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Meeting 2027 TMS Annual Meeting & Exhibition
Symposium Materials and Chemistry for Molten Salt Systems
Presentation Title Molten Salt Corrosion of 316H Stainless Steel in Nuclear Reactor Environments
Author(s) Alexandra Doherty, Joseph Warner, Austin Wells, Qiufeng Yang, Kaustubh Bawane, Ruchi Gakhar, Bobby Gentile, Connor van Heugten, Aidan Masi, James Earthman, Wiley Simpson, Xuan Zhang, Lingfeng He
On-Site Speaker (Planned) Alexandra Doherty
Abstract Scope 316H stainless steel is a suitable material for advanced reactors and is being investigated for its compliance when developed through laser powder bed fusion. Additive manufacturing (AM) enables the fabrication of materials with complex geometries to be designed for structural applications. A protective oxide layer on 316H stainless steel may not form in molten chloride salt environments, leaving the material susceptible to further dealloying, plus the unique grain structure, the corrosion kinetics of AM 316H stainless steel are largely unknown. Electrochemical corrosion techniques such as zero-resistance ammeter, potentiodynamic polarization, and cyclic voltammetry are used to predict corrosion rates and analyze post-test salt composition. The corrosion mechanisms and post-test salt chemistry are contrasted to those of in-situ neutron-irradiated samples, irradiated in NC State’s PULSTAR Research Reactor. Multimodal characterization is used to qualitatively describe the corrosive behavior of molten chloride salts in a variety of extreme conditions.
Proceedings Inclusion? Planned:
Keywords Nuclear Materials, Additive Manufacturing, Other

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