Pengfei Ma , Shihao Wu , Bo Liu , Haoli Wang , Yaping Zhang , Yicong Lan , Dayan Ma , Junkai Deng , Yapei Zhang , Kui Ge , Wenxi Tian , Suizheng Qiu , G.H. Su
{"title":"基于实验和第一性原理的CrSi包覆Zr合金扩散和溶解机理","authors":"Pengfei Ma , Shihao Wu , Bo Liu , Haoli Wang , Yaping Zhang , Yicong Lan , Dayan Ma , Junkai Deng , Yapei Zhang , Kui Ge , Wenxi Tian , Suizheng Qiu , G.H. Su","doi":"10.1016/j.jnucmat.2025.156050","DOIUrl":null,"url":null,"abstract":"<div><div>Accident-tolerant fuel (ATF) represents a critical research direction for enhancing nuclear reactor safety, with Cr-coated zirconium alloy cladding being one of the leading ATF cladding candidates. However, under beyond-design-basis accidents (BDBA) and reactivity-initiated accident (RIA) conditions, the eutectic melting of Cr-Zr poses a significant challenge to cladding integrity and safety. Current research suggests that suppressing elemental diffusion at the Cr/Zr interface is key to designing Cr coatings with enhanced resistance to eutectic melting, with the most effective approach being the introduction of a diffusion barrier layer between the coating and the substrate. In this study, a combined experimental and first-principles simulation approach was employed to investigate atomic diffusion behavior and dissolution mechanisms in CrSi coatings. CrSi coatings were conducted using a multi-arc ion beam physical vapor deposition system, followed by vacuum annealing in the 1800s to examine interfacial diffusion phenomena between the CrSi coating and the zirconium substrate. Meanwhile, the scratch tests and steam oxidation experiments were performed to investigated the CrSi coating performance. Furthermore, first-principles calculations were further conducted to establish interfacial dissolution models for the CrSi coating and the zirconium substrate, elucidating the dissolution mechanisms of Cr and Si atoms in both the HCP-Zr and transformed BCC-Zr phases. This study provides novel insights and theoretical foundations for the development of advanced Cr-Si-containing coatings, facilitating the engineering application of coated zirconium cladding under BDBA and RIA conditions.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 156050"},"PeriodicalIF":3.2000,"publicationDate":"2025-07-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Diffusion and dissolution mechanism of CrSi coated Zr alloy by experiments and first principles\",\"authors\":\"Pengfei Ma , Shihao Wu , Bo Liu , Haoli Wang , Yaping Zhang , Yicong Lan , Dayan Ma , Junkai Deng , Yapei Zhang , Kui Ge , Wenxi Tian , Suizheng Qiu , G.H. Su\",\"doi\":\"10.1016/j.jnucmat.2025.156050\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Accident-tolerant fuel (ATF) represents a critical research direction for enhancing nuclear reactor safety, with Cr-coated zirconium alloy cladding being one of the leading ATF cladding candidates. However, under beyond-design-basis accidents (BDBA) and reactivity-initiated accident (RIA) conditions, the eutectic melting of Cr-Zr poses a significant challenge to cladding integrity and safety. Current research suggests that suppressing elemental diffusion at the Cr/Zr interface is key to designing Cr coatings with enhanced resistance to eutectic melting, with the most effective approach being the introduction of a diffusion barrier layer between the coating and the substrate. In this study, a combined experimental and first-principles simulation approach was employed to investigate atomic diffusion behavior and dissolution mechanisms in CrSi coatings. CrSi coatings were conducted using a multi-arc ion beam physical vapor deposition system, followed by vacuum annealing in the 1800s to examine interfacial diffusion phenomena between the CrSi coating and the zirconium substrate. Meanwhile, the scratch tests and steam oxidation experiments were performed to investigated the CrSi coating performance. Furthermore, first-principles calculations were further conducted to establish interfacial dissolution models for the CrSi coating and the zirconium substrate, elucidating the dissolution mechanisms of Cr and Si atoms in both the HCP-Zr and transformed BCC-Zr phases. This study provides novel insights and theoretical foundations for the development of advanced Cr-Si-containing coatings, facilitating the engineering application of coated zirconium cladding under BDBA and RIA conditions.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"616 \",\"pages\":\"Article 156050\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-07-21\",\"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/S0022311525004441\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525004441","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}
Diffusion and dissolution mechanism of CrSi coated Zr alloy by experiments and first principles
Accident-tolerant fuel (ATF) represents a critical research direction for enhancing nuclear reactor safety, with Cr-coated zirconium alloy cladding being one of the leading ATF cladding candidates. However, under beyond-design-basis accidents (BDBA) and reactivity-initiated accident (RIA) conditions, the eutectic melting of Cr-Zr poses a significant challenge to cladding integrity and safety. Current research suggests that suppressing elemental diffusion at the Cr/Zr interface is key to designing Cr coatings with enhanced resistance to eutectic melting, with the most effective approach being the introduction of a diffusion barrier layer between the coating and the substrate. In this study, a combined experimental and first-principles simulation approach was employed to investigate atomic diffusion behavior and dissolution mechanisms in CrSi coatings. CrSi coatings were conducted using a multi-arc ion beam physical vapor deposition system, followed by vacuum annealing in the 1800s to examine interfacial diffusion phenomena between the CrSi coating and the zirconium substrate. Meanwhile, the scratch tests and steam oxidation experiments were performed to investigated the CrSi coating performance. Furthermore, first-principles calculations were further conducted to establish interfacial dissolution models for the CrSi coating and the zirconium substrate, elucidating the dissolution mechanisms of Cr and Si atoms in both the HCP-Zr and transformed BCC-Zr phases. This study provides novel insights and theoretical foundations for the development of advanced Cr-Si-containing coatings, facilitating the engineering application of coated zirconium cladding under BDBA and RIA conditions.
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.