C. Anghel, M. Limbäck, G. Westin, T. Tverberg, Björn Andersson, Michael Leideborg, Jonathan Wright
{"title":"Test-Reactor Study of the Effect of Zirconia Coating of Inconel Spacer Cells on Shadow Corrosion","authors":"C. Anghel, M. Limbäck, G. Westin, T. Tverberg, Björn Andersson, Michael Leideborg, Jonathan Wright","doi":"10.1520/stp162220190032","DOIUrl":"https://doi.org/10.1520/stp162220190032","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":"79984710","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}
P. Frankel, A. Garner, Adam Plowman, S. Hanlon, C. Gillen, A. Phillion, C. Race, J. Donoghue, C. Anghel, A. Ambard, M. Daymond
{"title":"Toward a Mechanistic Understanding of Pellet Cladding Interaction Using Advanced 3D Characterization and Atomistic Simulation","authors":"P. Frankel, A. Garner, Adam Plowman, S. Hanlon, C. Gillen, A. Phillion, C. Race, J. Donoghue, C. Anghel, A. Ambard, M. Daymond","doi":"10.1520/stp162220190047","DOIUrl":"https://doi.org/10.1520/stp162220190047","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":"87890478","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}
{"title":"Zirconium-Applied Anisotropic Cluster Dynamics for Irradiation-Induced Defect Modeling in Presence of Hydrogen","authors":"D. Brimbal, N. Chaari, P. Barbéris, F. Bourlier","doi":"10.1520/stp162220190013","DOIUrl":"https://doi.org/10.1520/stp162220190013","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":"85037570","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}
{"title":"The Creation of ZIRAT","authors":"P. Rudling","doi":"10.1520/stp162220190080","DOIUrl":"https://doi.org/10.1520/stp162220190080","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":"85858538","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}
Recent concern with fuel safety in accident scenarios has motivated research into accident tolerant fuels (ATF), which are defined as fuels that could increase coping time in case of an accident. This study is an attempt to develop an ATF by improving the corrosion performance of nuclear fuel cladding during a hightemperature excursion through the application of a ceramic coating using physical vapor deposition. In this study, ceramic coatings constituted of singlelayer and multi-layer TiN/TiAlN coatings with a titanium bond coat layer to improve adhesion were applied onto ZIRLO sheets using cathodic arc physical vapor deposition. The coating architecture and deposition parameters were systematically optimized to achieve good adhesion and corrosion performance, and an initial evaluation was performed for resistance to radiation damage. The coating performance was highly dependent on coating design architecture, and the best coating architecture was found to be that of eight-layer TiN/TiAlN coatings deposited with optimized parameters. The optimized coatings were Manuscript received March 6, 2019; accepted for publication January 29, 2020. Dept. of Materials Science and Engineering, The Pennsylvania State University, University Park, PA 16802, USA E. A. https://orcid.org/0000-0003-0312-6269, A. T. M. https://orcid.org/0000-0001-5735-1491 Applied Materials Division, IVEM, Building 212, Argonne National Laboratory, Lemont, IL 60439, USA https://orcid.org/0000-0003-1402-5949 Applied Research Laboratory, The Pennsylvania State University, 119 Materials Research Building, University Park, PA 16802, USA Ken and Mary Alice Lindquist Dept. of Nuclear Engineering, The Pennsylvania State University, University Park, PA 16802, USA ASTM 19th International Symposium on Zirconium in the Nuclear Industry on May 19–23, 2019 in
{"title":"Corrosion and Ion Irradiation Behavior of Ceramic-Coated Nuclear Fuel Cladding","authors":"Ece Alat, Jing Hu, D. Wolfe, A. Motta","doi":"10.1520/stp162220190029","DOIUrl":"https://doi.org/10.1520/stp162220190029","url":null,"abstract":"Recent concern with fuel safety in accident scenarios has motivated research into accident tolerant fuels (ATF), which are defined as fuels that could increase coping time in case of an accident. This study is an attempt to develop an ATF by improving the corrosion performance of nuclear fuel cladding during a hightemperature excursion through the application of a ceramic coating using physical vapor deposition. In this study, ceramic coatings constituted of singlelayer and multi-layer TiN/TiAlN coatings with a titanium bond coat layer to improve adhesion were applied onto ZIRLO sheets using cathodic arc physical vapor deposition. The coating architecture and deposition parameters were systematically optimized to achieve good adhesion and corrosion performance, and an initial evaluation was performed for resistance to radiation damage. The coating performance was highly dependent on coating design architecture, and the best coating architecture was found to be that of eight-layer TiN/TiAlN coatings deposited with optimized parameters. The optimized coatings were Manuscript received March 6, 2019; accepted for publication January 29, 2020. Dept. of Materials Science and Engineering, The Pennsylvania State University, University Park, PA 16802, USA E. A. https://orcid.org/0000-0003-0312-6269, A. T. M. https://orcid.org/0000-0001-5735-1491 Applied Materials Division, IVEM, Building 212, Argonne National Laboratory, Lemont, IL 60439, USA https://orcid.org/0000-0003-1402-5949 Applied Research Laboratory, The Pennsylvania State University, 119 Materials Research Building, University Park, PA 16802, USA Ken and Mary Alice Lindquist Dept. of Nuclear Engineering, The Pennsylvania State University, University Park, PA 16802, USA ASTM 19th International Symposium on Zirconium in the Nuclear Industry on May 19–23, 2019 in","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85159198","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}
B. Ensor, G. Lucadamo, J. Seidensticker, R. Bajaj, Z. Cai, A. Motta
Eleven Zircaloy-4 samples were irradiated in the Advanced Test Reactor at a variety of temperatures and neutron flux levels for up to 6.5 years. Subsequently, the coupons were characterized with complementary techniques to understand the mechanisms behind oxide growth as a function of different corrosion environments. Samples were examined using synchrotron X-ray diffraction/ fluorescence, traditional X-ray diffraction, focused ion beam/scanning electron microscopy serial sectioning, and three-dimensional reconstruction to develop Manuscript received March 28, 2019; accepted for publication August 13, 2019. Dept. of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA 16802, USA B. E. http://orcid.org/0000-0002-4592-7147, A. T. M. http://orcid.org/0000-0001-5735-1491 Naval Nuclear Laboratory, Schenectady, NY 12301, USA Naval Nuclear Laboratory, West Mifflin, PA 15122, USA Advanced Photon Source, Argonne National Laboratory, Argonne, IL 60439, USA ASTM 19th International Symposium on Zirconium in the Nuclear Industry on May 19–23, 2019 in
{"title":"Characterization of Long-Term, In-Reactor Zircaloy-4 Corrosion Coupons and the Impact of Flux, Fluence, and Temperature on Oxide Growth, Stress Development, Phase Formation, and Grain Size","authors":"B. Ensor, G. Lucadamo, J. Seidensticker, R. Bajaj, Z. Cai, A. Motta","doi":"10.1520/stp162220190038","DOIUrl":"https://doi.org/10.1520/stp162220190038","url":null,"abstract":"Eleven Zircaloy-4 samples were irradiated in the Advanced Test Reactor at a variety of temperatures and neutron flux levels for up to 6.5 years. Subsequently, the coupons were characterized with complementary techniques to understand the mechanisms behind oxide growth as a function of different corrosion environments. Samples were examined using synchrotron X-ray diffraction/ fluorescence, traditional X-ray diffraction, focused ion beam/scanning electron microscopy serial sectioning, and three-dimensional reconstruction to develop Manuscript received March 28, 2019; accepted for publication August 13, 2019. Dept. of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA 16802, USA B. E. http://orcid.org/0000-0002-4592-7147, A. T. M. http://orcid.org/0000-0001-5735-1491 Naval Nuclear Laboratory, Schenectady, NY 12301, USA Naval Nuclear Laboratory, West Mifflin, PA 15122, USA Advanced Photon Source, Argonne National Laboratory, Argonne, IL 60439, USA ASTM 19th International Symposium on Zirconium in the Nuclear Industry on May 19–23, 2019 in","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2021-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86622472","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}
{"title":"A Review of Early Findings within the Collaborative Research Programme MUZIC—“Mechanistic Understanding of Zirconium Corrosion”","authors":"M. Preuss","doi":"10.1520/stp162220190105","DOIUrl":"https://doi.org/10.1520/stp162220190105","url":null,"abstract":"","PeriodicalId":24038,"journal":{"name":"Zirconium in the Nuclear Industry: 19th International Symposium","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2019-12-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"85090293","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}
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