Ryan D. Kerr , Duc Nguyen-Manh , Mark R. Gilbert , Samuel T. Murphy
{"title":"Stability of oxide phases in W–Cr–Y SMART alloys","authors":"Ryan D. Kerr , Duc Nguyen-Manh , Mark R. Gilbert , Samuel T. Murphy","doi":"10.1016/j.nme.2025.101987","DOIUrl":null,"url":null,"abstract":"<div><div>The addition of Cr and Y into tungsten can dramatically increase the oxidation resistance of the first wall of a future fusion reactor, thereby reducing the risk of formation of volatile WO<span><math><msub><mrow></mrow><mrow><mn>3</mn></mrow></msub></math></span> and the release of radioactive material. Experimental observations suggest that in these SMART alloys, yttrium facilitates the formation of a self-passivating layer of Cr<sub>2</sub>O<sub>3</sub> at the metal surface, however, how exactly the Y does this remains unclear. Therefore, this work explores the phase stability of compounds consisting of W–Y–Cr–O and solution energies for the different components in tungsten using density functional theory. The simulations suggest that there is a substantial thermodynamic driving force for the formation of Y<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>O<span><math><msub><mrow></mrow><mrow><mn>3</mn></mrow></msub></math></span>, especially from yttrium and oxygen solvated in bulk tungsten. These observations suggest that the role of the yttrium may be to remove the oxygen that may inhibit Cr diffusion to the surface from the tungsten grains. This observation is in accordance with experimental studies showing that the oxidation resistance in the alloy occurs when the oxygen–yttrium ratio in the alloy is close to the stoichiometric ratio for Y<span><math><msub><mrow></mrow><mrow><mn>2</mn></mrow></msub></math></span>O<span><math><msub><mrow></mrow><mrow><mn>3</mn></mrow></msub></math></span>.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101987"},"PeriodicalIF":2.7000,"publicationDate":"2025-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Materials and Energy","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S2352179125001292","RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
The addition of Cr and Y into tungsten can dramatically increase the oxidation resistance of the first wall of a future fusion reactor, thereby reducing the risk of formation of volatile WO and the release of radioactive material. Experimental observations suggest that in these SMART alloys, yttrium facilitates the formation of a self-passivating layer of Cr2O3 at the metal surface, however, how exactly the Y does this remains unclear. Therefore, this work explores the phase stability of compounds consisting of W–Y–Cr–O and solution energies for the different components in tungsten using density functional theory. The simulations suggest that there is a substantial thermodynamic driving force for the formation of YO, especially from yttrium and oxygen solvated in bulk tungsten. These observations suggest that the role of the yttrium may be to remove the oxygen that may inhibit Cr diffusion to the surface from the tungsten grains. This observation is in accordance with experimental studies showing that the oxidation resistance in the alloy occurs when the oxygen–yttrium ratio in the alloy is close to the stoichiometric ratio for YO.
期刊介绍:
The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.