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Zirconium in the Nuclear Industry: 19th International Symposium最新文献

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Development of Cr-Al Coating on Zircaloy-4 for Enhanced Accident Tolerant Fuel 增强型耐事故燃料锆合金-4 Cr-Al涂层的研制
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190025
Hyun Gil Kim, Il-hyun Kim, Y. Jung, D. Park, Jung-Hwan Park, Young-ho Lee, Byoung-Kwon Choi
{"title":"Development of Cr-Al Coating on Zircaloy-4 for Enhanced Accident Tolerant Fuel","authors":"Hyun Gil Kim, Il-hyun Kim, Y. Jung, D. Park, Jung-Hwan Park, Young-ho Lee, Byoung-Kwon Choi","doi":"10.1520/stp162220190025","DOIUrl":"https://doi.org/10.1520/stp162220190025","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79470236","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Fundamental Understanding of Nb Effect on Corrosion Mechanisms of Irradiated Zr-Nb Alloys Nb对辐照Zr-Nb合金腐蚀机理影响的基本认识
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190021
Zefeng Yu, M. Moorehead, L. Borrel, Jing Hu, M. Bachhav, A. Couet
{"title":"Fundamental Understanding of Nb Effect on Corrosion Mechanisms of Irradiated Zr-Nb Alloys","authors":"Zefeng Yu, M. Moorehead, L. Borrel, Jing Hu, M. Bachhav, A. Couet","doi":"10.1520/stp162220190021","DOIUrl":"https://doi.org/10.1520/stp162220190021","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79406503","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Characterization of Hydrides and the α-Zr Matrix in Zirconium Alloys: Effects of Stresses, Microstructure, and Neutron Irradiation on Hydride Texture, Terminal Solid Solubility, and Dislocation Structure 锆合金中氢化物和α-Zr基体的表征:应力、微观结构和中子辐照对氢化物织构、末端固溶度和位错结构的影响
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190019
P. Vizcaino, Alejandra Flores, M. A. Vicente Alvarez, J. Santisteban, G. Domizzi, A. Tolley, A. Condó, J. Almer
{"title":"Characterization of Hydrides and the α-Zr Matrix in Zirconium Alloys: Effects of Stresses, Microstructure, and Neutron Irradiation on Hydride Texture, Terminal Solid Solubility, and Dislocation Structure","authors":"P. Vizcaino, Alejandra Flores, M. A. Vicente Alvarez, J. Santisteban, G. Domizzi, A. Tolley, A. Condó, J. Almer","doi":"10.1520/stp162220190019","DOIUrl":"https://doi.org/10.1520/stp162220190019","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83522306","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Fabrication of E110 Alloy Fuel Rod Claddings from Electrolytic Zirconium Base with Removing Fluorine Impurity for Providing Resistance to Breakaway Oxidation in High-Temperature Steam 电解锆基去除氟杂质制备E110合金燃料棒包壳以抗高温蒸汽分离氧化
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190022
V. Markelov, A. Malgin, N. K. Filatova, V. Novikov, A. Shevyakov, A. Gusev, Ivan A. Shelepov, Anton V. Golovin, Alexander V. Ugryumov, Alexey B. Dolgov, Alexander G. Ziganshin, Vladimir E. Donnikov, Vyacheslav I. Latуnin
{"title":"Fabrication of E110 Alloy Fuel Rod Claddings from Electrolytic Zirconium Base with Removing Fluorine Impurity for Providing Resistance to Breakaway Oxidation in High-Temperature Steam","authors":"V. Markelov, A. Malgin, N. K. Filatova, V. Novikov, A. Shevyakov, A. Gusev, Ivan A. Shelepov, Anton V. Golovin, Alexander V. Ugryumov, Alexey B. Dolgov, Alexander G. Ziganshin, Vladimir E. Donnikov, Vyacheslav I. Latуnin","doi":"10.1520/stp162220190022","DOIUrl":"https://doi.org/10.1520/stp162220190022","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85938609","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Analysis of the Corrosion Behavior of Vapor-Deposited CrN-Coated Zirconium under Normal Operation and Accident Scenarios 气相沉积crn包覆锆在正常工况和事故工况下的腐蚀行为分析
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190005
C. Dever, K. Daub, H. Nordin
{"title":"Analysis of the Corrosion Behavior of Vapor-Deposited CrN-Coated Zirconium under Normal Operation and Accident Scenarios","authors":"C. Dever, K. Daub, H. Nordin","doi":"10.1520/stp162220190005","DOIUrl":"https://doi.org/10.1520/stp162220190005","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"81982968","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Back-Calculated Indentation Stress-Strain Curves from Small Scale Testing and Verification Using Finite Element Models: Application to Nanoindentation and Micropillar Compression Study of a Heavy Ion Irradiated Zr-2.5Nb Alloy 基于有限元模型的小规模试验反演压痕应力-应变曲线:应用于重离子辐照Zr-2.5Nb合金的纳米压痕和微柱压缩研究
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190043
Qiang Wang, M. Daymond
{"title":"Back-Calculated Indentation Stress-Strain Curves from Small Scale Testing and Verification Using Finite Element Models: Application to Nanoindentation and Micropillar Compression Study of a Heavy Ion Irradiated Zr-2.5Nb Alloy","authors":"Qiang Wang, M. Daymond","doi":"10.1520/stp162220190043","DOIUrl":"https://doi.org/10.1520/stp162220190043","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85919802","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Toward an Improved Understanding of the Mechanisms Involved in the Increased Hydrogen Uptake and Corrosion at High Burnups in Zirconium Based Claddings 提高对锆基包层在高燃烧时氢吸收增加和腐蚀机制的理解
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190052
S. Abolhassani, A. Baris, R. Grabherr, John G Hawes, A. Colldeweih, Radovan Vanta, R. Restani, A. Hermann, J. Bertsch, M. Chollet, G. Kuri, Matthias Martin, S. Portier, H. Wiese, H. Schweikert, G. Bart, K. Ammon, G. Ledergerber, M. Limbäck
{"title":"Toward an Improved Understanding of the Mechanisms Involved in the Increased Hydrogen Uptake and Corrosion at High Burnups in Zirconium Based Claddings","authors":"S. Abolhassani, A. Baris, R. Grabherr, John G Hawes, A. Colldeweih, Radovan Vanta, R. Restani, A. Hermann, J. Bertsch, M. Chollet, G. Kuri, Matthias Martin, S. Portier, H. Wiese, H. Schweikert, G. Bart, K. Ammon, G. Ledergerber, M. Limbäck","doi":"10.1520/stp162220190052","DOIUrl":"https://doi.org/10.1520/stp162220190052","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"78442101","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Ex Situ and In Situ Studies of Radiation Damage Mechanisms in Zr-Nb Alloys Zr-Nb合金辐射损伤机理的原位和非原位研究
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190016
Junliang Liu, G. He, A. Callow, Kexue Li, S. Lozano-Perez, A. Wilkinson, Michael Moody, C. Grovenor, Jing Hu, M. Kirk, Meimei Li, A. H. Mir, J. Hinks, S. Donnelly, J. Partezana, H. Nordin
{"title":"Ex Situ and In Situ Studies of Radiation Damage Mechanisms in Zr-Nb Alloys","authors":"Junliang Liu, G. He, A. Callow, Kexue Li, S. Lozano-Perez, A. Wilkinson, Michael Moody, C. Grovenor, Jing Hu, M. Kirk, Meimei Li, A. H. Mir, J. Hinks, S. Donnelly, J. Partezana, H. Nordin","doi":"10.1520/stp162220190016","DOIUrl":"https://doi.org/10.1520/stp162220190016","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82657655","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
Thoughts on the Needed Focal Areas in the Research and Understanding of In-Reactor Corrosion, Hydrogen Absorption, and Hydrogen Migration in Zirconium Alloys 对锆合金反应器内腐蚀、氢吸收和氢迁移研究和认识需要重点领域的思考
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190107
B. Kammenzind
{"title":"Thoughts on the Needed Focal Areas in the Research and Understanding of In-Reactor Corrosion, Hydrogen Absorption, and Hydrogen Migration in Zirconium Alloys","authors":"B. Kammenzind","doi":"10.1520/stp162220190107","DOIUrl":"https://doi.org/10.1520/stp162220190107","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90479264","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Deformation Mechanisms of Zirconium Alloys after Irradiation Studied by Dislocation Dynamics Simulations and In Situ Straining Experiments in TEM 用位错动力学模拟和原位应变实验研究辐照后锆合金的变形机理
Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190036
F. Onimus, L. Dupuy, M. Gaumé, W. Kassem, F. Mompiou
{"title":"Deformation Mechanisms of Zirconium Alloys after Irradiation Studied by Dislocation Dynamics Simulations and In Situ Straining Experiments in TEM","authors":"F. Onimus, L. Dupuy, M. Gaumé, W. Kassem, F. Mompiou","doi":"10.1520/stp162220190036","DOIUrl":"https://doi.org/10.1520/stp162220190036","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82465963","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 2
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