Amin Esfandiarpour , Tomasz Stasiak , Zbigniew Kozioł , Jarosław Jasiński , Łukasz Kurpaska , Mikko Alava
{"title":"Characterizing the radiation-induced defect behavior in Inconel 617 through molecular dynamics simulations","authors":"Amin Esfandiarpour , Tomasz Stasiak , Zbigniew Kozioł , Jarosław Jasiński , Łukasz Kurpaska , Mikko Alava","doi":"10.1016/j.jnucmat.2025.156019","DOIUrl":null,"url":null,"abstract":"<div><div>Inconel 617, a nickel–chromium–cobalt–molybdenum superalloy, is a promising candidate for high-temperature nuclear applications due to its mechanical strength and oxidation resistance. Understanding its radiation response is crucial for evaluating its long-term performance. In this study, we employed molecular dynamics (MD) simulations with a modified embedded atom method (MEAM) potential to investigate defect formation and evolution in Inconel 617 with the composition Ni<sub>52</sub>Cr<sub>23.5</sub>Co<sub>11.4</sub>Mo<sub>9.7</sub>Fe<sub>1.6</sub>Al<sub>1.8</sub>, under single-cascade and successive overlapping cascade simulations up to 0.2 displacements per atom (dpa). Successive cascade simulations revealed that Inconel 617 exhibits a defect concentration comparable to values reported in the literature for equimolar NiCrCo. However, it forms fewer dislocations and smaller defect clusters, suggesting improved radiation resistance up to 0.2 dpa. To isolate the role of molybdenum (Mo), we also examined a comparable alloy (Ni<sub>59.8</sub>Cr<sub>27.1</sub>Co<sub>13.1</sub>) without Mo. Our results show that, while Mo does not significantly affect the number of Frenkel pairs (FPs) produced in single 5 keV cascades, it suppresses the formation of large interstitial clusters during successive cascade overlap simulations, thereby enhancing radiation resistance. Tensile simulations indicate that irradiation-induced dislocations reduce both the yield strength and Young’s modulus. These findings provide insights into the radiation tolerance of Inconel 617 and highlight the critical role of Mo in defect dynamics.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"616 ","pages":"Article 156019"},"PeriodicalIF":2.8000,"publicationDate":"2025-07-01","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/S0022311525004131","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
Inconel 617, a nickel–chromium–cobalt–molybdenum superalloy, is a promising candidate for high-temperature nuclear applications due to its mechanical strength and oxidation resistance. Understanding its radiation response is crucial for evaluating its long-term performance. In this study, we employed molecular dynamics (MD) simulations with a modified embedded atom method (MEAM) potential to investigate defect formation and evolution in Inconel 617 with the composition Ni52Cr23.5Co11.4Mo9.7Fe1.6Al1.8, under single-cascade and successive overlapping cascade simulations up to 0.2 displacements per atom (dpa). Successive cascade simulations revealed that Inconel 617 exhibits a defect concentration comparable to values reported in the literature for equimolar NiCrCo. However, it forms fewer dislocations and smaller defect clusters, suggesting improved radiation resistance up to 0.2 dpa. To isolate the role of molybdenum (Mo), we also examined a comparable alloy (Ni59.8Cr27.1Co13.1) without Mo. Our results show that, while Mo does not significantly affect the number of Frenkel pairs (FPs) produced in single 5 keV cascades, it suppresses the formation of large interstitial clusters during successive cascade overlap simulations, thereby enhancing radiation resistance. Tensile simulations indicate that irradiation-induced dislocations reduce both the yield strength and Young’s modulus. These findings provide insights into the radiation tolerance of Inconel 617 and highlight the critical role of Mo in defect dynamics.
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.