The Impact of Europium as a Fission Product Surrogate on Chromium Corrosion in Molten Chloride Salt

The rising interest in molten salts, both as thermal energy storage media and as high-temperature solvents for fissile materials in advanced nuclear reactors, has spurred significant growth in research on structural and functional salt-facing materials. Impurities, such as water, play a significant role in the degradation of materials in molten salt environments. Other impurities, such as fission products, are expected to accumulate in molten salts during normal reactor operation and can affect the properties of the salt and salt-facing materials. During normal reactor operation, rare-earth element species are expected to form as byproducts of fission reactions, potentially degrading or altering the performance of both structural and functional materials exposed to salts. In this work, fission product surrogates, europium metal and EuCl<sub>3</sub>, were added to the KCl-MgCl<sub>2</sub> salt while exposing pure Cr specimens in the melt at 600 and 700 °C for 1000 h. Low reactivity was observed with the baseline salt, while both the Eu and EuCl<sub>3</sub> additions to the salt resulted in increased mass loss of Cr specimens. A capillary electrophoresis technique was developed to enable the detection of low parts-per-million (ppm) concentrations of europium (Eu) in chloride salt both before and after exposure of Cr metal. This technique provides a sensitive and reliable method for monitoring trace levels of Eu, which is critical for understanding the interactions and potential contamination effects in salt-facing materials during reactor operation. This quantification technique can be applied to other cationic and anionic contaminants in halide salts.

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Publication Details

Journal
ACS Applied Engineering Materials
Published
2025-06-16
DOI
https://doi.org/10.1021/acsaenm.5c00191
Primary Topic
Nuclear materials and radiation effects
Type
article
Field-Weighted Citation Impact
0.00

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article

The Impact of Europium as a Fission Product Surrogate on Chromium Corrosion in Molten Chloride Salt

Bruce A. Pint, Stephen S. Raiman, Dino Sulejmanovic, J. Matthew Kurley et al.
ACS Applied Engineering Materials
Nuclear materials and radiation effects
article

The Impact of Europium as a Fission Product Surrogate on Chromium Corrosion in Molten Chloride Salt

Bruce A. Pint, Stephen S. Raiman, Dino Sulejmanovic, J. Matthew Kurley, Yi‐Feng Su
article en

Abstract

The rising interest in molten salts, both as thermal energy storage media and as high-temperature solvents for fissile materials in advanced nuclear reactors, has spurred significant growth in research on structural and functional salt-facing materials. Impurities, such as water, play a significant role in the degradation of materials in molten salt environments. Other impurities, such as fission products, are expected to accumulate in molten salts during normal reactor operation and can affect the properties of the salt and salt-facing materials. During normal reactor operation, rare-earth element species are expected to form as byproducts of fission reactions, potentially degrading or altering the performance of both structural and functional materials exposed to salts. In this work, fission product surrogates, europium metal and EuCl<sub>3</sub>, were added to the KCl-MgCl<sub>2</sub> salt while exposing pure Cr specimens in the melt at 600 and 700 °C for 1000 h. Low reactivity was observed with the baseline salt, while both the Eu and EuCl<sub>3</sub> additions to the salt resulted in increased mass loss of Cr specimens. A capillary electrophoresis technique was developed to enable the detection of low parts-per-million (ppm) concentrations of europium (Eu) in chloride salt both before and after exposure of Cr metal. This technique provides a sensitive and reliable method for monitoring trace levels of Eu, which is critical for understanding the interactions and potential contamination effects in salt-facing materials during reactor operation. This quantification technique can be applied to other cationic and anionic contaminants in halide salts.

ACS Applied Engineering MaterialsVol. 3(6)
Oak Ridge National Laboratory (US), University of Michigan (US)
Office of Nuclear Energy, Oak Ridge National Laboratory
Openalex Percentile: Top 90%
Nuclear materials and radiation effects
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