1. Fast breeder reactors are thus termed because they are based on energetic (fast) neutrons and because they produce (breed) more fissile material than they consume
2. Bhabha, H. J. and Prasad, N. B. “A Study of the Contribution of Atomic Energy to a Power Programme in India”. paper presented at the Second United Nations International Conference on the Peaceful Uses of Atomic Energy. Geneva. pp.89–101. R. Chidambaram and C. Ganguly, “Plutonium and Thorium in the Indian Nuclear Programme,”Current Science70(1) (1996): 21–35. While uranium can be used to fuel reactors, thorium cannot fission at low energies and so cannot fuel a reactor directly. But it can be converted to the isotope uranium-233 through neutron absorption followed by radioactive decay. Uranium-233, in turn, is fissile and can fuel reactors
3. Suresh, K. V. Kumar. 2002. “Fast Breeder Test Reactor. 15 Years of Operating Experience”. paper presented at the Technical Meeting on Operational and Decommissioning Experience with Fast Reactors. March11–152002, Cadarache. pp.15–27.