发布求助
文献互助 智能选刊 最新文献

Nuclear Technology最新文献

筛选
英文 中文
Failure Analysis of CRDINiCr Butterfly Valves for Nuclear Power Plant Applications 核电站用 CRDINiCr 蝶阀的失效分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-11 DOI: 10.1080/00295450.2024.2344912
Jian Cheng, Kewei Fang, Kexun Fei, Qiang Wang, Bo Li, Eduardo B. Farfán
{"title":"Failure Analysis of CRDINiCr Butterfly Valves for Nuclear Power Plant Applications","authors":"Jian Cheng, Kewei Fang, Kexun Fei, Qiang Wang, Bo Li, Eduardo B. Farfán","doi":"10.1080/00295450.2024.2344912","DOIUrl":"https://doi.org/10.1080/00295450.2024.2344912","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141355758","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
Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR 压水堆正弦热输入自然循环分析模型
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-11 DOI: 10.1080/00295450.2024.2337234
M. W. Abdulrahman
{"title":"Analytical Model of Natural Circulation with a Sinusoidal Heat Input in a PWR","authors":"M. W. Abdulrahman","doi":"10.1080/00295450.2024.2337234","DOIUrl":"https://doi.org/10.1080/00295450.2024.2337234","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141360363","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
Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions 正常和热管故障条件下热管冷却微反应器的自适应模型预测控制
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-10 DOI: 10.1080/00295450.2024.2342206
Joseph Oncken, Linyu Lin, V. Agarwal
{"title":"Adaptive Model Predictive Control for Heat Pipe–Cooled Microreactors Under Normal and Heat Pipe Failure Conditions","authors":"Joseph Oncken, Linyu Lin, V. Agarwal","doi":"10.1080/00295450.2024.2342206","DOIUrl":"https://doi.org/10.1080/00295450.2024.2342206","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141365429","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
Forecasting the Remaining Useful Life of Filters in Nuclear Power Plants 预测核电站过滤器的剩余使用寿命
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-10 DOI: 10.1080/00295450.2024.2342187
A. Young, M. Devereux, B. Brown, B. Stephen, G. West, S. McArthur
{"title":"Forecasting the Remaining Useful Life of Filters in Nuclear Power Plants","authors":"A. Young, M. Devereux, B. Brown, B. Stephen, G. West, S. McArthur","doi":"10.1080/00295450.2024.2342187","DOIUrl":"https://doi.org/10.1080/00295450.2024.2342187","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141363592","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 AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator 利用反应堆瞬态模拟器分析 AP1000 小破裂失去冷却剂事故
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-10 DOI: 10.1080/00295450.2024.2342168
Hossam H. Abdellatif, P. Bhowmik, David Arcilesi, P. Sabharwall
{"title":"Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator","authors":"Hossam H. Abdellatif, P. Bhowmik, David Arcilesi, P. Sabharwall","doi":"10.1080/00295450.2024.2342168","DOIUrl":"https://doi.org/10.1080/00295450.2024.2342168","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141360812","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
Roadmap of Graphite Moderator and Graphite-Matrix TRISO-Fuel Management Options 石墨慢化剂和石墨矩阵 TRISO-燃料管理方案路线图
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-10 DOI: 10.1080/00295450.2024.2337311
C. Forsberg
{"title":"Roadmap of Graphite Moderator and Graphite-Matrix TRISO-Fuel Management Options","authors":"C. Forsberg","doi":"10.1080/00295450.2024.2337311","DOIUrl":"https://doi.org/10.1080/00295450.2024.2337311","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-10","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141361492","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
Feasibility Analysis of Tritium Measurement in the Aqueous Medium Based on a Plastic Scintillating Fiber Array 基于塑料闪烁光纤阵列的水介质中氚测量可行性分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-07 DOI: 10.1080/00295450.2024.2338508
Wenyu Cheng, Linlin Zeng, He Zhou, Jie Liang, Ke Deng, Qin Zhang, Wei Liu
{"title":"Feasibility Analysis of Tritium Measurement in the Aqueous Medium Based on a Plastic Scintillating Fiber Array","authors":"Wenyu Cheng, Linlin Zeng, He Zhou, Jie Liang, Ke Deng, Qin Zhang, Wei Liu","doi":"10.1080/00295450.2024.2338508","DOIUrl":"https://doi.org/10.1080/00295450.2024.2338508","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141371476","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
SPIDARman: System-Level Physics-Informed Detection of Anomalies in Reactor Collected Data Considering Human Errors SPIDARman：考虑人为误差的反应堆采集数据中的系统级物理信息异常检测
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-07 DOI: 10.1080/00295450.2024.2338507
Ezgi Gursel, Bhavya Reddy, Katy Daniels, Jamie Coble, M. Madadi, Vivek Agarwal, Ronald Boring, Vaibhav Yadav, Anahita Khojandi
{"title":"SPIDARman: System-Level Physics-Informed Detection of Anomalies in Reactor Collected Data Considering Human Errors","authors":"Ezgi Gursel, Bhavya Reddy, Katy Daniels, Jamie Coble, M. Madadi, Vivek Agarwal, Ronald Boring, Vaibhav Yadav, Anahita Khojandi","doi":"10.1080/00295450.2024.2338507","DOIUrl":"https://doi.org/10.1080/00295450.2024.2338507","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141374019","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
Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections 利用主安全壳机器人检查评估福岛第一核电站 1 号机组舱外现象
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-07 DOI: 10.1080/00295450.2024.2339578
Michal Cibula, M. Pellegrini, Masato Mizokami, S. Mizokami
{"title":"Evaluation of Fukushima Daiichi Unit 1 Ex-Vessel Phenomenon Leveraging on Primary Containment Vessel Robotic Inspections","authors":"Michal Cibula, M. Pellegrini, Masato Mizokami, S. Mizokami","doi":"10.1080/00295450.2024.2339578","DOIUrl":"https://doi.org/10.1080/00295450.2024.2339578","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141375837","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
Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project 前言：核能先进建模与仿真热工水力学综合研究项目特刊
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-06-05 DOI: 10.1080/00295450.2024.2346452
Elia Merzari
{"title":"Foreword: Special issue on the Nuclear Energy Advanced Modeling and Simulation Thermal Hydraulics Integrated Research Project","authors":"Elia Merzari","doi":"10.1080/00295450.2024.2346452","DOIUrl":"https://doi.org/10.1080/00295450.2024.2346452","url":null,"abstract":"","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-06-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"141383545","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
首页 上一页 下一页 尾页
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整，为了账户安全，请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
请完成安全验证×
相关产品
×
本文献相关产品
联系我们：info@booksci.cn Book学术提供免费学术资源搜索服务，方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号：481959085
Book学术官方微信