主催: The Japan Society of Mechanical Engineers
会議名: 第30回 原子力工学国際会議（ICONE30）
開催日: 2023/05/21 - 2023/05/26
The Lead-cooled Fast Reactors are one of the most promising Gen. IV nuclear systems, currently under development. They can ensure enhanced performances and minimal waste production, but they also have some issues to be addressed. The long-term degradation process caused by Pb corrosion effects, in structural materials facing liquid lead is one of the most critical. The present state of the art showed that commercial stainless steels as AISI 316L and 15-15Ti uncoated can be adopted as structural materials in lead environments below 500 °C, beyond which they start to experience dissolution of constituting alloying elements (e.g., Ni, Cr, Fe).
Current R&D activities on corrosion-resistant materials are pursuing mainly two treads to push temperature threshold beyond 550 - 600 °C: alumina-based coating to be applied on commercial alloys and advanced alloys able to withstand lead corrosion. Among alumina-based coating technologies, Pack Cementation is an attractive option because of its potential good corrosion performance up to 500 °C and capability to coat complex geometries and the already existing availability at an industrial scale. On the other hand, advanced alloys such as the Kanthal FeCrAl have proven excellent corrosion resistance performances at temperatures beyond 600-650 °C.
