Nuclear Energy in India : Updates
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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.
Russia to power China's nuclear weapon ambitions - Asia Times
Russia plans to provide fast breeder nuclear reactor technology to China, an agreement that could allow Beijing to significantly grow its nuclear arsenalasiatimes.com
According to Saurav Jha in one of his IAH on the second half of last year , the PFBR is due to go critical this year in the second half after yrs of hiccups & last minute technical glitches. It was originally meant to go critical in 2018-19.
India's first domestically built 700 MW nuclear reactor starts commercial operations in Gujarat
economictimes.indiatimes.com
India's first domestically built 700 MW nuclear reactor starts commercial operations in Gujarat
India's first indigenously developed 700 MW nuclear power reactor has started commercial operations at the Kakrapar Atomic Power Project in Gujarat. The reactor is currently operating at 90% of its total power capacity. The Nuclear Power Corporation of India Limited (NPCIL) plans to build...
Fuel loading begins at India’s second 700 MWe nuclear power unit.
This is the second indigenous 700 MWe nuclear power station that may shortly become operational after KAPP-3 which began producing electricity on June 30 and commenced full power operational after KAPP-3 which began producing electricity on June 30 and commenced full power operation two months later.
By Kalyan Ray
Last Updated: 21 October 2023, 01:41 IST
Kakrapar Atomic Power Project – Units 3 & 4 in Gujarat. The reactors are being built by L&T Construction.
Nuclear fuel loading began on Friday at India’s second 700 MWe atomic power plant, setting the stage for “attaining criticality” and commercial electricity production at the fourth unit of the Kakrapar Atomic Power Project (KAPP-4) in Gujarat.
This is the second indigenous 700 MWe nuclear power station that may shortly become operational after KAPP-3 which began producing electricity on June 30 and commenced full power operation two months later. The two units at Kakrapar are the first two of the 16 such indigenous nuclear power stations that Nuclear Power Corporation of India Ltd is setting up.
In May 2017, the Union Cabinet approved setting up of ten 700 MWe nuclear reactors in “fleet mode” while six such units – two at Kakrapar, two at Rawatbhata in Rajasthan and two in Haryana - were under various stages of approval and construction at the time of the Cabinet approval.
The permission for initial fuel loading at KAPP-3 was granted by the Atomic Energy Regulatory Board after carrying out stringent safety and security reviews. This is a milestone in the setting up of a nuclear power plant as it is the prelude to approaching criticality (start of fission chain reaction) and subsequent start of power generation. In the case of KAPP-3, there was a gap of three years between the reactor attaining criticality and starting commercial power production as NPCIL faced unforeseen technical challenges.
Kakrapar Atomic Power Project – Units 3 & 4 in Gujarat. The reactors are being built by L&T Construction.
“During the unit commissioning, following synchronization with the grid, elevated temperatures were observed in certain areas of the reactor building,” Union Minister Jitendra Singh informed the Lok Sabha in July 2022.
Though the minister said the technical issues were addressed by carrying out “requisite modifications and improvements” and KAPP-3 was likely to start commercial operations by December 2022, it took another six months for the unit to produce electricity for the grid.
Officials said KAPP-4 was unlikely to take such a long time for commercial power production and criticality might happen by December.
“With the successful and stable operation of KAPP-3, the capability of the NPCIL in setting up of indigenous reactors of PHWR technology of this size is validated and paves the path for early completion of the remaining 14 reactors, beginning with Units 7&8 of Rajasthan Atomic Power Project at Rawatbhata,” the NPCIL said in a statement.
All the four big reactors took more than a decade to complete. The construction of the KAPP-3 began in November 2010 while KAPP-4 started in March 2011. The construction of Rajasthan Atomic Power Plant-7 & 8 began in 2011.
The NPCIL claims these reactors have advanced safety features comparable to the best in the world.
Other 700 MWe indigenous reactors will be set up at Kaiga in Karnataka, Gorakhpur in Haryana, Chutka in Madhya Pradesh and Mahi Banswara in Rajasthan.
Fuel loading begins at India’s second 700 MWe nuclear power unit
This is the second indigenous 700 MWe nuclear power station that may shortly become operational after KAPP-3 which began producing electricity on June 30 and commenced full power operational after KAPP-3 which began producing electricity on June 30 and commenced full power operation two months later.
By Kalyan Ray
Last Updated: 21 October 2023, 01:41 IST
Kakrapar Atomic Power Project – Units 3 & 4 in Gujarat. The reactors are being built by L&T Construction.
Nuclear fuel loading began on Friday at India’s second 700 MWe atomic power plant, setting the stage for “attaining criticality” and commercial electricity production at the fourth unit of the Kakrapar Atomic Power Project (KAPP-4) in Gujarat.
This is the second indigenous 700 MWe nuclear power station that may shortly become operational after KAPP-3 which began producing electricity on June 30 and commenced full power operation two months later. The two units at Kakrapar are the first two of the 16 such indigenous nuclear power stations that Nuclear Power Corporation of India Ltd is setting up.
In May 2017, the Union Cabinet approved setting up of ten 700 MWe nuclear reactors in “fleet mode” while six such units – two at Kakrapar, two at Rawatbhata in Rajasthan and two in Haryana - were under various stages of approval and construction at the time of the Cabinet approval.
The permission for initial fuel loading at KAPP-3 was granted by the Atomic Energy Regulatory Board after carrying out stringent safety and security reviews. This is a milestone in the setting up of a nuclear power plant as it is the prelude to approaching criticality (start of fission chain reaction) and subsequent start of power generation. In the case of KAPP-3, there was a gap of three years between the reactor attaining criticality and starting commercial power production as NPCIL faced unforeseen technical challenges.
Kakrapar Atomic Power Project – Units 3 & 4 in Gujarat. The reactors are being built by L&T Construction.
“During the unit commissioning, following synchronization with the grid, elevated temperatures were observed in certain areas of the reactor building,” Union Minister Jitendra Singh informed the Lok Sabha in July 2022.
Though the minister said the technical issues were addressed by carrying out “requisite modifications and improvements” and KAPP-3 was likely to start commercial operations by December 2022, it took another six months for the unit to produce electricity for the grid.
Officials said KAPP-4 was unlikely to take such a long time for commercial power production and criticality might happen by December.
“With the successful and stable operation of KAPP-3, the capability of the NPCIL in setting up of indigenous reactors of PHWR technology of this size is validated and paves the path for early completion of the remaining 14 reactors, beginning with Units 7&8 of Rajasthan Atomic Power Project at Rawatbhata,” the NPCIL said in a statement.
All the four big reactors took more than a decade to complete. The construction of the KAPP-3 began in November 2010 while KAPP-4 started in March 2011. The construction of Rajasthan Atomic Power Plant-7 & 8 began in 2011.
The NPCIL claims these reactors have advanced safety features comparable to the best in the world.
Other 700 MWe indigenous reactors will be set up at Kaiga in Karnataka, Gorakhpur in Haryana, Chutka in Madhya Pradesh and Mahi Banswara in Rajasthan.
Fuel loading begins at India’s second 700 MWe nuclear power unit
NPCIL to set up nuclear-powered hydrogen generation plants
Nuclear Power Corp. of India Ltd (NPCIL) is setting up hydrogen generation plants with 10 Nm3 per hour capacity at its Rawatbhata (Rajasthan) and Tarapur (Maharashtra) sites. These plants will produce hydrogen via electrolysis method using nuclear power produced at the site.
NOVEMBER 20, 2023
By UMA GUPTA
Unit-3 of NPCIL's Kaiga nuclear power generating station. Pic credit: NPCIL
Nuclear Power Corp. of India Ltd (NPCIL), a power sector utility under the Department of Atomic Energy, is setting up small hydrogen generation plants and associated systems with 10 Nm3 per hour capacity at the Rawatbhata and Tarapur sites to gain experience in hydrogen production and related aspects.
Under its hydrogen policy, NPCIL is pursuing clean hydrogen generation both as captive production for its nuclear power plant sites and commercial production as a diversification business model along with the generation of clean and green electricity.
In captive mode, small clean hydrogen-producing units will be established to meet the captive requirement of hydrogen at the nuclear power plant sites. The unit will use electricity sourced from the nuclear power plant itself to replace the sourcing of grey hydrogen from the market. The company said such a setup can be used as a prototype for subsequent implementation of large-size clean hydrogen-producing projects.
NPCIL is also looking at cogeneration mode, which allows NPCIL to generate profit from the sale of hydrogen apart from the sale of power generated.
In cogeneration mode, clean hydrogen is co-generated using the electricity generated by nuclear power plants, which may be rendered excess due to demand and price trends in the electricity market. “This strategy may be needed to deal with technologies like solar/wind and their falling tariffs, as difficulties are being faced in concluding power purchase agreements (PPA) with distribution companies (DISCOM) for electricity generated by new nuclear power plants,” said NPCIL. “There are also pressures on Nuclear Power Plants (NPPs) to operate in flexible mode in line with the availability of cheap solar power in the grid. Nuclear power plants in general are not amenable to flexible operation, as frequent variations in power are undesirable for reliable fuel performance and stability of the neutronic equilibrium of the reactor core.”
NPCIL is also looking at setting up dedicated nuclear power plants to generate electricity for the sole purpose of producing clean hydrogen. This model may be thought of for the small-capacity, older nuclear power plants, said NPCIL.
NPCIL to set up nuclear-powered hydrogen generation plants.
Nuclear Power Corp. of India Ltd (NPCIL) is setting up hydrogen generation plants with 10 Nm3 per hour capacity at its Rawatbhata (Rajasthan) and Tarapur (Maharashtra) sites. These plants will produce hydrogen via electrolysis method using nuclear power produced at the site.
NOVEMBER 20, 2023
By UMA GUPTA
Unit-3 of NPCIL's Kaiga nuclear power generating station. Pic credit: NPCIL
Nuclear Power Corp. of India Ltd (NPCIL), a power sector utility under the Department of Atomic Energy, is setting up small hydrogen generation plants and associated systems with 10 Nm3 per hour capacity at the Rawatbhata and Tarapur sites to gain experience in hydrogen production and related aspects.
Under its hydrogen policy, NPCIL is pursuing clean hydrogen generation both as captive production for its nuclear power plant sites and commercial production as a diversification business model along with the generation of clean and green electricity.
In captive mode, small clean hydrogen-producing units will be established to meet the captive requirement of hydrogen at the nuclear power plant sites. The unit will use electricity sourced from the nuclear power plant itself to replace the sourcing of grey hydrogen from the market. The company said such a setup can be used as a prototype for subsequent implementation of large-size clean hydrogen-producing projects.
NPCIL is also looking at cogeneration mode, which allows NPCIL to generate profit from the sale of hydrogen apart from the sale of power generated.
In cogeneration mode, clean hydrogen is co-generated using the electricity generated by nuclear power plants, which may be rendered excess due to demand and price trends in the electricity market. “This strategy may be needed to deal with technologies like solar/wind and their falling tariffs, as difficulties are being faced in concluding power purchase agreements (PPA) with distribution companies (DISCOM) for electricity generated by new nuclear power plants,” said NPCIL. “There are also pressures on Nuclear Power Plants (NPPs) to operate in flexible mode in line with the availability of cheap solar power in the grid. Nuclear power plants in general are not amenable to flexible operation, as frequent variations in power are undesirable for reliable fuel performance and stability of the neutronic equilibrium of the reactor core.”
NPCIL is also looking at setting up dedicated nuclear power plants to generate electricity for the sole purpose of producing clean hydrogen. This model may be thought of for the small-capacity, older nuclear power plants, said NPCIL.
NPCIL to set up nuclear-powered hydrogen generation plants.
Hello everyone, is BARC currently working on a 500mw naval nuclear reactor? I'm curious about if BARC is really working on it.
Kakrapar nuclear plant achieves criticality
The criticality was achieved after meeting all the stipulations of the Atomic Energy Regulatory Board (AERB), which issued clearance after a rigorous review of the safety of the plant systems.
By Mrityunjay Bose
DHNS
Last Updated 17 December 2023, 14:35 IST
Kakrapar Atomic Power Project (KAPP-4) in Gujarat. Credit: NPCIL
Mumbai: Unit 4 of the Kakrapar Atomic Power Project in Surat district of Gujarat achieved the important milestone of criticality (start of a controlled fission chain reaction) for the first time at 0117 hrs on Sunday, as announced by the Mumbai-headquartered Nuclear Power Corporation of India Ltd (NPCIL).
The KAPP-4 is a 700 MW Pressurised Heavy Water Reactor (PHWR). The criticality was achieved after meeting all the stipulations of the Atomic Energy Regulatory Board (AERB), which issued clearance after a rigorous review of the safety of the plant systems. KAPP-4 is the second in the series of sixteen indigenous PHWRs of 700 MW each being set up in the country.
The event was witnessed by B C Pathak, CMD, NPCIL, who was present in the control room of the station with the site team. Officials at NPCIL Headquarters in Mumbai witnessed the event through video link. Addressing the officials at the site and headquarters after the event, Pathak congratulated all the employees of NPCIL.
“The achievement of criticality of KAPP-4, within six months of commercial operation of KAPP-3 was a significant achievement. Together with the smooth operation of KAPP-3, it demonstrated the strength of NPCIL in all facets of nuclear power viz. design, construction, commissioning and operation,” said Pathak.
He urged everyone to work towards rapid completion of the units under construction.
After the first criticality, several experiments/tests will be conducted in KAPP-4 and the power level raised in steps, in line with the clearances of the AERB, ultimately culminating in operation of the unit at full power.
KAPP 3&4 (2X700 MW) are located at Kakrapar in Surat district of Gujarat, adjacent to the existing reactors KAPS 1&2 (2X220 MW). “These indigenous PHWRs have advanced safety features and are among the safest reactors in the world. While these reactors have been designed, constructed, commissioned and operated by NPCIL, the supply of equipment and execution of contracts have been by Indian industries and companies, and thus the true reflection of the spirit of AtmaNirbhar Bharat,” said B V S Sekhar, Outstanding Scientist and Associate Director (CP&CC) & Appellate Authority.
NPCIL presently operates 23 reactors with a total capacity of 7,480 MW and has nine units (including KAPP-4) with a capacity of 7,500 MW under construction.
In addition, 10 more reactors with a total capacity of 7,000 MW are in pre-project activities. These are expected to be completed progressively by 2031-32.
Kakrapar nuclear plant achieves criticality
The criticality was achieved after meeting all the stipulations of the Atomic Energy Regulatory Board (AERB), which issued clearance after a rigorous review of the safety of the plant systems.
By Mrityunjay Bose
DHNS
Last Updated 17 December 2023, 14:35 IST
Kakrapar Atomic Power Project (KAPP-4) in Gujarat. Credit: NPCIL
Mumbai: Unit 4 of the Kakrapar Atomic Power Project in Surat district of Gujarat achieved the important milestone of criticality (start of a controlled fission chain reaction) for the first time at 0117 hrs on Sunday, as announced by the Mumbai-headquartered Nuclear Power Corporation of India Ltd (NPCIL).
The KAPP-4 is a 700 MW Pressurised Heavy Water Reactor (PHWR). The criticality was achieved after meeting all the stipulations of the Atomic Energy Regulatory Board (AERB), which issued clearance after a rigorous review of the safety of the plant systems. KAPP-4 is the second in the series of sixteen indigenous PHWRs of 700 MW each being set up in the country.
The event was witnessed by B C Pathak, CMD, NPCIL, who was present in the control room of the station with the site team. Officials at NPCIL Headquarters in Mumbai witnessed the event through video link. Addressing the officials at the site and headquarters after the event, Pathak congratulated all the employees of NPCIL.
“The achievement of criticality of KAPP-4, within six months of commercial operation of KAPP-3 was a significant achievement. Together with the smooth operation of KAPP-3, it demonstrated the strength of NPCIL in all facets of nuclear power viz. design, construction, commissioning and operation,” said Pathak.
He urged everyone to work towards rapid completion of the units under construction.
After the first criticality, several experiments/tests will be conducted in KAPP-4 and the power level raised in steps, in line with the clearances of the AERB, ultimately culminating in operation of the unit at full power.
KAPP 3&4 (2X700 MW) are located at Kakrapar in Surat district of Gujarat, adjacent to the existing reactors KAPS 1&2 (2X220 MW). “These indigenous PHWRs have advanced safety features and are among the safest reactors in the world. While these reactors have been designed, constructed, commissioned and operated by NPCIL, the supply of equipment and execution of contracts have been by Indian industries and companies, and thus the true reflection of the spirit of AtmaNirbhar Bharat,” said B V S Sekhar, Outstanding Scientist and Associate Director (CP&CC) & Appellate Authority.
NPCIL presently operates 23 reactors with a total capacity of 7,480 MW and has nine units (including KAPP-4) with a capacity of 7,500 MW under construction.
In addition, 10 more reactors with a total capacity of 7,000 MW are in pre-project activities. These are expected to be completed progressively by 2031-32.
Kakrapar nuclear plant achieves criticality
Experimental reactors of BARC and IGCAR to be used for hydrogen pilot plants
Updated: January 05, 2024 at 09:22 PM.
BY M RAMESH
It is learned that IGCAR has formed a task force to look into developing a 100 MW ‘small modular reactor.
The Department of Atomic Energy is working on a plan to modify two experimental reactors developed by its arms to make them into pilot plants for producing nuclear-powered green hydrogen.
One is the Indian High-Temperature Reactor (IHRT) developed by the Bhabha Atomic Research Center in the mid-2000s. As businessline reported on December 12, 2021, the IHTR was developed to produce hydrogen—through the thermochemical route (splitting of water into hydrogen and oxygen using heat rather than electricity.) The reactor was designed to produce about 7,000 kg of hydrogen, 18 MWh (thermal) of energy per hour, and 9 million litres of (desalinated) water a day.
In a presentation made at a conference held at Oarai, Japan, on April 16, 2007, BARC scientists I V Dulera and R K Sinha (who later became Chairman of the Atomic Commission), described the IHTR as a 600 MW (thermal) reactor capable of producing 1,000 degrees C of heat.
The second reactor is the 40 MW (thermal) Fast Breeder Test Reactor (FBTR) of the Indira Gandhi Center for Atomic Research (IGCAR). This was set up to learn how to operate a fast breeder reactor and it is based on these learnings that the 500 MW ‘prototype fast breeder reactor’ (PFBR) is coming u at Kalpakkam, near Chennai. Incidentally, Dr R Divakar, Group Director – Metallurgy and Material Sciences, IGCAR, said at an energy conference in Chennai on Thursday that the PFBR would go on stream in 2024. The project has been under construction for over twenty years.
The FBTR is also being modified to produce green hydrogen.
Small modular reactors
Meanwhile, it is learned that IGCAR has formed a task force to look into developing a 100 MW ‘small modular reactor’ (SMR). Today, many countries are looking at SMRs for distributed generation of electricity. SMRs can be put up on sites of retired thermal power plants—which already have all the attendant infrastructure such as for power evacuation and materials movement.
The government of India is giving SMRs a big push and the small reactors figure in all energy conferences and discussions. The IHRT and FBTR may also be configured as SMRs.
Experimental reactors of BARC and IGCAR to be used for hydrogen pilot plants
Updated: January 05, 2024 at 09:22 PM.
BY M RAMESH
It is learned that IGCAR has formed a task force to look into developing a 100 MW ‘small modular reactor.
The Department of Atomic Energy is working on a plan to modify two experimental reactors developed by its arms to make them into pilot plants for producing nuclear-powered green hydrogen.
One is the Indian High-Temperature Reactor (IHRT) developed by the Bhabha Atomic Research Center in the mid-2000s. As businessline reported on December 12, 2021, the IHTR was developed to produce hydrogen—through the thermochemical route (splitting of water into hydrogen and oxygen using heat rather than electricity.) The reactor was designed to produce about 7,000 kg of hydrogen, 18 MWh (thermal) of energy per hour, and 9 million litres of (desalinated) water a day.
In a presentation made at a conference held at Oarai, Japan, on April 16, 2007, BARC scientists I V Dulera and R K Sinha (who later became Chairman of the Atomic Commission), described the IHTR as a 600 MW (thermal) reactor capable of producing 1,000 degrees C of heat.
The second reactor is the 40 MW (thermal) Fast Breeder Test Reactor (FBTR) of the Indira Gandhi Center for Atomic Research (IGCAR). This was set up to learn how to operate a fast breeder reactor and it is based on these learnings that the 500 MW ‘prototype fast breeder reactor’ (PFBR) is coming u at Kalpakkam, near Chennai. Incidentally, Dr R Divakar, Group Director – Metallurgy and Material Sciences, IGCAR, said at an energy conference in Chennai on Thursday that the PFBR would go on stream in 2024. The project has been under construction for over twenty years.
The FBTR is also being modified to produce green hydrogen.
Small modular reactors
Meanwhile, it is learned that IGCAR has formed a task force to look into developing a 100 MW ‘small modular reactor’ (SMR). Today, many countries are looking at SMRs for distributed generation of electricity. SMRs can be put up on sites of retired thermal power plants—which already have all the attendant infrastructure such as for power evacuation and materials movement.
The government of India is giving SMRs a big push and the small reactors figure in all energy conferences and discussions. The IHRT and FBTR may also be configured as SMRs.
Experimental reactors of BARC and IGCAR to be used for hydrogen pilot plants
Powering India. This new nuclear fuel can guarantee India’s green energy transition.
BY M RAMESH
Updated: January 08, 2024, 02:46 PM.
The Thorium breakthrough: Invented by a person-of-Indian origin, ANEEL is said to be the next generation nuclear fuel.
Mehul Shah, Founder and CEO of Clean Core Thorium Energy
An invention by an American company, set up by a person of Indian origin, is making waves in the nuclear establishment of North America. If adopted in India, it can guarantee green energy security for the subcontinent by fast-tracking the use of Thorium in nuclear reactors.
India has the world’s largest reserves of Thorium, estimated at 1.07 million tonnes, enough to last over a century. If India uses this Thorium, it can then produce enough green energy and easily turn net-zero by its target date of 2070.
However, Thorium is a fertile material and not a fissile material. This means, it must be paired with Uranium-235 or Plutonium-239 to be used as fuel in a reactor. As neutrons from these fissile materials bombard Thorium, it mutates into Uranium-233, which is also a fissile material. So, to use the Thorium in India, you need sufficient stocks of Uranium-235 (which India has very little of), or Plutonium-239 (which is produced using Uranium-235). So, the question has been, how to use Thorium with minimal use of (precious) Uranium.
This is where the invention of Mehul Shah, Founder and CEO of Clean Core Thorium Energy, comes in. The Chicago-based company has developed (and patented) a fuel, which is a mix of Thorium and Uranium of a certain level of enrichment, called HALEU (High Assay Low Enriched Uranium). Clean Core calls this concoction ANEEL (Advanced Nuclear Energy for Enriched Life) — named so to honour one of India’s foremost nuclear scientists, Dr Anil Kakodkar.
Gamechanger
ANEEL can be used in the existing Pressurized Heavy-Water Reactors (PHWRs), an indigenous reactor system that is the workhorse of India’s nuclear fleet. India has 18 PHWR reactors of a total capacity of 4,460 MW and is building ten more of 700 MW each.
If pursued, Clean Core’s ANEEL fuel can prove to be a game-changer for India. According to the World Nuclear Association, most of the current reactors run on uranium fuel enriched up to 5 per cent Uranium-235. HALEU is Uranium enriched to more than 5 per cent but less than 20 per cent. It is needed for many of the advanced nuclear reactor designs under development. “HALEU is not yet widely available commercially. At present only Russia and China have the infrastructure to produce HALEU at scale. Centrus Energy, in the US, began producing HALEU from a demonstration-scale cascade in October 2023,” says the Association. With uncertain commercialisation timelines, HALEU suppliers have remained cautious on scaling capacity due to demand-side risk.
Perfect pair: Clean Core’s nuclear fuel bundle made from Thorium and HALEU
However, with Clean Core’s near-term timeline to commercialisation, the company can help strengthen the demand-side confidence for HALEU suppliers.
India’s approach to Thorium utilisation has been to make a Thorium blanket around uranium or plutonium reactors, so that as the reactor produces energy, it also converts thorium into uranium-233. However, ANEEL provides an easier and quicker alternative for the deployment of thorium leveraging imported HALEU.
Nuclear waste reduction
Furthermore, in utilizing this fuel, reactor operators can enjoy a dramatic reduction in nuclear waste volume and operating costs.
Another significant advantage is the inherent operating characteristics of the ANEEL fuel bundle — it lasts much longer and burns more efficiently. Its burn-up is 60,000 MW-days per tonne, compared with the 7,000 MW-days per tonne of the conventional natural uranium fuel in PHWRs. This higher burn-up significantly impacts the waste volumes and economics of reactor operations compared with the currently used natural uranium.
For example, in an existing Indian 220 MW PHWR, while using natural uranium fuel, an average of eight bundles would need to be replaced daily for the rest of the reactor’s operating life of 60 years. That is about 1,75,000 bundles used over the life of a reactor. With the ANEEL fuel, an average of only one such bundle would need to be replaced daily resulting in about 22,000 bundles used over the lifetime of the reactor. This leads to significant reduction in waste generation and cost savings.
Due to the inherent benefits of using thorium, the spent ANEEL fuel cannot be used for weapons — a source of comfort for foreign uranium suppliers and reactor operators, says Mehul Shah.
With all these benefits, Shah believes that ANEEL-powered 220 MW Indian PHWR can fill a growing need for clean, baseload energy production, as highlighted by the pledge to triple nuclear capacity by more than 20 countries at the recently held COP28.
Other countries are also showing interest in using ANEEL. “This is the first-of-its-kind nuclear fuel, in that it combines HALEU and thorium in proprietary unique compositions that can drive a global clean energy future,” says Dr Sean McDeavitt, Director of the Nuclear Engineering and Science Center and professor in the Department of Nuclear Engineering at Texas A&M University.
In April 2023, Canadian Nuclear Laboratories signed a MoU with Clean Core “to further the development and deployment of Clean Core’s ANEEL fuel,” according to a press release. Under the MoU, CNL would support Clean Core’s activities, including R&D and licensing.
This new nuclear fuel can guarantee India’s green energy transition
@Ashwin @randomradio @Parthu et al. This could be a big deal.
BY M RAMESH
Updated: January 08, 2024, 02:46 PM.
The Thorium breakthrough: Invented by a person-of-Indian origin, ANEEL is said to be the next generation nuclear fuel.
Mehul Shah, Founder and CEO of Clean Core Thorium Energy
An invention by an American company, set up by a person of Indian origin, is making waves in the nuclear establishment of North America. If adopted in India, it can guarantee green energy security for the subcontinent by fast-tracking the use of Thorium in nuclear reactors.
India has the world’s largest reserves of Thorium, estimated at 1.07 million tonnes, enough to last over a century. If India uses this Thorium, it can then produce enough green energy and easily turn net-zero by its target date of 2070.
However, Thorium is a fertile material and not a fissile material. This means, it must be paired with Uranium-235 or Plutonium-239 to be used as fuel in a reactor. As neutrons from these fissile materials bombard Thorium, it mutates into Uranium-233, which is also a fissile material. So, to use the Thorium in India, you need sufficient stocks of Uranium-235 (which India has very little of), or Plutonium-239 (which is produced using Uranium-235). So, the question has been, how to use Thorium with minimal use of (precious) Uranium.
This is where the invention of Mehul Shah, Founder and CEO of Clean Core Thorium Energy, comes in. The Chicago-based company has developed (and patented) a fuel, which is a mix of Thorium and Uranium of a certain level of enrichment, called HALEU (High Assay Low Enriched Uranium). Clean Core calls this concoction ANEEL (Advanced Nuclear Energy for Enriched Life) — named so to honour one of India’s foremost nuclear scientists, Dr Anil Kakodkar.
Gamechanger
ANEEL can be used in the existing Pressurized Heavy-Water Reactors (PHWRs), an indigenous reactor system that is the workhorse of India’s nuclear fleet. India has 18 PHWR reactors of a total capacity of 4,460 MW and is building ten more of 700 MW each.
If pursued, Clean Core’s ANEEL fuel can prove to be a game-changer for India. According to the World Nuclear Association, most of the current reactors run on uranium fuel enriched up to 5 per cent Uranium-235. HALEU is Uranium enriched to more than 5 per cent but less than 20 per cent. It is needed for many of the advanced nuclear reactor designs under development. “HALEU is not yet widely available commercially. At present only Russia and China have the infrastructure to produce HALEU at scale. Centrus Energy, in the US, began producing HALEU from a demonstration-scale cascade in October 2023,” says the Association. With uncertain commercialisation timelines, HALEU suppliers have remained cautious on scaling capacity due to demand-side risk.
Perfect pair: Clean Core’s nuclear fuel bundle made from Thorium and HALEU
However, with Clean Core’s near-term timeline to commercialisation, the company can help strengthen the demand-side confidence for HALEU suppliers.
India’s approach to Thorium utilisation has been to make a Thorium blanket around uranium or plutonium reactors, so that as the reactor produces energy, it also converts thorium into uranium-233. However, ANEEL provides an easier and quicker alternative for the deployment of thorium leveraging imported HALEU.
Nuclear waste reduction
Furthermore, in utilizing this fuel, reactor operators can enjoy a dramatic reduction in nuclear waste volume and operating costs.
Another significant advantage is the inherent operating characteristics of the ANEEL fuel bundle — it lasts much longer and burns more efficiently. Its burn-up is 60,000 MW-days per tonne, compared with the 7,000 MW-days per tonne of the conventional natural uranium fuel in PHWRs. This higher burn-up significantly impacts the waste volumes and economics of reactor operations compared with the currently used natural uranium.
For example, in an existing Indian 220 MW PHWR, while using natural uranium fuel, an average of eight bundles would need to be replaced daily for the rest of the reactor’s operating life of 60 years. That is about 1,75,000 bundles used over the life of a reactor. With the ANEEL fuel, an average of only one such bundle would need to be replaced daily resulting in about 22,000 bundles used over the lifetime of the reactor. This leads to significant reduction in waste generation and cost savings.
Due to the inherent benefits of using thorium, the spent ANEEL fuel cannot be used for weapons — a source of comfort for foreign uranium suppliers and reactor operators, says Mehul Shah.
With all these benefits, Shah believes that ANEEL-powered 220 MW Indian PHWR can fill a growing need for clean, baseload energy production, as highlighted by the pledge to triple nuclear capacity by more than 20 countries at the recently held COP28.
Other countries are also showing interest in using ANEEL. “This is the first-of-its-kind nuclear fuel, in that it combines HALEU and thorium in proprietary unique compositions that can drive a global clean energy future,” says Dr Sean McDeavitt, Director of the Nuclear Engineering and Science Center and professor in the Department of Nuclear Engineering at Texas A&M University.
In April 2023, Canadian Nuclear Laboratories signed a MoU with Clean Core “to further the development and deployment of Clean Core’s ANEEL fuel,” according to a press release. Under the MoU, CNL would support Clean Core’s activities, including R&D and licensing.
This new nuclear fuel can guarantee India’s green energy transition
@Ashwin @randomradio @Parthu et al. This could be a big deal.
Experimental reactors of BARC and IGCAR to be used for hydrogen pilot plants
Atomic Energy Dept. plans to modify two experimental reactors to produce green hydrogen & nuclear-powered energy.
Minimal radioactive discharges from Indian nuclear plants: study
While samples were collected and measured for maximum radius of 30 km of each nuclear plant, the concentrations of fission products beyond 5 km radius were below the minimum detectable activity of the instruments used.
Updated January 28, 2024, 12:00 am IST
By R. PRASAD
A cooling tower at the Rajasthan Atomic Power Station, RAPS-5 in Rawatbhatta, Rajasthan. File | Photo Credit: The Hindu.
Based on an analysis of radiological data of 20 years (2000-2020) from six nuclear power plants based in India, researchers at the Bhabha Atomic Research Centre (BARC), Mumbai have found that the radioactive discharges from the nuclear plants and the resultant potential environmental impact have been “minimal”. “The findings hold potential significance for reinforcing India’s commitment to advancing its nuclear power programme,” the authors write. “The minimal public doses underscore the safe operation of Indian nuclear power plants. The study’s findings have the potential to dispel unfounded beliefs, serving as a catalyst to reinforce India’s commitment to advancing its nuclear power programme, thus encouraging policymakers and the public to reconsider their perspectives.”
The period of study for the Kudankulam Nuclear Power Station is from 2013 to 2020. The other six power plants studied are: Tarapur Atomic Power Station, Madras Atomic Power Station, Kaiga Generating Station, Rajasthan Atomic Power Station, Narora Atomic Power Station, and Kakrapar Atomic Power Station. The results were published recently in the journal Science of the Total Environment.
While samples were collected and measured for a maximum radius of 30 km of each nuclear plant, the study found that the concentrations of fission products beyond 5 km radius was below the minimum detectable activity of the instruments used, implying that the monitored values were “insignificant”. The study has therefore focussed only on the concentrations of fission products and neutron-activated nuclides values within 5 km of each nuclear plant.
The gaseous waste that is released to the atmosphere through stacks consists of fission product noble gases, Argon 41, radioiodine, particulate radionuclides —cobalt-60, strontium-90, caesium-137 — and tritium. The liquid discharge consists of fission product radionuclides — radioiodine, tritium, strontium -90, caesium-137 — and activation products like cobalt-60. The radioactive discharges are carried out through dilution and dispersion and by “adhering to strict radiological and environmental regulatory regimes”.
As per the study, average gross alpha activity in air particulates at all the seven nuclear plants was less than 0.1 megabecquerel (mBq) per cubic metre. “Though these gross values in air particulates appeared to be nearly the same across all the nuclear power plants, the Narora atomic power station (NAPS) exhibited higher maximum values than the other nuclear plants. This was attributed to the higher atmospheric dust load at NAPS compared to the other sites,” the authors write.
In the case of specific marker, the average radionuclides (iodine-131, caesium-137, and strontium-90) in air particulates across all the seven sites and the average iodine-131 activity concentration was below 1 mBq per cubic metre, while in the case of caesium-137 and strontium-90, the average concentrations were three orders lower and below 10 microbecquerel per cubic metre, they write.
In the case of rivers and lakes, the concentration of caesium-137 and strontium-90 were below 5 mBq per litre, while the concentration was less than 50 megabecquerel per litre in sea water near the nuclear plants.
In the case of sediments, caesium-137 concentration was maximum in the case of the Rajasthan Atomic Power Station, while strontium-90 concentration in the sediments recorded a maximum in the Narora atomic power station sediments. “These values are within the statistical variation of values observed in natural sediments, and do not show any trend of deposition or accumulation of activity in the environment,” they note.
The higher levels of caesium-137 seen at the Rajasthan Atomic Power Station is “likely due to the accumulation of caesium-137 discharged to the water bodies through scavenging and sedimentation process and because of the high distribution coefficient of the sediment at this site,” they write.
The authors stress that tritium was found “detectable above the minimum detectable activity in all the sites except in the Kudankulam Nuclear Power Station”. In the case of the Kudankulam power plant, tritium was “not detected in any single time during the period of study”, while its concentration was “relatively higher” at the Rajasthan Atomic Power Station.
Though the total doses have been lower than the regulatory limits, the total dose at the Rajasthan atomic power station, Madras atomic station and Tarapur atomic power station have been relatively higher. This is because at both the Rajasthan and Madras power stations, the “air-cooled reactor assemblies result in activation of natural argon to radioactive argon-41” before being released into the environment. The nuclear power plants constructed after the Rajasthan and Madras stations use carbon-dioxide instead of air in the annulus space between the calandria tube and pressure tube. This results in reduced production and release of argon-41 by other power plants.
Even though the total doses of Rajasthan, Madras and Tarapur power plants are below the regulatory limits and thus deemed to be safe to the public, efforts are being taken at all three sites to limit the doses further so as to keep the doses as low as reasonably achievable (ALARA), they note.
Minimal radioactive discharges from Indian nuclear plants: study
While samples were collected and measured for maximum radius of 30 km of each nuclear plant, the concentrations of fission products beyond 5 km radius were below the minimum detectable activity of the instruments used.
Updated January 28, 2024, 12:00 am IST
By R. PRASAD
A cooling tower at the Rajasthan Atomic Power Station, RAPS-5 in Rawatbhatta, Rajasthan. File | Photo Credit: The Hindu.
Based on an analysis of radiological data of 20 years (2000-2020) from six nuclear power plants based in India, researchers at the Bhabha Atomic Research Centre (BARC), Mumbai have found that the radioactive discharges from the nuclear plants and the resultant potential environmental impact have been “minimal”. “The findings hold potential significance for reinforcing India’s commitment to advancing its nuclear power programme,” the authors write. “The minimal public doses underscore the safe operation of Indian nuclear power plants. The study’s findings have the potential to dispel unfounded beliefs, serving as a catalyst to reinforce India’s commitment to advancing its nuclear power programme, thus encouraging policymakers and the public to reconsider their perspectives.”
The period of study for the Kudankulam Nuclear Power Station is from 2013 to 2020. The other six power plants studied are: Tarapur Atomic Power Station, Madras Atomic Power Station, Kaiga Generating Station, Rajasthan Atomic Power Station, Narora Atomic Power Station, and Kakrapar Atomic Power Station. The results were published recently in the journal Science of the Total Environment.
While samples were collected and measured for a maximum radius of 30 km of each nuclear plant, the study found that the concentrations of fission products beyond 5 km radius was below the minimum detectable activity of the instruments used, implying that the monitored values were “insignificant”. The study has therefore focussed only on the concentrations of fission products and neutron-activated nuclides values within 5 km of each nuclear plant.
The gaseous waste that is released to the atmosphere through stacks consists of fission product noble gases, Argon 41, radioiodine, particulate radionuclides —cobalt-60, strontium-90, caesium-137 — and tritium. The liquid discharge consists of fission product radionuclides — radioiodine, tritium, strontium -90, caesium-137 — and activation products like cobalt-60. The radioactive discharges are carried out through dilution and dispersion and by “adhering to strict radiological and environmental regulatory regimes”.
As per the study, average gross alpha activity in air particulates at all the seven nuclear plants was less than 0.1 megabecquerel (mBq) per cubic metre. “Though these gross values in air particulates appeared to be nearly the same across all the nuclear power plants, the Narora atomic power station (NAPS) exhibited higher maximum values than the other nuclear plants. This was attributed to the higher atmospheric dust load at NAPS compared to the other sites,” the authors write.
In the case of specific marker, the average radionuclides (iodine-131, caesium-137, and strontium-90) in air particulates across all the seven sites and the average iodine-131 activity concentration was below 1 mBq per cubic metre, while in the case of caesium-137 and strontium-90, the average concentrations were three orders lower and below 10 microbecquerel per cubic metre, they write.
In the case of rivers and lakes, the concentration of caesium-137 and strontium-90 were below 5 mBq per litre, while the concentration was less than 50 megabecquerel per litre in sea water near the nuclear plants.
In the case of sediments, caesium-137 concentration was maximum in the case of the Rajasthan Atomic Power Station, while strontium-90 concentration in the sediments recorded a maximum in the Narora atomic power station sediments. “These values are within the statistical variation of values observed in natural sediments, and do not show any trend of deposition or accumulation of activity in the environment,” they note.
The higher levels of caesium-137 seen at the Rajasthan Atomic Power Station is “likely due to the accumulation of caesium-137 discharged to the water bodies through scavenging and sedimentation process and because of the high distribution coefficient of the sediment at this site,” they write.
The authors stress that tritium was found “detectable above the minimum detectable activity in all the sites except in the Kudankulam Nuclear Power Station”. In the case of the Kudankulam power plant, tritium was “not detected in any single time during the period of study”, while its concentration was “relatively higher” at the Rajasthan Atomic Power Station.
Though the total doses have been lower than the regulatory limits, the total dose at the Rajasthan atomic power station, Madras atomic station and Tarapur atomic power station have been relatively higher. This is because at both the Rajasthan and Madras power stations, the “air-cooled reactor assemblies result in activation of natural argon to radioactive argon-41” before being released into the environment. The nuclear power plants constructed after the Rajasthan and Madras stations use carbon-dioxide instead of air in the annulus space between the calandria tube and pressure tube. This results in reduced production and release of argon-41 by other power plants.
Even though the total doses of Rajasthan, Madras and Tarapur power plants are below the regulatory limits and thus deemed to be safe to the public, efforts are being taken at all three sites to limit the doses further so as to keep the doses as low as reasonably achievable (ALARA), they note.
Minimal radioactive discharges from Indian nuclear plants: study
Top brass of NPCIL, Russian suppliers to meet at Kudankulam; expected to discuss acceleration of ongoing reactor construction.
The meeting is also expected to discuss construction of ‘Away From Reactor’ facility for storing the spent fuel getting generated in the two operational reactors.
February 06, 2024
07:25 pm IST - TIRUNELVELI
By P. SUDHAKAR
Kudankulam nuclear power plants. File | Photo Credit: SPECIAL ARRANGEMENT
The top brass of Nuclear Power Corporation of India Limited (NPCIL), which is constructing and operating nuclear power plants across the country and Atomstroyexport, Russian Federation’s nuclear power equipment supplier and service provider, are scheduled to meet at Kudankulam Nuclear Power Project (KKNPP) on Wednesday and Thursday (February 7 and 8) to review the progress of the ongoing construction of KKNPP reactors 3 to 6.
With the Atomstroyexport’s technical knowhow, the NPCIL has built 2x 1000 MWe VVER (water-cooled, water-moderated reactors) at the cost of ₹17,270 crore, which are operational now at KKNPP, and is constructing four more VVER-type reactors with similar capacity on the same premises. While more than 70% of the construction of reactors 3 and 4 has been completed as the work was started in June 2017, the remaining two reactors have crossed 40% of the construction.
Though NPCIL and Atomstroyexport want to complete the projects and commission the reactors as planned, the supply of certain critical components from Russia is getting delayed. This high-level meeting is expected to weed-out the delays in future and accelerate the ongoing construction, sources in KKNPP said.
While Chairman and Managing Director of NPCIL Bhuvan Chandra Pathak arrived at KKNPP on Tuesday afternoon, Chairman of Atomic Energy Commission and Secretary, Department of Atomic Energy, Ajit Kumar Mohanty is expected to reach the site on Wednesday along with a team of high-level delegates to hold talks with the Atomstroyexport representatives.
“The duration of construction of a VVER – 1,000 nuclear reactor is normally five years, which may spill over a bit due to some unexpected delays. However, the construction of reactors 3 and 4, which started in mid-2017 and suffered huge delay due to COVID-19 outbreak, has to be expedited to ensure its commissioning at least within a year. So, this all-important meeting is expected to draw some concrete plans and schedules for the supply of equipment from Russia for the early commissioning of reactors 3 and 4,” said a source.
The meeting is also expected to discuss construction of ‘Away From Reactor’ facility for storing the spent fuel getting generated in the two operational reactors.
“The Russians, who initially supplied UTVS fuel system with the fuel cycle of 12 months for the first reactors, upgraded it by supplying new, advanced and more reliable TVS – 2 M fuel systems which increased the fuel cycle to 18 months. It means that the reactor has to be stopped once in 18 months instead of 12 months for removal of spent fuel and refuelling. Then we are supplied Advanced Technology Fuel with the fuel cycle of 24 months. It is the testimony to the close coordination and understanding between NPCIL and Atomstroyexport. So, we are hopeful of strengthening the ties and cooperation further by removing obstacles, if any, during the discussions,” said the sources.
When asked about the possible construction of more reactors on KKNPP campus as informed by Minister for External Affairs Jaishankar during his recent visit to Russia, an official said: “I don’t have any information about it”.
Top brass of NPCIL, Russian suppliers to meet at Kudankulam; expected to discuss acceleration of ongoing reactor construction
The meeting is also expected to discuss construction of ‘Away From Reactor’ facility for storing the spent fuel getting generated in the two operational reactors.
February 06, 2024
07:25 pm IST - TIRUNELVELI
By P. SUDHAKAR
Kudankulam nuclear power plants. File | Photo Credit: SPECIAL ARRANGEMENT
The top brass of Nuclear Power Corporation of India Limited (NPCIL), which is constructing and operating nuclear power plants across the country and Atomstroyexport, Russian Federation’s nuclear power equipment supplier and service provider, are scheduled to meet at Kudankulam Nuclear Power Project (KKNPP) on Wednesday and Thursday (February 7 and 8) to review the progress of the ongoing construction of KKNPP reactors 3 to 6.
With the Atomstroyexport’s technical knowhow, the NPCIL has built 2x 1000 MWe VVER (water-cooled, water-moderated reactors) at the cost of ₹17,270 crore, which are operational now at KKNPP, and is constructing four more VVER-type reactors with similar capacity on the same premises. While more than 70% of the construction of reactors 3 and 4 has been completed as the work was started in June 2017, the remaining two reactors have crossed 40% of the construction.
Though NPCIL and Atomstroyexport want to complete the projects and commission the reactors as planned, the supply of certain critical components from Russia is getting delayed. This high-level meeting is expected to weed-out the delays in future and accelerate the ongoing construction, sources in KKNPP said.
While Chairman and Managing Director of NPCIL Bhuvan Chandra Pathak arrived at KKNPP on Tuesday afternoon, Chairman of Atomic Energy Commission and Secretary, Department of Atomic Energy, Ajit Kumar Mohanty is expected to reach the site on Wednesday along with a team of high-level delegates to hold talks with the Atomstroyexport representatives.
“The duration of construction of a VVER – 1,000 nuclear reactor is normally five years, which may spill over a bit due to some unexpected delays. However, the construction of reactors 3 and 4, which started in mid-2017 and suffered huge delay due to COVID-19 outbreak, has to be expedited to ensure its commissioning at least within a year. So, this all-important meeting is expected to draw some concrete plans and schedules for the supply of equipment from Russia for the early commissioning of reactors 3 and 4,” said a source.
The meeting is also expected to discuss construction of ‘Away From Reactor’ facility for storing the spent fuel getting generated in the two operational reactors.
“The Russians, who initially supplied UTVS fuel system with the fuel cycle of 12 months for the first reactors, upgraded it by supplying new, advanced and more reliable TVS – 2 M fuel systems which increased the fuel cycle to 18 months. It means that the reactor has to be stopped once in 18 months instead of 12 months for removal of spent fuel and refuelling. Then we are supplied Advanced Technology Fuel with the fuel cycle of 24 months. It is the testimony to the close coordination and understanding between NPCIL and Atomstroyexport. So, we are hopeful of strengthening the ties and cooperation further by removing obstacles, if any, during the discussions,” said the sources.
When asked about the possible construction of more reactors on KKNPP campus as informed by Minister for External Affairs Jaishankar during his recent visit to Russia, an official said: “I don’t have any information about it”.
Top brass of NPCIL, Russian suppliers to meet at Kudankulam; expected to discuss acceleration of ongoing reactor construction