I didn't know they were that far along already, i thought most of it was still in the experimental stages, but good on them!
Switching to a mostly thorium cycle would make sense for india since the ore is available domestically and nuclear infrastructure is already in place.
An interesting consequence might be that canada will go for thorium as well, since it also has domestic reserves, and designed the candu (heavy water moderated) reactor which is very suitable to run on U233 breeding more of it from thorium.
A HUGE factor is how easy it is to process Thorium baring ore.
You can chemically separate it.
EXTRACTION AND REFININGtoc
Acidic and alkaline digestion
Although monazite is very stable chemically, it is susceptible to attack by both strong mineral acids (e.g., sulfuric acid, H2SO4) and alkalies (e.g., sodium hydroxide, NaOH). In the acid treatment, finely ground monazite sand is digested at 155 to 230 °C (310 to 445 °F) with highly concentrated (93 percent) H2SO4. This converts both the phosphate and the metal content of the monazite to water-soluble species. The resulting solution is contacted with aqueous ammonia, first precipitating hydrated thorium phosphate as a gelatinous mass and then metathesizing the thorium phosphate to thorium hydroxide. Finally, the crude thorium hydroxide is dissolved in nitric acid to produce a thorium nitrate-containing feed solution suitable for final purification by solvent extraction (see below).
In alkaline digestion, finely ground monazite sand is carefully treated with a concentrated NaOH solution at 138 °C (280 °F) to produce a solid hydroxide product. Any one of several mineral acids is then used to dissolve this solid residue. For example, treatment with hydrochloric acid yields a solution of thorium and rare earth chlorides. Conventionally, thorium is partially separated from the rare earths by addition of NaOH to the acidic chloride solution. The crude thorium hydroxide precipitate is then dissolved in nitric acid for final purification by solvent extraction.
Solvent extraction
For the purification of thorium from residual rare earths and other contaminants present in nitric acid feed solutions, the crude thorium nitrate concentrate is usually contacted with a solution of tributyl phosphate diluted by a suitable hydrocarbon. The resulting organic extract, containing the thorium (and any uranium that may be present), is then contacted countercurrently with a small volume of nitric acid solution in order to remove contaminating rare earths and other metallic impurities to acceptable levels. Finally, the scrubbed tributyl phosphate solution is contacted with a dilute nitric acid solution; this removes, or strips, thorium from the organic solvent into the aqueous solution while retaining uranium (if present) in the organic phase. Thermal concentration of the purified thorium nitrate solution yields a product suitable for the fabrication of gas mantles (see below Chemical compounds). The nitrate can also be calcined to ThO2, which is incorporated into ceramic fuel elements for nuclear reactors or is converted to thorium metal.
Reduction to the metal
Powdered ThO2 can be fluorinated with gaseous hydrogen fluoride (HF), yielding thorium tetrafluoride (ThF4). The metal is obtained by the Spedding process, in which powdered ThF4 is mixed with finely divided calcium (Ca) and a zinc halide (either zinc chloride or zinc fluoride) and placed in a sealed, refractory-lined “bomb.” Upon heating to approximately 650 °C (1,200 °F), an exothermic reaction ensues that reduces the thorium and zinc to metal and produces a slag of calcium chloride or calcium fluoride:
After solidification, the zinc-thorium alloy product is heated above the boiling point of zinc (907 °C, or 1,665 °F) but below the melting temperature of thorium. This evaporates the zinc and leaves a highly purified thorium sponge, which is melted and cast into ingots.
This makes Thorium much cheaper than Uranium/Plutonium that requires centrifugal separation.
Once Thorium is processed you just put it in a bundle and sink it in with the reactor core to transmutate it into U-233 with neutron radiation.
