Development of alternate solvents for nuclear fuel reprocessing e.g. Development of TiAP based solvent for fast reactor fuel reprocessing; Synthesis of new solvents, extractants, metal organic frameworks for extraction / separation of actinides and lanthanides
High performance separation studies on lanthanides and actinides; burn-up measurements; Solubility of ligands in SCFs; Supercritical fluid extraction of actinides from various matrices.
Understanding third phase formation phenomenon during solvent extraction of actinides and other metal ions- insights and quantification using Small Angle Neutron Scattering (SANS) and Small Angle X-ray Scattering (SAXS) techniques.
Computational studies on actinide complexes.
Development of lab-scale remote handling facility for the fabrication of sphere-pac nuclear fuel using sol-gel process.
Glove box facility for the measurement of solidus and liquidus temperature of fuel materials using spot technique.
Studies on gel combustion synthesis and development of flow sheet for the preparation of ceramic oxide materials with tailor made morphology.
Measurement of thermophysical and thermochemical properties of nuclear fuel and fission products.
Fabrication of sphere-pac test fuel pins for test irradiation in FBTR.
R&D on Lanthanide - Actinide Separations.
Development of mixer-settler solvent extraction process Elemental analysis of radioactive materials using ICP-OES
Material characterization using X-ray diffraction
Laser Ablation based Mass Spectrometry (ICP-MS, TOF-MS, MALDI-MS) for characterisation of materials
Hotcell facility for Irradiated Fuel Studies, for Post-Irradiation Examination of FBTR Fuel, lab-scale separation of Minor Actinides from dissolver solutions
Establishing Minicell facility for handling irradiated Fuels.
Characterization of Nuclear Materials using isotopic abundance with TIMS & high temperature vaporization behaviour of nuclear materials using KEMS