Zirconium metal electrodeposition on uranium nitride in molten fluoride salts

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-14 DOI:10.1016/j.jnucmat.2025.155750

Jarom L. Chamberlain , Hannah K. Patenaude , Amanda L. Musgrove , Rami J. Batrice , Timothy P. Coons , Marisa J. Monreal

{"title":"Zirconium metal electrodeposition on uranium nitride in molten fluoride salts","authors":"Jarom L. Chamberlain , Hannah K. Patenaude , Amanda L. Musgrove , Rami J. Batrice , Timothy P. Coons , Marisa J. Monreal","doi":"10.1016/j.jnucmat.2025.155750","DOIUrl":null,"url":null,"abstract":"<div><div>Uranium nitride (UN) has application as fuel for nuclear thermal rockets and advanced nuclear reactors. The high melting point, high fissile density, and thermal conductivity of UN makes it an attractive candidate for fuel in these applications. Coating uranium nitride fuel with metal such as zirconium provides additional stability and containment to the UN, promoting its survivability and accident tolerance. This study demonstrates molten salt electrodeposition as a method to deposit a coating of zirconium metal onto a uranium nitride substrate. Cyclic voltammetry was used to characterize the molten salt system and demonstrate the zirconium precursor reduction. Post electrodeposition characterization depicted a zirconium metal coating on the uranium nitride substrate. Preferential growth was observed on one of the substrate interfaces. The average thickness of the coating where preferential growth was depicted was 194 µm.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"609 ","pages":"Article 155750"},"PeriodicalIF":3.2000,"publicationDate":"2025-03-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S002231152500145X","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}

引用次数: 0

Abstract

Uranium nitride (UN) has application as fuel for nuclear thermal rockets and advanced nuclear reactors. The high melting point, high fissile density, and thermal conductivity of UN makes it an attractive candidate for fuel in these applications. Coating uranium nitride fuel with metal such as zirconium provides additional stability and containment to the UN, promoting its survivability and accident tolerance. This study demonstrates molten salt electrodeposition as a method to deposit a coating of zirconium metal onto a uranium nitride substrate. Cyclic voltammetry was used to characterize the molten salt system and demonstrate the zirconium precursor reduction. Post electrodeposition characterization depicted a zirconium metal coating on the uranium nitride substrate. Preferential growth was observed on one of the substrate interfaces. The average thickness of the coating where preferential growth was depicted was 194 µm.

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

熔氟盐中氮化铀电沉积金属锆

氮化铀（UN）作为核热火箭和先进核反应堆的燃料得到了广泛的应用。UN的高熔点、高裂变密度和导热性使其成为这些应用中有吸引力的候选燃料。用锆等金属包裹氮化铀燃料为联合国提供了额外的稳定性和遏制能力，提高了其生存能力和事故容忍度。本研究展示了熔盐电沉积作为一种方法沉积锆金属涂层在铀氮化基底上。采用循环伏安法对熔盐体系进行了表征，并对锆前驱体还原进行了验证。电沉积后的表征描述了氮化铀衬底上的锆金属涂层。在其中一个衬底界面上观察到优先生长。优先生长的涂层平均厚度为194µm。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文去求助

来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.