Zirconium in the Nuclear Industry: 19th International Symposium最新文献_第4页

Test-Reactor Study of the Effect of Zirconia Coating of Inconel Spacer Cells on Shadow Corrosion 铬镍铁合金间隔电池氧化锆涂层对阴影腐蚀影响的试验反应器研究

Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190032

C. Anghel, M. Limbäck, G. Westin, T. Tverberg, Björn Andersson, Michael Leideborg, Jonathan Wright

引用次数: 0

Toward a Mechanistic Understanding of Pellet Cladding Interaction Using Advanced 3D Characterization and Atomistic Simulation 迈向微粒包层相互作用的机械理解使用先进的三维表征和原子模拟

Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190047

P. Frankel, A. Garner, Adam Plowman, S. Hanlon, C. Gillen, A. Phillion, C. Race, J. Donoghue, C. Anghel, A. Ambard, M. Daymond

引用次数: 0

Zirconium-Applied Anisotropic Cluster Dynamics for Irradiation-Induced Defect Modeling in Presence of Hydrogen 氢存在下辐照缺陷建模中应用锆的各向异性团簇动力学

Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190013

D. Brimbal, N. Chaari, P. Barbéris, F. Bourlier

引用次数: 1

The Creation of ZIRAT ZIRAT的创建

Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-07-01 DOI: 10.1520/stp162220190080

P. Rudling

引用次数: 0

Corrosion and Ion Irradiation Behavior of Ceramic-Coated Nuclear Fuel Cladding 陶瓷包覆核燃料包壳的腐蚀和离子辐照行为

Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-01-01 DOI: 10.1520/stp162220190029

Ece Alat, Jing Hu, D. Wolfe, A. Motta

{"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}

引用次数: 2

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 长期反应器内锆-4腐蚀片的表征以及通量、通量和温度对氧化物生长、应力发展、相形成和晶粒尺寸的影响

Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2021-01-01 DOI: 10.1520/stp162220190038

B. Ensor, G. Lucadamo, J. Seidensticker, R. Bajaj, Z. Cai, A. Motta

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引用次数: 0

A Review of Early Findings within the Collaborative Research Programme MUZIC—“Mechanistic Understanding of Zirconium Corrosion” MUZIC合作研究项目“锆腐蚀机理研究”早期研究成果综述

Zirconium in the Nuclear Industry: 19th International Symposium Pub Date : 2019-12-20 DOI: 10.1520/stp162220190105

M. Preuss

引用次数: 2