The Blanket Design and Fusion Fuel Cycle BDFC Section is entrusted with carrying out indigenous research and development activities on nuclear design & optimization, outer fusion fuel cycle for their application in the Breeding Blanket System of nuclear fusion reactors. The relevant R&D activities to develop technologies associated with hydrogen isotope extraction, removal, recovery, purification, safe storage and analytics of hydrogen isotope related ancillary systems of the fusion blanket are being actively pursued at IPR.
Major Research & Development Activities: Research and development activities undertaken by BDFC section are as follows:
• Nuclear Design and Optimization of Breeding Blanket of Indian fusion reactors.
• Nuclear Design, Activation Analyses, Radiation Damage, Dose Rate and Rad-Waste assessment of Test Blanket Module System in ITER
• Technology development for Q2O and Q2 processing in Helium Gas and Q2 storage (Lab Scale Level):
◦ Atmospheric Molecular Sieve Bed (AMSB), Reduced Metal Bed (RMB),
◦ Cryogenic Molecular Sieve Bed (CMSB)
◦ Hot Metal Bed (HMB), Getter Bed
• Development of Coating technology: Dip coating, Magnetron sputtering
• Hydrogen isotope permeation experiments: structural material
• Development of Hydrogen Isotope Extraction System (HIES) for liquid PbLi.
• Multi-scale modelling of adsorption/absorption process for AMSB, CMSB, getter beds; development of numerical model to study hydrogen isotopes permeation through structural materials; Hydrogen isotope release modelling from lithium ceramics.
• Design of Integrated loop for hydrogen isotope removal & recovery from He purge gas and storage system.
• Tritium residence time and inventory assessment in solid breeder blanket and dynamic tritium inventory analyse in outer fuel cycle components of fusion reactor.