Establishing a Design Strategy for Corrosion Resistant Structural Materials in Molten Salt Technologies

R. Pillai, D. Sulejmanovic, T. Lowe, S. S. Raiman, B. A. Pint

Research output: Contribution to journalArticlepeer-review

5 Scopus citations

Abstract

To address the gap in material design strategies for structural components in molten salt-powered technologies, the current work aimed to identify key parameters governing corrosion induced degradation of materials during exposures in molten halide salts. The applicability of the data on dissolution rates of pure metals (e.g., Cr) in a given molten salt to enable predictions of corrosion behavior of multicomponent binary and ternary Fe-based model and Ni-based commercial alloys isothermally exposed in the purified KCl-MgCl 2 in quartz capsules at 700 and 800°C was evaluated. The influence of alloy chemistry on initial dissolution rates and the consequent impact on the time-dependent corrosion induced microstructural evolution in the alloy subsurface was predicted with a coupled thermodynamic-kinetic model. The model was well able to predict the Cr depletion in all investigated alloys demonstrating the ability of the proposed approach to enable a unique design strategy for structural materials in molten salts.

Original languageEnglish
Pages (from-to)994-1005
Number of pages12
JournalJOM
Volume75
Issue number4
DOIs
StatePublished - Apr 2023

Funding

A. Willoughby assisted with the experimental work at ORNL. V. Cox is thanked for helping with metallography and microstructural characterization respectively. J. Keiser and M. Romedenne are thanked for their valuable comments on the paper. This research was sponsored by the US Department of Energy Office of Nuclear Energy, Molten Salt Reactor Campaign and the Nuclear Energy Advanced Modeling and Simulation program. A. Willoughby assisted with the experimental work at ORNL. V. Cox is thanked for helping with metallography and microstructural characterization respectively. J. Keiser and M. Romedenne are thanked for their valuable comments on the paper. This research was sponsored by the US Department of Energy Office of Nuclear Energy, Molten Salt Reactor Campaign and the Nuclear Energy Advanced Modeling and Simulation program. This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).

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