Nuclear Energy in India : Updates

Union Minister Dr.Jitendra Singh says, the installed nuclear power capacity grew from 4780 MW to 6780 MW, an increase of over 40% in the last seven years​

Union Minister of State (Independent Charge) Science & Technology; Minister of State (Independent Charge) Earth Sciences; MoS PMO, Personnel, Public Grievances, Pensions, Atomic Energy and Space, Dr Jitendra Singh said, in the last seven years, the installed nuclear power capacity grew from 4780 MW to 6780 MW, an increase of over 40%.


In a written reply to a question in the Lok Sabha today, DrJitendra Singh informed that India is pursuing an indigenous three-stage nuclear power programme to provide the country long term energy security in a sustainable manner. In addition, Light Water Reactors based on foreign cooperation are also being set up as additional facilities to provide the country clean electricity.


In a separate question on Nuclear Power augmentation, DrJitendra Singh informed that Kudankulam Nuclear Power Plant KKNPP 3&4 (2X1000 MW) project implemented by Nuclear Power Corporation of India Limited (NPCIL) has achieved a physical progress of 54.96% as of November, 2021.


He said, the units of KKNPP 3&4 project are expected to be completed by March, 2023 & November, 2023 respectively. Fast Reactor Fuel Cycle Facility (FRFCF) project is presently being executed by Nuclear Recycle Board, Bhabha Atomic Research Centre, Department of Atomic Energy. Financial progress of the project as on 30th November 2021 is 32% and the Project is expected to be completed by December 2027.
 
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Screenshot_20211217-132348~2.png
 
Department of Atomic Energy

Union Minister Dr. Jitendra Singh says, Government has accorded approval for setting up the largest nuclear power generating site at Jaitapur in Maharashtra with a total capacity of 9900 MW

Minister says, presently techno - commercial discussions to arrive at the project proposal with M/s. EDF, France are in progress


Posted On: 16 DEC 2021 3:37PM by PIB Delhi​

Union Minister of State (Independent Charge) Science & Technology; Minister of State (Independent Charge) Earth Sciences; MoS PMO, Personnel, Public Grievances, Pensions, Atomic Energy and Space, Dr Jitendra Singh said, the Government has accorded ‘In-Principle’ approval of the site at Jaitapur in Maharashtra for setting up 6 nuclear power reactors of 1650 MW each in technical cooperation with France which would make it the largest nuclear power generating site with a total capacity of 9900 MW.

In a written reply to a question in the Rajya Sabha today, Dr. Jitendra Singh informed that the project is proposed to be setup at Jaitapur site in Ratnagiri district of Maharashtra. He said, presently techno-commercial discussions to arrive at the project proposal with M/s. EDF, France are in progress.

In a separate written reply to a question in the Rajya Sabha on nuclear power capacity, Dr. Jitendra Singh informed that the present installed nuclear power capacity in the country is 6780 MW and the share of nuclear power in the total electricity generation in the country is about 3.1% in the year 2020-21.

The Minister said that Nuclear power is clean and environment friendly, apart from having a huge potential to ensure the country’s long term energy security on a sustainable basis. The nuclear power plants have so far generated about 755 billion units of electricity saving about 650 million tons of CO2 emission.

Dr. Jitendra Singh said that the net zero targets are expected to be met through a combination of various clean energy sources including nuclear power. In this context, the present nuclear power capacity of 6780 MW is planned to be increased to 22480 MW by 2031 on progressive completion of projects under construction and accorded sanction. More nuclear power reactors are planned in future.

The Government has taken several measures to enhance the generation from nuclear power plants in the country. These include:
  1. Accord of administrative approval and financial sanction of - ten (10) indigenous 700 MW Pressurized Heavy Water Reactors (PHWRs) to be set up in fleet mode with provision of equity support.
  2. Resolution of issues related to Civil Liability for Nuclear Damage (CLND) Act & Creation of Indian Nuclear Insurance Pool (INIP).
  3. Amendment of the Atomic Energy Act to enable Joint Ventures of Public Sector Companies to set up nuclear power projects.

 
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Haven't done a long post in a while. Allow me.....

India' 3 stage nuclear power program has been the object of my fascination for long. A program born in the early 1950s that would reach its final stage of fruition about a 100 years later. Within those 100 years the country needs invest 10s of billions in R&D to develop some incredibly complex & niche technologies most of which aren't commercially available & invest 100s of billions to build the nuclear plants. Oh and the research institutions working on this have been under sanctions for many many years. They are cut off from the rest of the world & have to continue working in isolation for most of those 100 years. Add these problems with India's non-existent engineering, manufacturing & technological base in the 50s & this program is easily one of the most difficult ones we've ever undertaken.

The reason for taking up this program is well known. India's reserves of Uranium & Plutonium are limited. Much of our U & Pu reserve is/will be used for military purposes, from nuclear warheads to marine nuclear reactors. Our thorium reserves are huge, ~25% of global reserves of Th are in India. The Indian nuclear establishment estimates that the country could produce 500+ GWe for at least four centuries using just the country's economically extractable thorium reserves. For comparison, India' current installed electricity generation capacity is 388 GWe. It would be shame to have so much Thorium & do nothing with it.

I am sure you already know this by now. But still lets go over the basics one more time. The 3 stages of the program are as follows:

1. Stage 1: Natural Uranium undergoes fission in a Pressurized Heavy Water Reactor (PHWR) to give us electricity. Plutonium & depleted Uranium are the by products. The depleted Uranium will be converted into Plutonium-239 via nuclear transmutation during reprocessing. Some other byproducts produced in small quantities & vitrified & sent to storage.

2. Stage 2: Pu-239 from Stage 1 is reprocessed & mixed with natural Thorium to produce a Mixed Oxide Fuel (MOX). MOX undergoes fission in a Fast Breeder Reactor (FBR) to produce electricity. Plutonium & Uranium-233 are the by products. The U-233 will be used in the 3rd stage where as the Plutonium will be reprocessed & used the 2nd stage again. The FBRs will also produce small quantities of Curium (Cm), Americium (Am) & Neptunium (Np). All 3 of those will be converted to Pu & fed into the 3rd stage again.

3. Stage 3: The final stage will use a MOX prepared from U-233 obtained from Stage-2 & natural Thorium. The fission will take place in an Advanced Heavy Water Reactor (AHWR) producing electricity & U-233 as byproduct. The byproduct can be used to make more MOX to feed the AHWRs.
Screenshot (825).png

Two types of reactor technologies were available to us for the Stage 1; Light Water Reactors (LWR) & Pressurized Heavy Water Reactors (PHWR). LWRs use enriched Uranium or MOX as fuel & are cooled by light water where as PHWR use natural Uranium & are cooled by heavy water. The difference between Light & Heavy waters is the isotope of hydrogen in the water, the former has protium & the later has deuterium.

Adopting any of the 2 reactor types brought its own technological challenges as India then could neither enrich Uranium nor produce heavy water. This was a very critical choice, thankfully we made the right choice. PHWRs were chosen as the way ahead. The BARC correctly estimated that developing & deploying large scale Uranium enrichment facilities would take more time & money than developing & deploying large scale heavy water production facilities.

Also there was the military angle. Heavy water in PHWRs occasionally get bombarded by neutrons. This causes some of the deuterium in heavy water to convert to tritium. Tritium is radioactive & needs to be removed from the heavy water reservoirs. BARC developed a method by the name Liquid Phase Catalytic Exchange (LPCE) for the removal of Tritium. After the removal Tritium is stockpiled & later used in making thermonuclear weapons. Not a lot is known about the LPCE process, for obvious reasons it is shrouded in secrecy. Of course that's not the only way of producing Tritium nor is it the most efficient way. It is however the cheapest way. Some decades back we started producing Tritium by irradiating Lithium-6 directly in the IPHWR family of reactors.

Somewhere along the way we developed our own enrichment technology & deployed in en masse. Enrichment tech was developed for preparing fuel for the fission & boosted fission bombs. Interesting how military and civilian needs feed each other. The deployment of enrichment facilities brought the previously discarded LWRs back into the picture. With the signing of the India-US civil nuclear deal foreign LWR reactor tech & more importantly nuclear fuel became available.

We signed deals with Russia & then France for LWR & life time supply of nuclear fuel for these reactors. There was a deal in the making with the Americans too, though it might be dead by now. We've also signed deals to import nuclear fuel from Kazakhstan, Uzbekistan, Australia etc. Now the 1st & 2nd stage of the program looks like this:
Screenshot (826).png

The idea is to use foreign LWR to generate electricity, thus freeing up local Uranium & Plutonium for you know what. The PHWRs though are going to be our own design & fueled by our own Uranium. Have to keep those PHWRs away from IAEA safeguards if we want to keep producing & stockpiling Tritium. We are also in the process of converting the Arihant class SSBN's CLWR-B1 reactor into a full scale 900 MWe civilian LWR reactor named IPWR-900.

The IPHWR family of reactors started off as direct derivatives of the CANDU reactors. Eventually larger, more reactors with better safety parameters were developed. The original CANDU were barely Generation II safety standard compliant. Where as the IPHWR-700, the backbone of our nuclear reactor fleet, is Generation III+ compliant. Can the IPHWR family still be considered CANDU derivatives ? I'll leave that to your judgement.

In 2016-2017 the following was the projection of the installed nuclear power generation capacity:
Screenshot (827).png

With the pandemic, budgetary problems & the stellar rise of thermal/hydro/solar/wind power installation in the country expect the timelines shown above to be pushed back by a few years at least.

Our current installed nuclear power generation capacity is 6.78 GWe. In the post above you can see we will reach 22.48 GWe by 2031.

The upper limit of installed capacity from the IPHWR family & various research reactors using domestic Uranium is ~10 GWe. 6 GWe will come from the 6 units of the Russian VVER-1000 reactors in Kudankulam & 9.9 GWe from the 6 units of French EPR at Jaitapur. Total power from imported reactors is 15.9 GWe. Therefore total installed power capacity from Stage 1 from both domestic & imported reactors is ~25.9 GWe.

If by 2031 we will have 22.48 GWe, then we should be able to install the balance ~3 GWe & reach the maximum capacity limit of the Stage 1 by 2035. From then on there will be no further increase in Stage 1 reactors as shown in the graph above.

As we are implementing the Stage 1 we are also entering early implementation of the Stage 2 of the program with the Prototype Fast Breeder Reactor (PFBR). The physical testing phase of the Stage 2 began in October 1985 when the 40 MWt Fast Breeder Test Reactor (FBTR) attained criticality. The reactor ran into problems soon & had to be shut down in 1987 & then again in 1989. By the end of the 90s, IGCAR had a good understanding of the reactor & it would run at full capacity for the next 2 decades.

Based on the experience of the FBTR the Prototype Fast Breeder Reactor (PFBR) started in the 90s. PFBR is a 500 MWe reactor that would provide validation for the full sized FBR-600. FBR-600 or Fast Breeder Reactor-600 is a 600 MWe scaled up version of the PFBR. The FBR-600 will be the main reactor for the Stage 2 of the program. Construction was supposed to begin in 2007 in Kalpakkam, but some design changes caused inordinate delays.

Design of the PFBR:
1639830471037.png


Some construction images:

Here you can see the reactor vessel being lifted by a crane:
1639833851582.png

Vessel being inserted into the designated spot. The vessel was manufactured by L&T's Nuclear Engineering division:
1639830797472.png

Mounting equipment on top of the vessel:
1639833827301.png

The PFBR facility nearly complete:
1639830402856.png

In the winter session of the Parliament in 2020 responding to a question in the Lok Sabha Dr. Jitendra Singh said the PFBR will be operational by December of 2021.
1639830528695.png

We are now in December 2021. When asked the same question Dr. Jitendra Singh responded the commissioning date has been delayed to October 2022. Almost a year from now. 😑

The advantage of breeder reactors is that they produce more fuel than they consume. The PFBR/FBR-600 will produce Plutonium & Uranium, this surplus Plutonium bred in each FBR can be used to set up more such reactors. Thus the problem of lack of Uranium & Plutonium which stops the growth of nuclear power in India is greatly reduced but not completely gone. You can completely remove that problem once you can bring in the country's Thorium into play.

It is estimated that once India's nuclear power installed capacity reaches 50 GWe we will have enough Plutonium & Uranium to bring the 3rd stage online. 25 GWe is supposed to come from Stage 1, so we roughly need another 25 GWe from Stage 2 to start making Stage 3 reactors. We will need ~40 breeder reactors of 600 MWe capacity to get to 25 GWe. That's a lot of reactors. Maybe we should make a 1 GWe FBR.

That's all for today. Will write about the various types of reactors being studied for the Stage 3 in a post tomorrow....
 
Haven't done a long post in a while. Allow me.....

India' 3 stage nuclear power program has been the object of my fascination for long. A program born in the early 1950s that would reach its final stage of fruition about a 100 years later. Within those 100 years the country needs invest 10s of billions in R&D to develop some incredibly complex & niche technologies most of which aren't commercially available & invest 100s of billions to build the nuclear plants. Oh and the research institutions working on this have been under sanctions for many many years. They are cut off from the rest of the world & have to continue working in isolation for most of those 100 years. Add these problems with India's non-existent engineering, manufacturing & technological base in the 50s & this program is easily one of the most difficult ones we've ever undertaken.

The reason for taking up this program is well known. India's reserves of Uranium & Plutonium are limited. Much of our U & Pu reserve is/will be used for military purposes, from nuclear warheads to marine nuclear reactors. Our thorium reserves are huge, ~25% of global reserves of Th are in India. The Indian nuclear establishment estimates that the country could produce 500+ GWe for at least four centuries using just the country's economically extractable thorium reserves. For comparison, India' current installed electricity generation capacity is 388 GWe. It would be shame to have so much Thorium & do nothing with it.

I am sure you already know this by now. But still lets go over the basics one more time. The 3 stages of the program are as follows:

1. Stage 1: Natural Uranium undergoes fission in a Pressurized Heavy Water Reactor (PHWR) to give us electricity. Plutonium & depleted Uranium are the by products. The depleted Uranium will be converted into Plutonium-239 via nuclear transmutation during reprocessing. Some other byproducts produced in small quantities & vitrified & sent to storage.

2. Stage 2: Pu-239 from Stage 1 is reprocessed & mixed with natural Thorium to produce a Mixed Oxide Fuel (MOX). MOX undergoes fission in a Fast Breeder Reactor (FBR) to produce electricity. Plutonium & Uranium-233 are the by products. The U-233 will be used in the 3rd stage where as the Plutonium will be reprocessed & used the 2nd stage again. The FBRs will also produce small quantities of Curium (Cm), Americium (Am) & Neptunium (Np). All 3 of those will be converted to Pu & fed into the 3rd stage again.

3. Stage 3: The final stage will use a MOX prepared from U-233 obtained from Stage-2 & natural Thorium. The fission will take place in an Advanced Heavy Water Reactor (AHWR) producing electricity & U-233 as byproduct. The byproduct can be used to make more MOX to feed the AHWRs.
View attachment 22089
Two types of reactor technologies were available to us for the Stage 1; Light Water Reactors (LWR) & Pressurized Heavy Water Reactors (PHWR). LWRs use enriched Uranium or MOX as fuel & are cooled by light water where as PHWR use natural Uranium & are cooled by heavy water. The difference between Light & Heavy waters is the isotope of hydrogen in the water, the former has protium & the later has deuterium.

Adopting any of the 2 reactor types brought its own technological challenges as India then could neither enrich Uranium nor produce heavy water. This was a very critical choice, thankfully we made the right choice. PHWRs were chosen as the way ahead. The BARC correctly estimated that developing & deploying large scale Uranium enrichment facilities would take more time & money than developing & deploying large scale heavy water production facilities.

Also there was the military angle. Heavy water in PHWRs occasionally get bombarded by neutrons. This causes some of the deuterium in heavy water to convert to tritium. Tritium is radioactive & needs to be removed from the heavy water reservoirs. BARC developed a method by the name Liquid Phase Catalytic Exchange (LPCE) for the removal of Tritium. After the removal Tritium is stockpiled & later used in making thermonuclear weapons. Not a lot is known about the LPCE process, for obvious reasons it is shrouded in secrecy. Of course that's not the only way of producing Tritium nor is it the most efficient way. It is however the cheapest way. Some decades back we started producing Tritium by irradiating Lithium-6 directly in the IPHWR family of reactors.

Somewhere along the way we developed our own enrichment technology & deployed in en masse. Enrichment tech was developed for preparing fuel for the fission & boosted fission bombs. Interesting how military and civilian needs feed each other. The deployment of enrichment facilities brought the previously discarded LWRs back into the picture. With the signing of the India-US civil nuclear deal foreign LWR reactor tech & more importantly nuclear fuel became available.

We signed deals with Russia & then France for LWR & life time supply of nuclear fuel for these reactors. There was a deal in the making with the Americans too, though it might be dead by now. We've also signed deals to import nuclear fuel from Kazakhstan, Uzbekistan, Australia etc. Now the 1st & 2nd stage of the program looks like this:
View attachment 22088
The idea is to use foreign LWR to generate electricity, thus freeing up local Uranium & Plutonium for you know what. The PHWRs though are going to be our own design & fueled by our own Uranium. Have to keep those PHWRs away from IAEA safeguards if we want to keep producing & stockpiling Tritium. We are also in the process of converting the Arihant class SSBN's CLWR-B1 reactor into a full scale 900 MWe civilian LWR reactor named IPWR-900.

The IPHWR family of reactors started off as direct derivatives of the CANDU reactors. Eventually larger, more reactors with better safety parameters were developed. The original CANDU were barely Generation II safety standard compliant. Where as the IPHWR-700, the backbone of our nuclear reactor fleet, is Generation III+ compliant. Can the IPHWR family still be considered CANDU derivatives ? I'll leave that to your judgement.

In 2016-2017 the following was the projection of the installed nuclear power generation capacity:
View attachment 22087
With the pandemic, budgetary problems & the stellar rise of thermal/hydro/solar/wind power installation in the country expect the timelines shown above to be pushed back by a few years at least.

Our current installed nuclear power generation capacity is 6.78 GWe. In the post above you can see we will reach 22.48 GWe by 2031.

The upper limit of installed capacity from the IPHWR family & various research reactors using domestic Uranium is ~10 GWe. 6 GWe will come from the 6 units of the Russian VVER-1000 reactors in Kudankulam & 9.9 GWe from the 6 units of French EPR at Jaitapur. Total power from imported reactors is 15.9 GWe. Therefore total installed power capacity from Stage 1 from both domestic & imported reactors is ~25.9 GWe.

If by 2031 we will have 22.48 GWe, then we should be able to install the balance ~3 GWe & reach the maximum capacity limit of the Stage 1 by 2035. From then on there will be no further increase in Stage 1 reactors as shown in the graph above.

As we are implementing the Stage 1 we are also entering early implementation of the Stage 2 of the program with the Prototype Fast Breeder Reactor (PFBR). The physical testing phase of the Stage 2 began in October 1985 when the 40 MWt Fast Breeder Test Reactor (FBTR) attained criticality. The reactor ran into problems soon & had to be shut down in 1987 & then again in 1989. By the end of the 90s, IGCAR had a good understanding of the reactor & it would run at full capacity for the next 2 decades.

Based on the experience of the FBTR the Prototype Fast Breeder Reactor (PFBR) started in the 90s. PFBR is a 500 MWe reactor that would provide validation for the full sized FBR-600. FBR-600 or Fast Breeder Reactor-600 is a 600 MWe scaled up version of the PFBR. The FBR-600 will be the main reactor for the Stage 2 of the program. Construction was supposed to begin in 2007 in Kalpakkam, but some design changes caused inordinate delays.

Design of the PFBR:
View attachment 22092

Some construction images:

Here you can see the reactor vessel being lifted by a crane:
View attachment 22098
Vessel being inserted into the designated spot. The vessel was manufactured by L&T's Nuclear Engineering division:
View attachment 22095
Mounting equipment on top of the vessel:
View attachment 22097
The PFBR facility nearly complete:
View attachment 22090
In the winter session of the Parliament in 2020 responding to a question in the Lok Sabha Dr. Jitendra Singh said the PFBR will be operational by December of 2021.
View attachment 22094
We are now in December 2021. When asked the same question Dr. Jitendra Singh responded the commissioning date has been delayed to October 2022. Almost a year from now. 😑

The advantage of breeder reactors is that they produce more fuel than they consume. The PFBR/FBR-600 will produce Plutonium & Uranium, this surplus Plutonium bred in each FBR can be used to set up more such reactors. Thus the problem of lack of Uranium & Plutonium which stops the growth of nuclear power in India is greatly reduced but not completely gone. You can completely remove that problem once you can bring in the country's Thorium into play.

It is estimated that once India's nuclear power installed capacity reaches 50 GWe we will have enough Plutonium & Uranium to bring the 3rd stage online. 25 GWe is supposed to come from Stage 1, so we roughly need another 25 GWe from Stage 2 to start making Stage 3 reactors. We will need ~40 breeder reactors of 600 MWe capacity to get to 25 GWe. That's a lot of reactors. Maybe we should make a 1 GWe FBR.

That's all for today. Will write about the various types of reactors being studied for the Stage 3 in a post tomorrow....
@Gautam thanks for the wonderful write-up. Very detailed and informative.
 
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The IPHWR family of reactors started off as direct derivatives of the CANDU reactors. Eventually larger, more reactors with better safety parameters were developed. The original CANDU were barely Generation II safety standard compliant. Where as the IPHWR-700, the backbone of our nuclear reactor fleet, is Generation III+ compliant. Can the IPHWR family still be considered CANDU derivatives ? I'll leave that to your judgement.
Isn't IPHWR-700 is GEN III and IPHWR-900 suppose to be GEN III+ ?
 
That's all for today. Will write about the various types of reactors being studied for the Stage 3 in a post tomorrow....
Oh right forgot about this. Had some work in the morning.
Isn't IPHWR-700 is GEN III and IPHWR-900 suppose to be GEN III+ ?
Oops my bad. You are right, IPHWR-700 is Gen III. The 900 MWe reactor derived from the Arihant's powerplant is not a heavy water reactor. So its not IPHWR-900 but IPWR-900. The IPWR-900 & the AHWR are Gen III+ designs.
@Gautam thanks for the wonderful write-up. Very detailed and informative.
Thank you.(y)

Now on we go with the Stage-3 of India's nuclear power program.

The Advanced Heavy Water Reactor (AHWR) is the main proposed reactor for the 3rd stage of the program. The AHWR is an advanced fuel cycle reactor compliant to Generation III+ safety standards using fuel clusters comprising of Th-232/U-233 Mixed Oxide Fuel (MOX) & Th-232/Pu-239 Mixed Oxide Fuel (MOX). The Thorium would be from natural sources but the Uranium & Plutonium would be fission byproducts from the Stage-2 Fast Breeder Reactors (FBRs).
Screenshot (828).png

All the fuel bundles will be produced at the Advanced Fuel Fabrication Facility (AFFF), BARC at Tarapur. AFFF also provides fuel for IPHWR & the FBR families making it the only nuclear fuel production facility in the world that has expertise in processing Uranium, Plutonium & Thorium. The current model of the AHWR is rated to produce 300 MWe & is hence named AHWR-300. But like the IPHWR family the AHWR is also scalable. More powerful reactors can be made by simply enlarging the design.
Screenshot (829).png

AHWR's development started in the late 90s, detailed design phase ended by 2002. Component fabrication & testing began by 2005 & was completed by 2016. By 2017-18 design was in final stages of validation. Plans for deciding the location for setting up the AHWR was supposed to be called by soon.
Screenshot (833).png

Since then there has been radio silence, in December 2021 we still don't have any new info. Have they decided on the location for setting up the said reactors ? We don't know.

The problem with the 3 stage nuclear power program is the long doubling time needed for full scale Thorium reactor deployment. In our case we need to operate Stage-2 FBRs for 30-40 years before we've built up enough Uranium & Plutonium for full scale utilization of Thorium. Even if we make 10s of billions on FBRs we still have to wait another 3-4 decades before AHWRs can become mainstream.

What do we do about our growing energy needs in these 3-4 decades ? Keep burning coal ? That's not viable. So renewables it is. This realization has caused the nuclear establishment to be increasingly feel threatened. The rise of renewable, especially solar, energy installation across the nation has put a question mark on the need & want for nuclear reactors. Well previously a case could be made about the transient nature of renewable energy but the increasing deployment of grid scale battery systems makes that argument shaky.

So as New Delhi keeps ploughing in more money onto renewables the amount of money left for nuclear is less. Remember we had to wait 3-4 decades after the full scale deployment of the Stage-2. The way things are going we might not see full scale deployment of FBRs at all. There is of course no way a Stage-3 can happen without a Stage-2.

So the nuclear establishment had to come up with a way to keep the govt. funding coming. They needed to find some way of cutting down the waiting time to something more acceptable. If the lure of near unending Thorium based nuclear power wasn't enough how about some green hydrogen along with that ? That's the promise of a High Temperature Reactor.

1639927115462.png


Why Hydrogen ? What's green Hydrogen ? That's a long story. Google it you will know most of what you need to know. I'll tell you that all of the hydrogen we produce now are brown & grey hydrogen. The govt. wants to make India a global hub for production & exports of green hydrogen.

Since the early 2000s BARC has been working on a prototype High Temperature Reactor called the Compact High Temperature Reactor (CHTR). Besides producing electricity the CHTR would be capable of causing a thermo-chemical breakdown of water to produce green hydrogen. The thermo chemical splitting process of water holds the great promise, as it has the potential to generate large quantities of hydrogen, with a high degree of efficiency (40-57%). Temperatures of ~1000 deg C is needed to carry out the process. How do you generate that temperature ? With a High Temperature Reactor.

Screenshot (834).png


The CHTR is a technology demonstrator to validate concepts & prove technologies necessary to build full-scale Indian High Temperature Reactor (IHTR). The CHTR is an advanced fuel cycle reactor with Generation IV safety levels generating 100 KW of thermal power which in turn produces heat of ~1100 deg C. The heat would be used to produce hydrogen, the reject heat would produce electricity & the waste heat could be used for desalination. A mixture of Uranium-233 & Thorium-232, weighing 2.4 kg & 5.6 kg respectively, would fuel the CHTR's Core, that would require refueling every 15 years.

CHTR fuel bed.png

Once the CHTR is validated its larger cousin IHTR can be built. The plan is very similar to what we saw with the Stage-2 reactors. IHTR's proposed design is shown below:
Screenshot (840).png

Screenshot (842).png

Specs of the IHTR:
Screenshot (841).png

The IHTR can produce ~7 tons of green Hydrogen per hour & 9 million liters of drinkable water per day. Water is also becoming a problem in many part of the country. As the CHTR will be small enough to be truck mobile it is also proposed as a solution to provide electricity to many remote areas of the country that are not connected to the national electric grid.

No doubt the CHTR/IHTR is a great package. It is also the tool the country's nuclear establishment has chosen to counter the threat from ever expending solar/wind projects. BARC & IGCAR is known to have made many presentations & proposals to the govt. in the recent past about funding the CHTR/IHTR projects.

Recently they are also sounding off to the media to garner some attention. Articles have started coming out in regular intervals about the indispensability of nuclear power to the nation. A few examples are below:

India can’t meet net-zero target without nuclear power, says Anil Kakodkar

Bringing back reactors for green hydrogen

Will they succeed in convincing New Delhi ? We will see.

Besides the CHTR/IHTR, other types of reactors are also in consideration that will directly use Thorium. Namely the Indian Molten Salt Breeder Reactor (IMSBR) & the Indian Accelerator Driven Systems (IADS). IMSBR is a typical reactor but the IADS is a subcritical reactor. Both are still in early phases of design. IMSBR is a completely indigenous effort where as IADS started as an indigenous program & is now a JV. We signed a deal with Fermi Labs of US to jointly develop the IADS.

Either way the Stage 3 of the nuclear energy program will certainly be more eventful than the last phases. Interesting times ahead.
 

India To Build Nuclear Power Plants In "Fleet Mode" From 2023​

New Delhi:
With the first pour of concrete for a 700 MW atomic power plant in Karnataka's Kaiga scheduled in 2023, India is set to put in motion construction activities for 10 'fleet mode' nuclear reactors over the next three years.

The first pour of concrete (FPC) signals the beginning of construction of nuclear power reactors from the pre-project stage which includes excavation activities at the project site.

“The FPC of Kaiga units 5&6 is expected in 2023; FPC of Gorakhpur Haryana Anu Vidyut Praiyonjan units 3 & 4 and Mahi Banswara Rajasthan Atomic Power Projects units 1 to 4 is expected in 2024; and that of Chutka Madhya Pradesh Atomic Power Project units 1 & 2 in 2025,” officials of the Department of Atomic Energy (DAE) told the Parliamentary panel on science and technology.

The Centre had approved construction of 10 indigenously developed pressurised heavy water reactors (PHWR) of 700 MW each in June 2017. The ten PHWRs will be built at a cost of ₹ 1.05 lakh crore.

It was for the first time that the government had approved building 10 nuclear power reactors in one go with an aim to reduce costs and speed up construction time.

Bulk procurement was underway for the fleet mode projects with purchase orders placed for forgings for steam generators, SS 304L lattice tubes and plates for end shields, pressuriser forgings, bleed condensers forgings, incoloy-800 tubes for 40 steam generators, reactor headers, DAE officials said. Engineering, procurement and construction package for turbine island has been awarded for Gorakhpur units three and four and Kaiga units five and six, they added.

Under the fleet mode, a nuclear power plant is expected to be built over a period of five years from the first pour of concrete.

Currently, India operates 22 reactors with a total capacity of 6780 MW in operation. One 700 MW reactor at Kakrapar in Gujarat was connected to the grid on January 10 last year, but it is yet to start commercial operations.

The PHWRs, which use natural uranium as fuel and heavy water as moderator, have emerged as the mainstay of India's nuclear power programme.

India's first pair of PHWRs of 220 MW each were set up at Rawatbhata in Rajasthan in the 1960s with Canadian support. The second reactor had to be built with significant domestic components as Canada withdrew support following India's peaceful nuclear tests in 1974.

As many as 14 PHWRS of 220 MW each with standardised design and improved safety measures were built by India over the years. Indian engineers further improvised the design to increase the power generation capacity to 540 MWe, and two such reactors were made operational at Tarapur in Maharashtra.

61 Comments Further optimisations were carried out to upgrade the capacity to 700 MWe.
 

Supply of six nuclear reactors: Question mark on Russia inputs, India evaluates French push at Jaitapur​

Amid mounting uncertainties over the civil nuclear partnership with Russia in the wake of the Ukraine war, there are indications of fresh progress on the much-delayed deal with French power utility EDF for the supply of six EPR (European Pressurised Water Reactors) nuclear reactors.

The Department of Atomic Energy is actively examining a binding techno-commercial offer submitted by the French state-owned power company to help build six third-generation EPR reactors at Jaitapur in Maharashtra.

A high-level team from EDF was here late last month.

New Delhi had accorded an “in-principle” approval of the site at Jaitapur in Maharashtra for setting up of six reactors of 1650 MWe (megawatt electric) each as part of an umbrella nuclear deal signed with France in September 2008.

However, that proposal has been hanging fire on account of multiple factors, including the slowdown in nuclear projects globally post the Fukushima incident and internal reorganisation at French nuclear utility Areva (which was subsequently taken over by EDF).

If the Jaitapur deal takes off, it would be the largest nuclear power generating site in the country with a total capacity of 9,900 MWe and one of
the biggest-ever export deals for the French side.

Sources said the issue of the techno-commercial offer came up during delegation level talks between Prime Minister Narendra Modi and French President Emmanuel Macron in May.

At present, Russia is the only country setting up imported Light Water Reactor-based nuclear projects in India, despite the fruition of international cooperation in nuclear energy well over a decade ago.

Russia has been involved in the project at the Kudankulam site under a pact signed in 1998, with 2000 MWe of capacity – Units 1&2 (2X1000 MWe) currently in operation. Work is being launched for four more reactors: Units 3 to 6 (KKNPP 3&4 and KKNPP 5&6, 4X1000 MWe).

Alongside the French, discussion on project proposals with technology partners from the US for Kovvada, Andhra Pradesh (6 X 1208 MWe) is still work in progress.

A bigger n-power basket​

If Jaitapur takes off, it will be the largest n-power site in the country with a capacity of 9000 MWe. Given the war in Europe, there is also a need to diversify the nuclear cooperation basket. Also, New Delhi is factoring in the patchy French record on deadline management on EPR projects across the world.

As of February 2022, KKNPP 3&4 and KKNPP 5&6 had an overall physical progress of 58.22 per cent and 8.12 per cent respectively but sources indicated that the Kudankulam project completion schedule “is likely to be impacted” as components and equipment to be imported from Ukraine and Russia may be delayed due to logistical and ocean freight challenges arising out of the conflict.

Rosatom, the Russian nuclear organisation, is not an entity under sanctions at present but the current conflict, sources said, underlines the need for a more diverse nuclear cooperation basket.

Speaking to The Indian Express on the progress of the Jaitapur project, Emmanuel Lenain, Ambassador of France to India, said: “These are all big projects, big issues and for the long-term and we have to address them very professionally through discussions. We have technical aspects, commercial aspects, financial aspects, and you have the aspect of safety and all that needs to be done in a professional manner and that is what we are doing right now. Both governments feel that it’s a major cooperation and that it’s a key project for fighting against climate change but also for real autonomy.”

Flagging what he called India’s “amazing job” in terms of renewable energy, Lenain said: “…everybody was impressed with the announcement made by Prime Minister Modi at COP (climate change conference). You also need to have some stable source of energy — currently it is coal. If you want to get out of coal, nuclear power would be the best. The discussions have been very positive.”

There are 22 reactors with a capacity of 6780 MWe in operation in India and one additional reactor Kakrapar-3 (700 MWe) has been connected to the grid on January 10, 2021.

While the EPR is EDF’s next-generation nuclear reactor, there are lingering concerns over delays given the record of EPR-based projects across the world.

For example, the EPR-based Flamanville 3 reactor project in France, already a decade late, has seen cost quadruple since 2004 and fuel loading at the project has been pushed back by up to six months.

In China, EDF said, inspections of fuel assemblies at its Taishan 1 EPR reactor showed “mechanical wear of certain assembly components”, which had already been observed in many French reactors.

China General Nuclear Power Group, which operates the Taishan plant with EDF, shut down one of its reactors in August to investigate fuel damage, after EDF said it was examining a potential issue linked to a build-up of radioactive gases. Its other EPR site, in Finland at Olkiluoto 3, started critical functions last month after multi-year delays and cost over-runs.

In India, EDF subsidiary, Framatome, which has had a cooperation agreement with L&T for the manufacturing of certain components of the nuclear island, is among the partnerships likely to be leveraged by the French utility to ensure that the localisation content goes up and costs are kept low. A detailed query sent to EDF on the issue did not elicit a response.

While indications are that there are no specific cost benchmarks, the two Russian-design reactor units (KKNPP units 3 & 4) coming up at Kudankulam entailed an initial sanctioned project cost of Rs 39,849 crore (in 2014), translating into a cost of nearly Rs 20 crore per MWe as against the average project cost of Rs 7-10 crore per MWe for existing nuclear projects based largely on indigenous PHWR (pressurised heavy water reactor) technology.
 

Kudankulam unit 3 reactor building dome installed​

The lifting, by a Liebherr LR 11350 heavy crane, took place on Wednesday in an operation that took about one hour and fifteen minutes.


Rosatom added that preassembling on the ground, with the installation of one structure instead of two, "made it possible to reduce the duration of construction and installation works at the reactor building by almost one month".


Andrey Lebelev, vice president of ASE JSC for Projects in India, said: "We share our experience and our technologies with our partners, we perform the necessary training and fulfill all the obligations. This allows us to be confident in the quality of our products and services and maintain the trust-based relations."


Kudankulam is a long-term strategic project between India and Russia that began with an intergovernmental agreement in 1988. Nuclear Power Corporation of India Limited is building four new VVER-1000 units of 1000 MWe each in Kudankulam, which is in Tamil Nadu in southern India - units 3, 4, 5 and 6. The expected completion dates for Kundankulam 3 and 4 are in 2023. Kudankulam 1 and 2 entered commercial operation in December 2014 and April 2017, respectively.


In July, Rosatom said that installing equipment at Kudankulam unit 3 using the "open top" technique - while the dome was open - had saved between five and seven months of construction time.
 
Russia plans to provide fast breeder nuclear reactor technology to China, an agreement that could allow Beijing to significantly grow its nuclear arsenal and tip the prevailing global balance of nuclear weapons.


I have nt heard any recent news regarding India's PFBR . May be nobody gives a shit anymore .
 
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