Operation and Maintenance Group (ROMG). KAMINI 30 kWt reactor, starred in 1996, uses Uranium 233 fuel transformed from Thorium in the FBTR. Prototype Fast Breeder Reactor, a 500MWe fast breeder reactor using Mixed Oxide (Uranium oxide + Plutonium oxide) fuel based on the Sodium-cooled fast reactor design. In addition, the Research Facility also built the 100MWe reactor for India's first nuclear submarine the Arihant class submarine project and operated it on land for testing purposes since it attained criticality in December 2004. The submarine launched on 26 July 2009 has this reactor. Reprocessing plant The Kalpakkam Atomic Reprocessing Plant [KARP] facility has been estimated to have a capacity to reprocess 100 tonnes of spent fuel plutonium per annum.it incorporates a number of innovative features such as hybrid maintenance concept in hot cells using servo-manipulators and engineered provisions for extending the life of the plant. This plant will cater to the needs of reprocessing fuels from MAPS as well as FBTR. It has mastered the technology of reprocessing highly irradiated mixed carbide fuel for the first time in the world. Fast reactor fuel reprocessing at IGCAR Reprocessing Development Laboratory was designed in early seventies and the commissioning of inactive facilities was carried out in 1976. The plutonium handling facilities were cleared for operation in 1980. The reprocessing of irradiated thorium rods which was carried out during the period 1989 to 1992 in the concrete shielded cells, was the first major radioactive operation. The U-233 recovered during the operation was used in fabricating the fuel for the KAlpakkam MINI reactor (KAMINI). U-233 was also useful for the fuel development programme for carrying out the Prototype Fast Breeder Reactor test fuel irradiation experiments in Fast Breeder Test Reactor. Apart from this, the operation aided in validating the equipment and design of system as well as the manpower training. Later a hot cell facility for reprocessing of Fast Breeder Test Reactor fuel was conceived which had the necessary features for delivering the product with all the uncertainties in the dissolution of irradiated fuel and process flowsheet. Added to this was the need for the deployment of the yet to be proven designs of centrifuge and centrifugal extractors without which the success of the PUREX process for fast reactor fuel reprocessing would be doubtful. With these minimal inputs, the hot cell facility, Lead Mini Cell (LMC) was created, which was later rechristened as CORAL (COmpact