Experience with proposed molten fuel salt and blanket salt for Indian molten salt breeder reactor

India's three-stage nuclear power program and associated technologies are based on the optimum utilization of the indigenous nuclear resources Uranium and Thorium. Development of technologies pertaining to utilization of thorium is important for long term energy security of the country. Thorium offers number of physics and engineering advantages for use in reactors. In this respect use of thorium in both solid fueled and liquid fueled reactors can be considered. While it is possible to breed ²³³U from thorium in conventional reactor design (i.e. with solid fueled), thorium usage in conventional reactors, suffers from one disadvantage: ²³³Pa is an intermediate isotope in the chain of nuclear reaction with Thorium. The conversion of ²³³Pa to ²³³U is possible only by beta decay. However, in a reactor core ²³³Pa is always subjected to presence of fission neutrons. With solid fuels, ²³³Pa may be lost through parasitic capture of thermal neutron. This can be avoided if the fuel is in liquid form so that ²³³Pa is separated out as soon as it is produced, and allowed to decay to ²³³U out of core