[en] Indian Fast Reactor Program is entering into an important phase. Fast Breeder Test Reactor (FBTR) at Kalpakkam, after it was made critical with a small core in October 1985, was operated at low power levels until the mid 1992. Various tests were performed and the tests were completed with the demonstration that thermal power up to 1 MWt could be safely removed solely by natural convection in the steam generator casing air flow path. Theoretical studies performed using simplified thermal and hydraulic models of the FBTR reactor system satisfactorily predicted the natural circulation heat removal capability of the reactor system. It was indeed predicted that natural convection in primary and secondary sodium circuit could also be depended upon for heat removal while keeping all the temperatures within limits. 1 MWt of thermal power being the short term post shutdown fission product decay power level for a full 40 MWth core, the above test has convincingly demonstrated that natural convection mode of decay heat removal can be relied upon. Further theoretical studies has shown that, with a primary flow halving time of 17s, even an unprotected (or without reactor trip) total power failure situation from full power operation can be sustained with reactor power reducing gradually to decay power levels because of the negative reactivity feedback and with all the temperatures well within the limits. This paper brings out the details of the tests performed and the results of the various theoretical predictions. Presently FBTR is poised to be operated up to a power level of 10 MWt. Simultaneously preliminary design of Prototype Fast Breeder Reactor (PFBR), a 500 MWe, 1200 MWt LMFBR has been completed. Presently it is in a detailed design phase. In this overview, the various options available for post shutdown decay heat removal in PFBR, the argument for selection of the normal heat transport path and Safety Grade Decay Heat Removal System (SGDHRS) as two diverse paths of heat removal, methodology adopted for preliminary sizing of the SGDHRS and the analysis performed to assess the adequacy of the sizing are brought out. (author)