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

材料科学 乏核燃料 中子毒 溶解 冶金 腐蚀 奥氏体 硼 奥氏体不锈钢 微观结构 氧化物 赤铁矿 中子俘获 碳化物 相(物质) 碳化硼 核临界安全 中子通量 溶解度 中子 核燃料
作者
Daehyeon Park,Yunju Lee,Junhyuk Ham,Seung Chang Yoo,Ki-Young Kim,Dong-Hee Lee,Yongdeog Kim,Ji Hyun Kim
出处
期刊:Journal of materials research and technology [Elsevier BV]
卷期号:41: 344-362
标识
DOI:10.1016/j.jmrt.2025.12.045
摘要

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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