The thrust here is on electricity generation from nuclear reactors, wherein France leads the world.
While India has dismal 4% share.
Now what is wrong here?
Bulgaria produces more electricity percentage wise from nuclear reactors than India.
What is wrong here?
All these are facts, which no body is able to challenge.
Come with per capita numbers.
You just cannot use filtered aspect of data to make your points, if you want to talk you got to see things in totality.
Problem with this kind of mentality is they just try to catch the figure what looks minuscule when compared with others without making any rational logic. And then with that absurd figure build along the illogical reasons.
@
anant_s
Please note that thermal efficiency of any Nuclear power plant be it a 1600 MWe (EPR) or 220 MWe (IPHWR) is in narrow range of 28-32% only meaning only 28-32% of total heat generated by fission is actually converted to electricity.
Quote:
Supercritical water-cooled reactors (SCWRs) are promising advanced nuclear systems because of their high thermal efficiency (i.e., about 45% vs. about 33% efficiency for current LWRs) and considerable plant simplification.
India does not have advanced reactors, its reactors are of second generation, hence you will get only so much.
Majority of worlds reactors are of Second Generation or first generation, there is no commercial gen IV reactor anywhere and only handful gen III?
Can you quote any country which has production ready SCWR's ?
SCWR's are concept in which Russia leads and they have a research purpose reactors.
Further more world is moving over from Thermal reactors to Fast reactors because they make less nuclear waste and can produce more resources then what they consume and SFR and LFR is the area where works are been done.
Specifically SFR with Thorium cycle is what even China is working upon.
Fast reactors can have a higher power density and are more compact than thermal reactors, thereby saving on construction materials. Crucially, because fast reactors operate in a more energetic neutron spectrum, they can more readily transform the U-238 in the fuel into plutonium through the capture of fast moving neutrons. When the fuel is discharged from the reactor, it can be reprocessed to extract the plutonium, which is then recycled in fresh fuel. Fast reactors can even be designed to produce, or breed, more plutonium from U-238 than they consume in the chain reaction. In such configurations they are called Fast Breeder Reactors. They therefore offer the possibility to develop a true 'closed fuel cycle', involving repeated recycling though reprocessing of discharged spent fuel in order to remove fissile material. On the counter part the SCWR's are thermal reactor, which are operating using an 'open fuel cycle', in which the nuclear fuel is kept in the reactor for one cycle and once discharged is considered as waste. The main advantage of a closed fuel cycle using Fast Breeder Reactors is that it enables much more energy to be extracted from the original uranium, of which the isotope U-238 makes up 99.3%. By also exploiting the U-238, instead of just the U-235, these reactors can produce more than 50 times more energy from the same quantity of natural uranium.
And for your knowledge India is already building PFBR based on SFR (Gen IV) in Kalpakkam and will go critical in Jan 2017 And out of handfull gen III reactors world wide, India has its own share in that too.
I would suggest you to go back to basics and read more about Nuclear World, rather then making half learned and half baked guesses.
chill buddy
