Design and Irradiation of a Molten Salt Corrosion Experiment in the Ohio State University Research Reactor

Joel Lee McDuffee, N. Dianne Bull Ezell, Kurt R. Smith, Neil Rutger Taylor, Stephen S. Raiman, A Lou Qualls

Research output: Book/ReportCommissioned report

Abstract

The primary containment system of any molten salt reactor (MSR) will be exposed to corrosive salt at high temperatures (>650°C) (McDuffee et al. 2018). Many MSR designs also use dissolved fuel, which introduces the challenge of fission product–induced corrosion. Even those designs that do not call for dissolved fuel might need to address the deleterious effects of dissolved fission products on the fuel containment system and potential particle failure.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2018

Keywords

  • 22 GENERAL STUDIES OF NUCLEAR REACTORS

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