Selvakumar Jayaparakasam
Also known as: Selva
Bhabha Atomic Research Centre, Homi Bhabha National Institute, Loyola College, Annamalai University, St. Joseph's College
About
Dr. Jayaprakasam Selvakumar is an Indian scientist specializing in nuclear and radiochemistry. He completed his Ph.D. in Chemistry in 2010 from Loyola College, affiliated with the University of Madras. After his doctoral studies, he was awarded the Indian Prodigious KSKRA Fellowship at Bhabha Atomic Research Centre under the Department of Atomic Energy. In 2011, he joined BARC as a Scientific Officer, where he carries out advanced research in areas central to both materials chemistry and nuclear fuel cycle technologies.
Dr. Selvakumar’s research interests encompass the chemical science of chemical vapor deposition (CVD) precursors and thin-film deposition, detailed thermal studies, and the development and optimization of processes for spent nuclear fuel reprocessing. His work further includes liquid–liquid extraction and extraction chromatography techniques, formulation of borosilicate glasses for immobilization of radioactive wastes, and the treatment, vitrification, and management of high-level radioactive liquid wastes — all critical to sustainable and safe nuclear waste management practices. His publications in prestigious scientific journals reflect contributions to the fields of nuclear waste treatment and advanced material applications in radiochemical separations.
Employment
-
Bhabha Atomic Research Centre Scientific Officer2013 - Present
-
Bhabha Atomic Research Centre Scientific Officer2010 - 2013
-
Homi Bhabha National Institute Associate Professor
Education
-
Loyola College PhD2005 - 2010
-
Loyola College MSc? - 2005
-
Annamalai University BEd? - 2003
-
St. Joseph's College BSc? - 2000
Projects & Funding
Projects & funding information is unavailable.
Publications (103)
- Soft N-donor and CHON ligands for minor actinide separation: From 4f/5f bonding principles to process design Save
- Carbon Nano Materials (CNMs) for Applications in Nuclear Fuel Cycles Save
- Optimized Synthesis and Evaluation of Composite Beads for Antimony Removal from Acidic Nuclear Reprocessing Effluent Save
- Next-Generation Emerging Nanomaterials: Transforming the Nuclear Fuel Cycle Save
- Process Intensification in Spent Nuclear Fuel Reprocessing: A Critical Review of Global Technologies Save
- Influence of CeO2 addition on solubility and glass network structure of the vitrified Na2O-TiO2-Fe2O3 -B2O3-SiO2 glass system Save
- Advanced vitrification and selective partitioning strategies for sustainable high-level radioactive liquid waste management Save
- Characterisation of Cladding Hull Waste from Reprocessing Plant Save
- Recovery of Technetium-99 from Iron Oxide based Radioactive Sludge Save
- Spectral and Thermal Characterization of Neutral and Acidic Extractants for High-Level Liquid Waste Treatment Save