkono, Supardjo, Juan Carlos Sihotang","doi":"10.1080/00295450.2024.2365485","DOIUrl":"https://doi.org/10.1080/00295450.2024.2365485","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141810892","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants 核电站运行中的不确定性感知和可解释人为错误检测
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-23 DOI: 10.1080/00295450.2024.2372217
Bhavya Reddy, Ezgi Gursel, Katy Daniels, A. Khojandi, Jamie Baalis Coble, Vivek Agarwal, Ronald Boring, Vaibhav Yadav, M. Madadi
{"title":"Uncertainty-Aware and Explainable Human Error Detection in the Operation of Nuclear Power Plants","authors":"Bhavya Reddy, Ezgi Gursel, Katy Daniels, A. Khojandi, Jamie Baalis Coble, Vivek Agarwal, Ronald Boring, Vaibhav Yadav, M. Madadi","doi":"10.1080/00295450.2024.2372217","DOIUrl":"https://doi.org/10.1080/00295450.2024.2372217","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141813081","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor 倾斜式近海浮动沸水堆中反应堆功率变化的中子-热学-水力学耦合瞬态分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-22 DOI: 10.1080/00295450.2024.2368966
Kodai Fukuda, Toru Obara, K. Suyama
{"title":"Neutronics–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor","authors":"Kodai Fukuda, Toru Obara, K. Suyama","doi":"10.1080/00295450.2024.2368966","DOIUrl":"https://doi.org/10.1080/00295450.2024.2368966","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141816464","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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
Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding 用于压水堆燃料转移保障中微子源计算的特定同位素裂变率计算
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-07-22 DOI: 10.1080/00295450.2024.2369476
Dean Price, Leia Barrowes, James Wells, B. Kochunas
{"title":"Calculation of Isotope-Specific Fission Rates for Neutrino Source Calculation in PWR Fuel Diversion Safeguarding","authors":"Dean Price, Leia Barrowes, James Wells, B. Kochunas","doi":"10.1080/00295450.2024.2369476","DOIUrl":"https://doi.org/10.1080/00295450.2024.2369476","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-07-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141814524","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"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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