Pub Date : 2024-04-19DOI: 10.1080/00295450.2024.2329830
Mohamed S. El-Genk, Timothy M. Schriener
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 ...
{"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}
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...
辐射场的反向重建方法不需要放射源的信息，并且能够使用少量的监测数据来构建辐射场。
{"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}
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...
{"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}
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 ...
核电站的严重事故可能会因压力增大而破坏安全壳的完整性，导致放射性产品的释放。人们特别关注...
{"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}
Pub Date : 2024-04-15DOI: 10.1080/00295450.2024.2323267
Zeyun Wu, Christian Pochron, Mihai (Mike) G. M. Pop, Neal Mann
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...
{"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}
Pub Date : 2024-04-15DOI: 10.1080/00295450.2024.2323260
Ark O. Ifeanyi, Daniel Dos Santos, Abhinav Saxena, Jamie Coble
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...
{"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}
Pub Date : 2024-04-15DOI: 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
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...
{"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}
Pub Date : 2024-04-15DOI: 10.1080/00295450.2024.2324213
Sarah R. Suffield, William A. Perkins, Ben J. Jensen, Brady D. Hanson, Steven B. Ross
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...
{"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}
Pub Date : 2024-04-15DOI: 10.1080/00295450.2024.2315362
John N. Hamawi, Pedro B. Pérez
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...
{"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}
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...
{"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}
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