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A Semi-Analytical Prediction Model for Fluid-Elastic Instability of a Normal Triangular Tube Array Under Transverse Flow Excitation 横向流动激励下正常三角管阵列流体弹性不稳定性的半解析预测模型
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-02 DOI: 10.1080/00295450.2024.2312023
Gongbo Chen, Naibin Jiang
{"title":"A Semi-Analytical Prediction Model for Fluid-Elastic Instability of a Normal Triangular Tube Array Under Transverse Flow Excitation","authors":"Gongbo Chen, Naibin Jiang","doi":"10.1080/00295450.2024.2312023","DOIUrl":"https://doi.org/10.1080/00295450.2024.2312023","url":null,"abstract":"The heat exchange tubes in the steam generator are susceptible to vibration caused by fluid flow, which can lead to damage to both the tubes and their support structures due to collisions. To enhan...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"26 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570724","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
Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks 利用神经网络确定缓解给水泵瞬态损失的增益调度参数
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-01 DOI: 10.1080/00295450.2024.2312022
Ryan J. Hoover, Kenji Shimada
{"title":"Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks","authors":"Ryan J. Hoover, Kenji Shimada","doi":"10.1080/00295450.2024.2312022","DOIUrl":"https://doi.org/10.1080/00295450.2024.2312022","url":null,"abstract":"Transient mitigation for nuclear power plants is essential for safe operation. The fourth industrial revolution brings with it the potential for data-based predictive maintenance and identifying re...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"28 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570304","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
Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor 池式研究堆电站瞬态停电的最佳估计加不确定性分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-01 DOI: 10.1080/00295450.2024.2304915
Amitanshu Mishra, Paban Kumar Guchhait, Samiran Sengupta
{"title":"Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor","authors":"Amitanshu Mishra, Paban Kumar Guchhait, Samiran Sengupta","doi":"10.1080/00295450.2024.2304915","DOIUrl":"https://doi.org/10.1080/00295450.2024.2304915","url":null,"abstract":"Simulation of a station blackout (SBO) scenario was carried out for an open pool–type nuclear research reactor. The SBO transient was analyzed using the best estimate (BE) thermal-hydraulic code RE...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"206 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570825","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
Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels 用于干式贮存铝壳乏核燃料的氢氧化铝薄膜的干燥和分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-01 DOI: 10.1080/00295450.2024.2312019
Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight
{"title":"Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels","authors":"Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight","doi":"10.1080/00295450.2024.2312019","DOIUrl":"https://doi.org/10.1080/00295450.2024.2312019","url":null,"abstract":"In aluminum-clad spent nuclear fuels, an (oxy)hydroxide layer on the surface of the cladding hosts chemisorbed water formed during reactor and post-discharge exposure to water. Any residual water i...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"57 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570297","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
Estimation of Densities of Aqueous Actinide Solutions Ranging from Pure Water to Hydrated Crystals 估算从纯水到水合晶体的锕系元素水溶液密度
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-03-27 DOI: 10.1080/00295450.2024.2309070
Shekhar Kumar
{"title":"Estimation of Densities of Aqueous Actinide Solutions Ranging from Pure Water to Hydrated Crystals","authors":"Shekhar Kumar","doi":"10.1080/00295450.2024.2309070","DOIUrl":"https://doi.org/10.1080/00295450.2024.2309070","url":null,"abstract":"The density of aqueous solutions containing actinide nitrates is an important parameter for process design, equipment design, and remote operation/control. It is also significantly important for th...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"109 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316231","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
Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring 模拟小型模块化反应堆燃料置换时的中子泄漏变化及其对无人值守保障监督的影响
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-03-26 DOI: 10.1080/00295450.2024.2304931
Markus Preston, Erik Branger, Sophie Grape, Olena Khotiaintseva
{"title":"Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring","authors":"Markus Preston, Erik Branger, Sophie Grape, Olena Khotiaintseva","doi":"10.1080/00295450.2024.2304931","DOIUrl":"https://doi.org/10.1080/00295450.2024.2304931","url":null,"abstract":"According to a recently proposed nuclear safeguards technique, monitoring the power-normalized, ex-core neutron detection rate over time could be used to detect undeclared changes to the fissile co...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"210 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316061","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
Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay 奥帕林纳斯粘土全尺度加热器实验的热-水文模拟模型开发
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-03-26 DOI: 10.1080/00295450.2024.2304910
Teklu Hadgu, Edward Matteo, Thomas Dewers
{"title":"Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay","authors":"Teklu Hadgu, Edward Matteo, Thomas Dewers","doi":"10.1080/00295450.2024.2304910","DOIUrl":"https://doi.org/10.1080/00295450.2024.2304910","url":null,"abstract":"Disposal of commercial spent nuclear fuel in a geologic repository is studied. In situ heater experiments in underground research laboratories provide a realistic representation of subsurface behav...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"38 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316227","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
Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models 利用代数模型进行火灾影响分析的移动应用开发计划
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-03-25 DOI: 10.1080/00295450.2024.2309599
Yongjae Kim, Seokhyeon Han, Seungjun Oh, Samwon Chung
{"title":"Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models","authors":"Yongjae Kim, Seokhyeon Han, Seungjun Oh, Samwon Chung","doi":"10.1080/00295450.2024.2309599","DOIUrl":"https://doi.org/10.1080/00295450.2024.2309599","url":null,"abstract":"There are numerous computational programs available for fire influence analysis; however, currently, there is no computational program in Korea specifically designed to aid Authority Having Jurisdi...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"34 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316135","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
Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly 叶片偏转角度对燃料棒组件流动-热特性影响的数值分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-03-25 DOI: 10.1080/00295450.2024.2309080
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
{"title":"Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly","authors":"Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma","doi":"10.1080/00295450.2024.2309080","DOIUrl":"https://doi.org/10.1080/00295450.2024.2309080","url":null,"abstract":"The utilization of a grid spacer with vane is a significant component within reactor fuel channels. The presence of the vane has a notable impact on the mixing of flow and the enhancement of heat t...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"14 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316057","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
Experimental Model to Study Characteristics of Radon Cover in Waste Landfills 研究垃圾填埋场氡覆盖特性的实验模型
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-03-25 DOI: 10.1080/00295450.2024.2311977
Nora Nassiri-Mofakham, Mojtaba Kakaei
{"title":"Experimental Model to Study Characteristics of Radon Cover in Waste Landfills","authors":"Nora Nassiri-Mofakham, Mojtaba Kakaei","doi":"10.1080/00295450.2024.2311977","DOIUrl":"https://doi.org/10.1080/00295450.2024.2311977","url":null,"abstract":"Waste from resource extraction industries contains uranium and thorium decay chain radionuclides. One important radiological impact of these wastes is the release of radon into the atmosphere. Ther...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"252 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140302541","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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