Major interests of Materials & Chemistry center on the integrity of structural materials in Nuclear Power Plants and facilities.
By aging, all structural materials in NPPs suffer from various degradation phenomena such as corrosion and stress corrosion cracking in reactor coolant conditions and external conditions.
Since such material degradation could affect the safe operation of NPPs, it is very important to identify possible degradation mechanisms for components and structures, to investigate their kinetics, and to evaluate their consequences.
- Dr. Yongsun Yi
- Dr. Andreas Schiffer
- Dr. Akram Al Fantazi
- Dr. Tae Yeon Kim
- Dr. Boohyun An
Mr. Pyungyeon Cho
The team’s research is focused on the following areas:
- Primary water stress corrosion cracking (PWSCC) of austenitic stainless steels
- Integrity of reactor containment building
- Reinforcement corrosion of reactor containment buildings
- Chloride penetration in concrete
- Surface degradation of dry storage systems
- Localized corrosion of structural metals in Chloride environment
- Sara Alhanaee, Yongsun Yi, Andreas Schiffer, ‘Ultimate pressure capacity of nuclear reactor containment buildings under unaged and aged conditions’, Nuclear Engineering and Design 335 (2018) 128–139.
- Boohyun An, Yongsun Yi, Pyungyeon Cho, Taeyeon Kim, Paul Rostron, Akram AlFantazi, ‘Degradation and service life of reactor containment buildings in the Middle East and North Africa region’, International Union of Materials Research Societies (IUMRS), Nice, France in 27-31 May, 2019.