RD-EMMA-AMALIA – Dr. Agata Sotniczuk
Project: 2026-1-RD-EMMA-AMALIA
Title: Prediction of degradation phenomena in future (SCWR) and current (PWR) nuclear power plants: behaviour of modern HEA and classic 316L nuclear grade steel
Abstract: Progressing demand for energy enforces twofold development: (i) extension the lifetime and safety of currently exploited Pressurized Water Reactors (PWR) which requires further understanding of nuclear materials behaviour, (ii) moving closer GEN IV such as Supercritical Water-Cooled Reactors (SCWR) to the practical implementation which requires development and testing new materials. This project concerns both of these issues as it offers non-standard SCC testing of conventional 316L steel in PWR water as well as electrochemistry tests of novel high entropy alloy in SCW. Expected outcome can be summarized as follows: (i) to understand degradation phenomena in PWR and SCWR conditions, (ii) to contribute to EU standardization in the nuclear field by filling existing gaps in SCC data, (iii) to increase the knowledge related to corrosion behaviour of novel HEA alloys in SCW conditions, which can finally contribute to propose alloy modifications to maximize its corrosion resistance
Keywords: Stress corrosion cracking, PWRs, SCWRs, in situ EIS, High entropy alloys




