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Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface 用于月球表面核反应堆动力系统的轻质热管散热器
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-19 DOI: 10.1080/00295450.2024.2329830
Mohamed S. El-Genk, Timothy M. Schriener
{"title":"Lightweight Heat Pipe Radiator for Nuclear Reactor Power Systems on Lunar Surface","authors":"Mohamed S. El-Genk, Timothy M. Schriener","doi":"10.1080/00295450.2024.2329830","DOIUrl":"https://doi.org/10.1080/00295450.2024.2329830","url":null,"abstract":"Heat rejection radiators of nuclear reactor power systems for space exploration and for planetary surface power are the largest component by volume and mass, depending on the radiator’s design and ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140625240","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
Surrogate Model of Solved Poisson Kriging Method for Radiation Field Reconstruction 用于辐射场重建的求解泊松克里金法替代模型
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-19 DOI: 10.1080/00295450.2024.2325751
Zhenyu Wang, Zungang Wang, Jian Sun, Zhiyuan Li, Shanxue Xi, Xing Wei, Weiqi Huang, Chunzhi Zhou
{"title":"Surrogate Model of Solved Poisson Kriging Method for Radiation Field Reconstruction","authors":"Zhenyu Wang, Zungang Wang, Jian Sun, Zhiyuan Li, Shanxue Xi, Xing Wei, Weiqi Huang, Chunzhi Zhou","doi":"10.1080/00295450.2024.2325751","DOIUrl":"https://doi.org/10.1080/00295450.2024.2325751","url":null,"abstract":"Reverse reconstruction methods for the radiation field do not require information on the radioactive source and are capable of constructing the radiation field using a small amount of monitoring da...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140625282","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
Theoretical Calculation of Gamma-Ray and Neutron Shielding Properties for CsPbBr3-Polypropylene Composite Material 铯硼丙烯-聚丙烯复合材料伽马射线和中子屏蔽性能的理论计算
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-17 DOI: 10.1080/00295450.2024.2323257
Junfeng Zhao, Yuanjie Sun, Yue Zhang, Zhigang Li, Hongtao Zhao, Qingyu Wang
{"title":"Theoretical Calculation of Gamma-Ray and Neutron Shielding Properties for CsPbBr3-Polypropylene Composite Material","authors":"Junfeng Zhao, Yuanjie Sun, Yue Zhang, Zhigang Li, Hongtao Zhao, Qingyu Wang","doi":"10.1080/00295450.2024.2323257","DOIUrl":"https://doi.org/10.1080/00295450.2024.2323257","url":null,"abstract":"The impact of CsPbBr3, known for its high atomic number and cross section with neutrons, on the gamma-ray and neutron shielding properties of CsPbBr3-polypropylene (PP) composite material was inves...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140615393","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
Review of Filtered Containment Venting System (FCVS) Eleven Years After Fukushima Accident 福岛事故 11 年后对过滤式安全壳通风系统（FCVS）的审查
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-17 DOI: 10.1080/00295450.2024.2302716
Jawaria Ahad, Amjad Farooq, Masroor Ahmad, Naseem Irfan, Khalid Waheed
{"title":"Review of Filtered Containment Venting System (FCVS) Eleven Years After Fukushima Accident","authors":"Jawaria Ahad, Amjad Farooq, Masroor Ahmad, Naseem Irfan, Khalid Waheed","doi":"10.1080/00295450.2024.2302716","DOIUrl":"https://doi.org/10.1080/00295450.2024.2302716","url":null,"abstract":"Severe accidents in nuclear power plants can breach the integrity of containment due to pressure build up, resulting in the release of radioactive products. Special interest has been shown towards ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140615554","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
Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools 利用 MCNP 和 SCALE 工具对概念性熔融铀增殖反应堆进行中子分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-15 DOI: 10.1080/00295450.2024.2323267
Zeyun Wu, Christian Pochron, Mihai (Mike) G. M. Pop, Neal Mann
{"title":"Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor Using MCNP and SCALE Tools","authors":"Zeyun Wu, Christian Pochron, Mihai (Mike) G. M. Pop, Neal Mann","doi":"10.1080/00295450.2024.2323267","DOIUrl":"https://doi.org/10.1080/00295450.2024.2323267","url":null,"abstract":"The Molten Uranium Breeder Reactor (MUBR) is a radically new reactor concept with a mixed-energy spectrum. MUBR is fueled with molten uranium metal in large-diameter fuel tubes and is cooled by cir...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140593739","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
Fault Detection and Isolation in Simulated Batch Operation of Fine Motion Control Rod Drives 精细运动控制杆驱动器模拟批量运行中的故障检测和隔离
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-15 DOI: 10.1080/00295450.2024.2323260
Ark O. Ifeanyi, Daniel Dos Santos, Abhinav Saxena, Jamie Coble
{"title":"Fault Detection and Isolation in Simulated Batch Operation of Fine Motion Control Rod Drives","authors":"Ark O. Ifeanyi, Daniel Dos Santos, Abhinav Saxena, Jamie Coble","doi":"10.1080/00295450.2024.2323260","DOIUrl":"https://doi.org/10.1080/00295450.2024.2323260","url":null,"abstract":"Control rods and elements manage the power distribution in nuclear reactors through the motion of banks of rods distributed throughout the core. These positional changes are achieved through the ac...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570311","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
Fluid-Solid Interaction Analysis at the Slip Joint of a Boiling Water Reactor Type 5 Jet Pump 沸水反应堆 5 型喷射泵滑动接头处的流固相互作用分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-15 DOI: 10.1080/00295450.2024.2323239
J. Cruz-Castro, L. H. Hernández-Gómez, Y. López-Grijalba, E. Hernández-Palafox, J. A. Beltrán-Fernández, J. I. E. Palacios-Hernández, I. A. Alarcón-Sánchez
{"title":"Fluid-Solid Interaction Analysis at the Slip Joint of a Boiling Water Reactor Type 5 Jet Pump","authors":"J. Cruz-Castro, L. H. Hernández-Gómez, Y. López-Grijalba, E. Hernández-Palafox, J. A. Beltrán-Fernández, J. I. E. Palacios-Hernández, I. A. Alarcón-Sánchez","doi":"10.1080/00295450.2024.2323239","DOIUrl":"https://doi.org/10.1080/00295450.2024.2323239","url":null,"abstract":"In this paper, the fluid-solid interaction of a jet pump of a boiling water reactor type 5 (BWR/5), with its riser subjected to a leakage flow through its slip joint, is reported. This is a fluid-e...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570309","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
Turbulent Particle Flow in Spent Nuclear Fuel Storage Systems 乏核燃料贮存系统中的湍流粒子流
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-15 DOI: 10.1080/00295450.2024.2324213
Sarah R. Suffield, William A. Perkins, Ben J. Jensen, Brady D. Hanson, Steven B. Ross
{"title":"Turbulent Particle Flow in Spent Nuclear Fuel Storage Systems","authors":"Sarah R. Suffield, William A. Perkins, Ben J. Jensen, Brady D. Hanson, Steven B. Ross","doi":"10.1080/00295450.2024.2324213","DOIUrl":"https://doi.org/10.1080/00295450.2024.2324213","url":null,"abstract":"Deposition models are being developed with the commercial computational fluid dynamics software STAR-CCM+ to evaluate particulate deposition on spent nuclear fuel (SNF) canisters. The primary parti...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140593466","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
Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides 将蒙特卡洛推导出的惰性气体空气浸没有效剂量率系数外推至其他几何形状和放射性核素的选定职业环境
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-15 DOI: 10.1080/00295450.2024.2315362
John N. Hamawi, Pedro B. Pérez
{"title":"Extrapolation of Monte Carlo–Derived Noble Gas Air-Submersion Effective Dose Rate Coefficients for Selected Occupational Settings to Other Geometries and Radionuclides","authors":"John N. Hamawi, Pedro B. Pérez","doi":"10.1080/00295450.2024.2315362","DOIUrl":"https://doi.org/10.1080/00295450.2024.2315362","url":null,"abstract":"External exposures to airborne radioactivity at nuclear power sites are typically based on semi-infinite clouds with uniform concentrations and corresponding effective dose rate coefficients (EDRCs...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570317","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
Combustion Properties of Glove-Box Panel Resins Under Fire Accidents 火灾事故下手套箱面板树脂的燃烧特性
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-12 DOI: 10.1080/00295450.2024.2329832
Shinsuke Tashiro, Gunzo Uchiyama, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Koji Watanabe, Hitoshi Abe, Yuichi Yamane
{"title":"Combustion Properties of Glove-Box Panel Resins Under Fire Accidents","authors":"Shinsuke Tashiro, Gunzo Uchiyama, Takuya Ohno, Yuki Amano, Ryoichiro Yoshida, Koji Watanabe, Hitoshi Abe, Yuichi Yamane","doi":"10.1080/00295450.2024.2329832","DOIUrl":"https://doi.org/10.1080/00295450.2024.2329832","url":null,"abstract":"Contributing to the confinement safety evaluation of glove boxes (GBs) connected to high-efficiency particle air filters for radioactive materials under fire accidents, combustion tests of a flamma...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":null,"pages":null},"PeriodicalIF":1.5,"publicationDate":"2024-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570313","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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