Long-term corrosion behavior of borated stainless steel in a simulated spent fuel pool environment

Borated stainless steel (BSS) is widely utilized as a neutron absorber material for criticality control in spent nuclear fuel pools, which use borated water to cool spent nuclear fuel to room temperature. By incorporating boron into SS304, BSS exhibits a higher neutron absorption cross section than other austenitic stainless steels. Boron in BSS has a low solubility in the austenite structure, leading to the formation of a secondary phase, (Fe, Cr) 2 B, upon alloying. Given that BSS is intended for long-term use in spent nuclear fuel pools, it is important to evaluate its long-term integrity. This paper investigates the long-term corrosion behavior of BSS along with its oxide microstructure through an accelerated corrosion experiment simulating spent nuclear fuel pool conditions. The 2-year experiment was conducted at elevated temperatures based on the Arrhenius equation with temperature as a variable. Detailed microstructural analysis employed electron microscopy, energy-dispersive X-ray spectroscopy, electron probe microanalysis, and image analysis. According to the results, upon oxidation, hematite oxide film was formed and shallow, non-propagating incipient localized attack was obserbed on the substrate; the features were typically ≈1–3 μm deep and accounted for <0.1 % of the cross-sectional thickness. Incipient localized attack from the relatively low Cr content in BSS compared to conventional stainless steel. Dissolution of Cr and B was observed from the secondary phase (Fe, Cr) 2 B, indicating that B dissolution is caused by oxidation. • Long-term corrosion of BSS evaluated under simulated spent fuel pool conditions. • Selective oxidation of boride phases observed, forming porous corrosion structures. • Oxide film on secondary phase thicker than on substrate due to enhanced diffusion. • Oxidation sequence followed B .→ Cr → Fe based on Gibbs free energy • Provides insight into BSS degradation mechanism for nuclear storage system safety.

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Publication Details

Journal
Journal of Materials Research and Technology
Published
2025-12-06
DOI
https://doi.org/10.1016/j.jmrt.2025.12.045
Primary Topic
Hydrogen embrittlement and corrosion behaviors in metals
Type
article
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article

Long-term corrosion behavior of borated stainless steel in a simulated spent fuel pool environment

Junhyuk Ham, Seung Chang Yoo, Daehyeon Park, Ji Hyun Kim et al.
Journal of Materials Research and Technology
Hydrogen embrittlement and corrosion behaviors in metals
article

Long-term corrosion behavior of borated stainless steel in a simulated spent fuel pool environment

Junhyuk Ham, Seung Chang Yoo, Daehyeon Park, Ji Hyun Kim, Dong-Hee Lee, Yunju Lee, Yongdeog Kim, Ki-Young Kim
article en

Abstract

Borated stainless steel (BSS) is widely utilized as a neutron absorber material for criticality control in spent nuclear fuel pools, which use borated water to cool spent nuclear fuel to room temperature. By incorporating boron into SS304, BSS exhibits a higher neutron absorption cross section than other austenitic stainless steels. Boron in BSS has a low solubility in the austenite structure, leading to the formation of a secondary phase, (Fe, Cr) 2 B, upon alloying. Given that BSS is intended for long-term use in spent nuclear fuel pools, it is important to evaluate its long-term integrity. This paper investigates the long-term corrosion behavior of BSS along with its oxide microstructure through an accelerated corrosion experiment simulating spent nuclear fuel pool conditions. The 2-year experiment was conducted at elevated temperatures based on the Arrhenius equation with temperature as a variable. Detailed microstructural analysis employed electron microscopy, energy-dispersive X-ray spectroscopy, electron probe microanalysis, and image analysis. According to the results, upon oxidation, hematite oxide film was formed and shallow, non-propagating incipient localized attack was obserbed on the substrate; the features were typically ≈1–3 μm deep and accounted for <0.1 % of the cross-sectional thickness. Incipient localized attack from the relatively low Cr content in BSS compared to conventional stainless steel. Dissolution of Cr and B was observed from the secondary phase (Fe, Cr) 2 B, indicating that B dissolution is caused by oxidation. • Long-term corrosion of BSS evaluated under simulated spent fuel pool conditions. • Selective oxidation of boride phases observed, forming porous corrosion structures. • Oxide film on secondary phase thicker than on substrate due to enhanced diffusion. • Oxidation sequence followed B .→ Cr → Fe based on Gibbs free energy • Provides insight into BSS degradation mechanism for nuclear storage system safety.

Journal of Materials Research and TechnologyVol. 41
Openalex Percentile: Top 63%
Hydrogen embrittlement and corrosion behaviors in metals
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