Thank for the nice writeup. I thought India was building a full scale thorium reactor after running a breeder for about 10 years.
since you seems to know lots about this field, can you explain what the Indians have been trying until now. is the fast breeder the same as irradiating the plutonium?
The Indians are planning to go to thorium in a 3 phase process.
1. Use of relatively conventional uranium-fuelled heavy-water reactors. These are designed to produce a modest amount of plutonium as a side-effect of generating power.
While conventional PWR/BWR reactors could be used for this - the Indians have preferred to go with their home-grown heavy-water designs, which have a number of advantages, not least requiring much less very expensive and very high-tech uranium enrichment, and they can be tuned to produce decent quantities of plutonium.
2. Once a reasonable stock of plutonium is available (probably after about 10 years), fast breeder reactors (FBRs) are planned for construction. These would probably be of a sodium-cooled design, as have been used elsewhere. These would be fuelled by plutonium. Historically, these were designed to produce large amounts of plutonium, in order to maximize weapons production, but can be modified to produce fuel from thorium (but are not a good choice for burning the subsequent fuel).
There are two options:
Use the FBRs to accelerate plutonium production, then switch the reactors to irradiating thorium, or simply start with thorium irradiation (assuming enough plutonium is available)
At the same time, plants capable of reprocessing the irradiated thorium to extract the uranium 233 fuel (this is not natural or enriched uranium and has markedly different properties).
3. Finally, once enough U233 fuel has been acquired, construct some advanced thorium 'thermal breeder' reactors. The Indians have proposed a design that is sufficiently similar to conventional PWRs/BWRs, that it should be constructable and maintainable, even if it's not particularly efficient, and its operation is considerably more complex than a conventional PWR/BWR.
The thermal breeders would burn U233 from thorium fuel, while producing power, and simultaneously irradiating thorium. Ideally, the reactors should produce as much U233 fuel as they burn (or more, if you want to expand the number of reactors). If they don't, they will need constant top-ups of fuel from the stage 1 and 2 reactors.