A breeding blanket is an important components of a fusion power reactor that removes heat for electrical production and generates tritium. Testing of prototype fusion blankets (known as Test Blanket Module:TBM) for in-situ tritium breeding and nuclear heat extraction is one of the prime objectives of ITER. Fusion Blanket Division in IPR has its mandate to perform R&D activities and relevant technology development for India’s future fusion reactor blankets. It is working for the development of two different Indian blanket concepts, namely Lead Lithium Ceramic Breeder (LLCB) blanket and Helium Cooled Solid Breeder (HCSB) blanket. Blanket relevant R&D activities were also initiated focusing on (i) blanket neutronic and engineering design, (ii) development of ancillary system technologies related to high temperature Pb-Li liquid metal, hydrogen isotope extraction and removal as well as high pressure and high temperature helium process systems, (iii) development and qualification of blanket materials such as structural material (IN-RAFMS), functional materials (lithium ceramics and Pb-Li as tritium breeder), (iv) development and testing of manufacturing technologies blanket system, (v) blanket safety analysis.