Christopher Petersson

Christopher Petersson is a researcher at KTH Royal Institute of Technology, affiliated with the School of Engineering Sciences in Chemistry, Biotechnology and Health within the Surface and Corrosion Science department. His work focuses on material behavior in extreme nuclear reactor environments.

His primary research areas include:

• Liquid Metal Embrittlement (LME) mechanisms
• Corrosion resistance of alumina-forming steels
• High-temperature material testing in liquid lead and LBE
• Microstructure-property relationships in nuclear materials

His experimental work employs advanced techniques like Slow Strain Rate Testing (SSRT) and Erosion Corrosion-rig (ECO) systems.

Petersson's publication analysis (2023-2025) reveals strong focus on metallurgical responses to liquid metal environments, particularly examining how bismuth content affects embrittlement thresholds and how protective alumina scales prevent degradation in next-generation nuclear reactors.

His doctoral dissertation (2024) established foundational knowledge on alumina-forming steels' performance in liquid metal coolants, supervised by Rachel Pettersson, Peter Szakalos, and Mats Lundberg with funding from the Swedish Foundation for Strategic Research (ARC19-0043).

Current research directions include optimizing microstructures for improved LME resistance and evaluating long-term viability of alumina-forming alloys in Generation IV nuclear systems.