Rate My Professor Arun Bhattacharya

Professor Arunodaya Bhattacharya is the Chair in Fusion Energy at the University of Birmingham's School of Metallurgy and Materials, a role supported by Tokamak Energy since 2024. An internationally recognised expert in fusion and fission energy systems, he specialises in nuclear materials, leading R&D on advanced structural alloys, plasma-facing components, and reactor shielding materials. His research encompasses irradiation damage mechanisms in metals and ceramics, plasma-material interactions, high-temperature mechanical properties including creep and fatigue, and the design of in-vessel fusion components such as breeder blankets and divertors. Professor Bhattacharya is Co-Director of the Fusion Engineering Centre for Doctoral Training, advisor to the UK Fusion Industry Taskforce, and member of the Fusion Skills Council. Fluent in English, French, Hindi, and Bengali, he advocates for global partnerships, innovation, and diversity in STEM and the energy sector.

Before joining Birmingham, Professor Bhattacharya served as Chief Technologist in Irradiated Materials at the UK Atomic Energy Authority, overseeing collaborations with the US Department of Energy and contributing to the STEP fusion pilot plant. Previously, as Staff Scientist at Oak Ridge National Laboratory, he led international studies on irradiation effects in RAFM steels, ODS alloys, tungsten variants, and copper alloys for fusion applications, funded by US DOE, EUROfusion, and international partners. He also gained industrial expertise in iron and steel making at Tata Steel UK. Holding a PhD in Physics (Materials Science) from University of Paris-Saclay (2014), a Master's in Nuclear Energy from the same university (2011), and a BSc (Hons) in Physics from University of Delhi (2008), he has secured over £21 million in research funding. Notable publications include 'Determining the low temperature Cr solubility limit and precipitation mechanisms in Fe-Cr alloys with proton irradiations and thermal aging' (Materials and Design, 2025), 'Temperature and dose effects on dislocation loops in self-ion irradiated high-purity iron' (Acta Materialia, 2025), and 'Development of PWHT-Free, Reduced Activation Creep-Strength Enhanced Bainitic Ferritic Steel for Large-Scale Fusion Reactor Components' (2024). His pioneering work on radiation effects in Fe-Cr alloys underpins structural steel designs for fission and fusion reactors.