DOE OSTI · 3362780
INL_intern_poster_RashedA
Abstract
Advanced nuclear reactors often operate at elevated temperatures, novel fuel with different chemical and thermal properties that may interact differently with cladding, new coolants (e.g., molten salt, liquid metal, or sodium) that are chemically aggressive, requires cladding materials with superior oxidation, corrosion, and creep resistance. Developing fuel cladding for advanced reactors is essential, as the cladding plays a critical role in reactor safety, performance, and longevity. In this study, innovative Non-Concentrated Alloys (NCAs) were developed as novel fuel cladding materials for advanced nuclear reactors. Multiple elements were chosen for the alloys. NCAs were manufactured and tested mechanically, showing promise with the arc-melting method, and setting a clear path for the next step of NCAs' development as a fuel cladding for advanced nuclear reactors.
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Hakeem Taha Almasri, Rashed Abdul [Idaho National Laboratory], Song, Rongjie [Idaho National Laboratory] (ORCID:0009000790378654), Yang, Jingfan [Idaho National Laboratory], Zhang, Xinchang [Idaho National Laboratory], Xiong, Wei [University of Pittsburgh], Li, Daozheng [University of Pittsburgh]. 2025-08-12. INL_intern_poster_RashedA. https://www.osti.gov/biblio/3362780
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