Prof S Ningshen, JSPS Fellow, FIIM, FAMPP, FRSC

About

Dr S. Ningshen is currently the Head of the Corrosion Science & Technology Division at the Indira Gandhi Centre for Atomic Research, Kalpakkam, and a Professor at the Homi Bhabha National Institute. Dr Ningshen has made significant research contributions in the development of advanced structural materials and coatings technology for Fast Breeder Reactors, associated spent nuclear fuel reprocessing plants, and other allied industries. Also, contributed significantly to fireside corrosion and steam oxidation of Indian Advanced Ultra Supercritical (AUSC) technology materials and materials for hydrogen production.

Employment

• Hokkaido University JSPS Postdoctoral Fellow
  2011 - 2013
• Leibniz-Institut für Festkörper- und Werkstoffforschung Dresden eV Visiting Scientist
  1999 - 2000
• Indira Gandhi Centre for Atomic Research

Education

• University of Madras PhD (Chemistry-Metallurgy), Interdisciplinary

Projects & Funding

Projects & funding information is unavailable.

Publications (74)

• Enhanced corrosion resistance of (10–18Cr) Al-ODS steels in spent nuclear fuel reprocessing nitric acid environment: Impact of renewal and non-renewal conditions
  Journal of Nuclear Materials 2026 DOI: 10.1016/j.jnucmat.2025.156355
  +Save
• Fireside corrosion of SS304HCu alloy for advanced ultra super critical coal-fired boiler plants
  Fuel 2026 DOI: 10.1016/j.fuel.2026.139623
  +Save
• Oxidation kinetics of pyrolytic graphite in combined air and steam environment for pyrochemical reprocessing application
  Journal of Nuclear Materials 2026 DOI: 10.1016/j.jnucmat.2025.156226
  +Save
• High temperature corrosion evaluation of SS 316 L in CeCl3-LiCl-KCl molten salt using electrochemical techniques
  Corrosion Science 2026 DOI: 10.1016/j.corsci.2025.113483
  +Save
• Comparison of the corrosion behaviour of 10Cr and 17Cr Al added ODS steel in simulated reprocessing nitric acid medium
  Journal of Nuclear Materials 2024 DOI: 10.1016/j.jnucmat.2024.155258
  +Save
• Oxidation Mechanism and Surface Characterization of Pyrolytic Graphite in Simulated Air for Pyrochemical Reprocessing Application
  Journal of Nuclear Materials 2024 DOI: 10.1016/j.jnucmat.2024.154996
  +Save
• Corrosion behaviour of P-91 steel and type 316 LN stainless steel with and without a ceramic coating in the lead with oxygen at 550°C
  Journal of Nuclear Materials 2023 DOI: 10.1016/j.jnucmat.2022.154181
  +Save
• Localised corrosion susceptibility of nitrogen-containing type 316LN stainless steel in cold work and thermally aged conditions
  Corrosion Engineering, Science and Technology 2022 DOI: 10.1080/1478422X.2022.2126407
  +Save
• Vacuum brazing of copper and SS316L using Ni–P eutectic alloy filler for nuclear applications
  Welding in the World 2022 DOI: 10.1007/s40194-022-01374-6
  +Save
• Synthesis and characterization of chemical vapour deposited pyrolytic graphite
  Thin Solid Films 2022 DOI: 10.1016/j.tsf.2022.139180
  +Save