High-Temperature Corrosion Behavior of 12Cr18Ni10Ti Grade Austenitic Stainless Steel Under Chlorination Conditions
Baklanova Y. Sapatayev Y. Samarkhanov K.
September 2025Multidisciplinary Digital Publishing Institute (MDPI)
Metals
2025#15Issue 9
Ensuring the long-term integrity of structural materials in extreme environments is a critical challenge in the design of equipment for nuclear fuel cycle operations. In particular, the durability of materials exposed to high temperatures and chemically aggressive environments during the processing of irradiated reactor components remains a key concern. This study investigates the high-temperature corrosion behavior of 12Cr18Ni10Ti austenitic stainless steel in the reaction chamber of a beryllium chlorination plant developed for recycling irradiated beryllium reflectors from the JMTR (Japan Materials Testing Reactor). The chlorination process was conducted at temperatures ranging from 500 °C to 1000 °C in a chlorine-rich atmosphere. Post-operation analysis of steel samples extracted from the chamber revealed that uniform wall thinning was the predominant degradation mechanism. However, in high-temperature regions near the heating element, localized forms of damage, specifically pitting and intergranular corrosion, were detected, indicating that thermal stresses exacerbated localized attack. These findings contribute to the assessment of the service life of structural components under extreme conditions and offer practical guidance for material selection and design optimization in high-temperature chlorination systems used in nuclear applications.
austenitic stainless steel , beryllium chlorination , high-temperature corrosion , irradiated beryllium reflectors , JMTR nuclear reactor , pitting and intergranular corrosion
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Institute of Atomic Energy, Branch National Nuclear Center of the Republic of Kazakhstan, Kurchatov, 071100, Kazakhstan
Institute of Atomic Energy
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