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India's three-stage nuclear power programme was formulated by Homi Bhabha, the well-known physicist, in the 1950s to secure the country's long term
energy independence Energy independence is independence or autarky regarding energy resources, energy supply and/or energy generation by the energy industry. Energy dependence, in general, refers to mankind's general dependence on either primary or secondary ene ...
, through the use of
uranium Uranium is a chemical element with the symbol U and atomic number 92. It is a silvery-grey metal in the actinide series of the periodic table. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. Uranium is weak ...
and
thorium Thorium is a weakly radioactive metallic chemical element with the symbol Th and atomic number 90. Thorium is silvery and tarnishes black when it is exposed to air, forming thorium dioxide; it is moderately soft and malleable and has a high ...
reserves found in the
monazite Monazite is a primarily reddish-brown phosphate mineral that contains rare-earth elements. Due to variability in composition, monazite is considered a group of minerals. The most common species of the group is monazite-(Ce), that is, the ceriu ...
sands of coastal regions of
South India South India, also known as Dakshina Bharata or Peninsular India, consists of the peninsular southern part of India. It encompasses the Indian states of Andhra Pradesh, Karnataka, Kerala, Tamil Nadu, and Telangana, as well as the union territ ...
. The ultimate focus of the programme is on enabling the thorium reserves of India to be utilised in meeting the country's energy requirements. Thorium is particularly attractive for India, as India has only around 1–2% of the global
uranium reserves Uranium is a chemical element with the Symbol (chemistry), symbol U and atomic number 92. It is a silvery-grey metal in the actinide series of the periodic table. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. ...
, but one of the largest shares of global thorium reserves at about 25% of the world's known thorium reserves. However, thorium is more difficult to use than uranium as a fuel because it requires
breeding Breeding is sexual reproduction that produces offspring, usually animals or plants. It can only occur between a male and a female animal or plant. Breeding may refer to: * Animal husbandry, through selected specimens such as dogs, horses, and ra ...
, and global uranium prices remain low enough that breeding is not cost effective. India published about twice the number of papers on thorium as its nearest competitors, during each of the years from 2002 to 2006. 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. The first Prototype Fast Breeder Reactor has been repeatedly delayed – and is currently expected to be commissioned by October 2022 – and India continues to import thousands of tonnes of uranium from Russia, Kazakhstan, France, and Uzbekistan. The 2005 Indo–US Nuclear Deal and the NSG waiver, which ended more than three decades of international isolation of the Indian civil nuclear programme, have created many hitherto unexplored alternatives for the success of the three-stage nuclear power programme.


Origin and rationale

Homi Bhabha conceived of the three-stage nuclear programme as a way to develop nuclear energy by working around India's limited uranium resources. Thorium itself is not a
fissile In nuclear engineering, fissile material is material capable of sustaining a nuclear fission chain reaction. By definition, fissile material can sustain a chain reaction with neutrons of thermal energy. The predominant neutron energy may be t ...
material, and thus cannot undergo fission to produce energy. Instead, it must be transmuted to
uranium-233 Uranium-233 (233U or U-233) is a fissile isotope of uranium that is bred from thorium-232 as part of the thorium fuel cycle. Uranium-233 was investigated for use in nuclear weapons and as a reactor fuel. It has been used successfully in exp ...
in a reactor fueled by other fissile materials. The first two stages, natural uranium-fueled heavy water reactors and plutonium-fueled fast breeder reactors, are intended to generate sufficient fissile material from India's limited uranium resources, so that all its vast thorium reserves can be fully utilised in the third stage of thermal breeder reactors. Bhabha summarised the rationale for the three-stage approach as follows: In November 1954, Bhabha presented the three-stage plan for national development, at the conference on "Development of Atomic Energy for Peaceful Purposes" which was also attended by India's first
Prime Minister A prime minister, premier or chief of cabinet is the head of the cabinet and the leader of the ministers in the executive branch of government, often in a parliamentary or semi-presidential system. Under those systems, a prime minister i ...
Jawaharlal Nehru Pandit Jawaharlal Nehru (; ; ; 14 November 1889 – 27 May 1964) was an Indian anti-colonial nationalist, secular humanist, social democrat— * * * * and author who was a central figure in India during the middle of the 20t ...
. Four years later in 1958, the Indian government formally adopted the three-stage plan. Indian energy resource base was estimated to be capable of yielding a total electric power output of the order shown in the table below. Indian government recognised that thorium was a source that could provide power to the Indian people for the long term.


Fuel reserves and research capability

According to a report issued by the
IAEA The International Atomic Energy Agency (IAEA) is an intergovernmental organization that seeks to promote the peaceful use of nuclear energy and to inhibit its use for any military purpose, including nuclear weapons. It was established in 195 ...
, India has limited uranium reserves, consisting of approximately 54,636 tonnes of "reasonably assured resources", 25,245 tonnes of "estimated additional resources", 15,488 tonnes of "undiscovered conventional resources, and 17,000 tonnes of "speculative resources". According to
NPCIL The Nuclear Power Corporation of India Limited (NPCIL) is an Indian public sector undertaking based in Mumbai, Maharashtra. It is wholly owned by the Government of India and is responsible for the generation of electricity from nuclear power. ...
, these reserves are only sufficient to generate about 10 GWe for about 40 years. In July 2011, it was reported that a four-year-long mining survey done at Tummalapalle mine in
Kadapa Kadapa (colonial spelled Cuddapah) is a city in the southern part of Andhra Pradesh, India. It is located in the Rayalaseema region, and is the district headquarters of YSR Kadapa district. As of the 2022 Census of India, the city had a popul ...
district near
Hyderabad Hyderabad ( ; , ) is the capital and largest city of the Indian state of Telangana and the ''de jure'' capital of Andhra Pradesh. It occupies on the Deccan Plateau along the banks of the Musi River, in the northern part of Southern India ...
had yielded confirmed reserve figure of 49,000 tonnes with a potential that it could rise to 150,000 tonnes. This was a rise from an earlier estimate of 15,000 tonnes for that area. Although India has only around 1–2% of the global
uranium reserves Uranium is a chemical element with the Symbol (chemistry), symbol U and atomic number 92. It is a silvery-grey metal in the actinide series of the periodic table. A uranium atom has 92 protons and 92 electrons, of which 6 are valence electrons. ...
, thorium reserves are bigger; around 12–33% of global reserves, according to IAEA and US Geological Survey. Several in-depth independent studies put Indian thorium reserves at 30% of the total world thorium reserves. Indian uranium production is constrained by government investment decisions rather than by any shortage of ore. As per official estimates shared in the country's Parliament in August 2011, the country can obtain 846,477 tonnes of thorium from 963,000 tonnes of ThO2, which in turn can be obtained from 10.7 million tonnes of
monazite Monazite is a primarily reddish-brown phosphate mineral that contains rare-earth elements. Due to variability in composition, monazite is considered a group of minerals. The most common species of the group is monazite-(Ce), that is, the ceriu ...
occurring in beaches and river sands in association with other heavy metals. Indian monazite contains about 9–10% ThO2. The 846,477 tonne figure compares with the earlier estimates for India, made by IAEA and US Geological Survey of 319,000 tonnes and 290,000 to 650,000 tonnes respectively. The 800,000 tonne figure is given by other sources as well. It was further clarified in the country's
parliament In modern politics, and history, a parliament is a legislative body of government. Generally, a modern parliament has three functions: representing the electorate, making laws, and overseeing the government via hearings and inquiries. Th ...
on 21 March 2012 that, "Out of nearly 100 deposits of the heavy minerals, at present only 17 deposits containing about 4 million tonnes of monazite have been identified as exploitable. Mine-able reserves are ~70% of identified exploitable resources. Therefore, about 225,000 tonnes of thorium metal is available for nuclear power program." India is a leader of thorium based research. It is also by far the most committed nation as far as the use of thorium fuel is concerned, and no other country has done as much neutron physics work on thorium. The country published about twice the number of papers on thorium as its nearest competitors during each of the years from 2002 to 2006.
Bhabha Atomic Research Centre The Bhabha Atomic Research Centre (BARC) is India's premier nuclear research facility, headquartered in Trombay, Mumbai, Maharashtra, India. It was founded by Homi Jehangir Bhabha as the Atomic Energy Establishment, Trombay (AEET) in January 1 ...
(BARC) had the highest number of publications in the thorium area, across all research institutions in the world during the period 1982–2004. During this same period, India ranks an overall second behind the United States in the research output on Thorium. According to
Siegfried Hecker Siegfried S. Hecker (born October 2, 1943) is an American metallurgist and nuclear scientist. He served as Director of the Los Alamos National Laboratory from 1986 to 1997 and is now affiliated with Stanford University, where he is research pro ...
, a former director (1986–1997) of the
Los Alamos National Laboratory Los Alamos National Laboratory (often shortened as Los Alamos and LANL) is one of the sixteen research and development laboratories of the United States Department of Energy (DOE), located a short distance northwest of Santa Fe, New Mexico, ...
in the United States, "India has the most technically ambitious and innovative nuclear energy programme in the world. The extent and functionality of its nuclear experimental facilities are matched only by those in Russia and are far ahead of what is left in the US." However, conventional uranium-fueled reactors are much cheaper to operate; so India imports large quantities of uranium from abroad. Also, in March 2011, large deposits of uranium were discovered in the Tummalapalle belt in the southern part of the Kadapa basin in Andhra Pradesh.


Stage I – Pressurised Heavy Water Reactor

In the first stage of the programme, natural uranium fueled
pressurised heavy water reactor A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water ( deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently use natural uranium as fuel, but sometimes also use very low enriched uranium. The ...
s (PHWR) produce electricity while generating
plutonium-239 Plutonium-239 (239Pu or Pu-239) is an isotope of plutonium. Plutonium-239 is the primary fissile isotope used for the production of nuclear weapons, although uranium-235 is also used for that purpose. Plutonium-239 is also one of the three mai ...
as by-product. PHWRs was a natural choice for implementing the first stage because it had the most efficient reactor design in terms of uranium utilisation, and the existing Indian infrastructure in the 1960s allowed for quick adoption of the PHWR technology. India correctly calculated that it would be easier to create heavy water production facilities (required for PHWRs) than uranium enrichment facilities (required for LWRs). Natural uranium contains only 0.7% of the fissile isotope
uranium-235 Uranium-235 (235U or U-235) is an isotope of uranium making up about 0.72% of natural uranium. Unlike the predominant isotope uranium-238, it is fissile, i.e., it can sustain a nuclear chain reaction. It is the only fissile isotope that exi ...
. Most of the remaining 99.3% is uranium-238 which is not fissile but can be converted in a reactor to the fissile isotope plutonium-239. Heavy water ( deuterium oxide, D2O) is used as moderator and
coolant A coolant is a substance, typically liquid, that is used to reduce or regulate the temperature of a system. An ideal coolant has high thermal capacity, low viscosity, is low-cost, non-toxic, chemically inert and neither causes nor promotes corrosi ...
. Since the program began, India has developed a series of sequentially larger PHWR's under the
IPHWR The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors bu ...
series derived from the original Canadian supplied CANDU reactors. The IPHWR series consists of three designs of 220 MWe, 540 MWe and 700 MWe capacity under the designations
IPHWR-220 The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. It is a Generation II reactor developed from earlier CANDU based RAPS-1 and RAPS-2 reactors b ...
, IPHWR-540 and IPHWR-700 respectively. Indian uranium reserves are capable of generating a total power capacity of 420 GWe-years, but the Indian government limited the number of PHWRs fueled exclusively by indigenous uranium reserves, in an attempt to ensure that existing plants get a lifetime supply of uranium. US analysts calculate this limit as being slightly over 13 GW in capacity. Several other sources estimate that the known reserves of natural uranium in the country permit only about 10 GW of capacity to be built through indigenously fueled PHWRs. The three-stage programme explicitly incorporates this limit as the upper cut off of the first stage, beyond which PHWRs are not planned to be built. Almost the entire existing base of Indian nuclear power (4780 MW) is composed of first stage PHWRs of the
IPHWR The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors bu ...
series, with the exception of the two
Boiling Water Reactor A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is a design different from a Soviet graphite-moderated RBMK. It is the second most common type of electricity-generating nu ...
(BWR) units at Tarapur. The installed capacity of Kaiga station is now 880 MW consisting of four 220 MWe
IPHWR-220 The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. It is a Generation II reactor developed from earlier CANDU based RAPS-1 and RAPS-2 reactors b ...
reactors, making it the third largest after Tarapur (1400 MW) (2 x BWR Mark-1, 2 x IPHWR-540) and
Rawatbhata Rawatbhata is a city, Tehsil and Nagar Palika in Chittorgarh District, Rajasthan, India. It is 131 km from Chittorgarh city, 50 km from the nearest city, Kota. The city has eight nuclear power stations, an under-construction nuclear fuel ...
(1180 MW) (2 x CANDU, 2 x
IPHWR-220 The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. It is a Generation II reactor developed from earlier CANDU based RAPS-1 and RAPS-2 reactors b ...
). The remaining three power stations at Kakrapar,
Kalpakkam Kalpakkam is a township in Tamil Nadu, India, situated on the Coromandel Coast 70 kilometres south of Chennai. A conglomerate of two villages (Puduppattinam and Sadurangappatinam) and a DAE township, it is about from Thiruvanmiyur and fr ...
and Narora all have 2 units of 220 MWe, thus contributing 440 MW each to the grid. The 2 units of 700 MWe each ( IPHWR-700) that are under construction at both Kakrapar and
Rawatbhata Rawatbhata is a city, Tehsil and Nagar Palika in Chittorgarh District, Rajasthan, India. It is 131 km from Chittorgarh city, 50 km from the nearest city, Kota. The city has eight nuclear power stations, an under-construction nuclear fuel ...
, and the one planned for Banswara would also come under the first stage of the programme, totalling a further addition of 4200 MW. These additions will bring the total power capacity from the first stage PHWRs to near the total planned capacity of 10 GW called for by the three-stage power programme. Capital costs of PHWRs is in the range of Rs. 6 to 7 crore ($1.2 to $1.4 million) per MW, coupled with a designed plant life of 40 years. Time required for construction has improved over time and is now at about 5 years. Tariffs of the operating plants are in the range of Rs. 1.75 to 2.80 per unit, depending on the life of the reactor. In the year 2007–08 the average tariff was Rs. 2.28. India is also working on the design of reactors based on the more efficient
Pressurized Water Reactor A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs constitute the large majority of the world's nuclear power plants (with notable exceptions being the UK, Japan and Canada). In a PWR, the primary coolant (water) i ...
technology derived from the work on the Arihant-class submarine program to develop a 900 MWe
IPWR-900 The Indian Pressurized Water Reactor-900 (IPWR-900) is a class of pressurized water reactors being designed by Bhabha Atomic Research Centre (BARC) in partnership with Nuclear Power Corporation of India Limited to supplement the Indian three- ...
reactor platform to supplement the currently deployed
PHWR A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water ( deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently use natural uranium as fuel, but sometimes also use very low enriched uranium. T ...
's of the
IPHWR The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors bu ...
series.


Stage II – Fast Breeder Reactor

In the second stage, fast breeder reactors (FBRs) would use a mixed oxide (MOX) fuel made from
plutonium-239 Plutonium-239 (239Pu or Pu-239) is an isotope of plutonium. Plutonium-239 is the primary fissile isotope used for the production of nuclear weapons, although uranium-235 is also used for that purpose. Plutonium-239 is also one of the three mai ...
, recovered by reprocessing spent fuel from the first stage, and natural uranium. In FBRs, plutonium-239 undergoes fission to produce energy, while the uranium-238 present in the mixed oxide fuel transmutes to additional plutonium-239. Thus, the Stage II FBRs are designed to "breed" more fuel than they consume. Once the inventory of plutonium-239 is built up thorium can be introduced as a blanket material in the reactor and transmuted to
uranium-233 Uranium-233 (233U or U-233) is a fissile isotope of uranium that is bred from thorium-232 as part of the thorium fuel cycle. Uranium-233 was investigated for use in nuclear weapons and as a reactor fuel. It has been used successfully in exp ...
for use in the third stage. The surplus plutonium bred in each fast reactor can be used to set up more such reactors, and might thus grow the Indian civil nuclear power capacity till the point where the third stage reactors using thorium as fuel can be brought online, which is forecasted as being possible once 50 GW of nuclear power capacity has been achieved. The uranium in the first stage PHWRs that yield 29 EJ of energy in the once-through fuel cycle, can be made to yield between 65 and 128 times more energy through multiple cycles in fast breeder reactors. The design of the country's first fast breeder, called
Prototype Fast Breeder Reactor The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe fast breeder nuclear reactor presently being constructed at the Madras Atomic Power Station (MAPS) in Kalpakkam, India. The Indira Gandhi Centre for Atomic Research (IGCAR) is responsible f ...
(PFBR), was done by Indira Gandhi Centre for Atomic Research (IGCAR). Bharatiya Nabhikiya Vidyut Nigam Ltd (Bhavini), a public sector company under the Department of Atomic Energy (DAE), has been given the responsibility to build the fast breeder reactors in India. The construction of this
PFBR The Prototype Fast Breeder Reactor (PFBR) is a 500 MWe fast breeder nuclear reactor presently being constructed at the Madras Atomic Power Station (MAPS) in Kalpakkam, India. The Indira Gandhi Centre for Atomic Research (IGCAR) is responsibl ...
at
Kalpakkam Kalpakkam is a township in Tamil Nadu, India, situated on the Coromandel Coast 70 kilometres south of Chennai. A conglomerate of two villages (Puduppattinam and Sadurangappatinam) and a DAE township, it is about from Thiruvanmiyur and fr ...
was due to be completed in 2012. It is not yet complete. The date of commission has been delayed to October 2022 from the previous date in 2019.


Doubling time

Doubling time refers to the time required to extract as output, double the amount of fissile fuel, which was fed as input into the breeder reactors. This metric is critical for understanding the time durations that are unavoidable while transitioning from the second stage to the third stage of Bhabha's plan, because building up a sufficiently large fissile stock is essential to the large deployment of the third stage. In Bhabha's 1958 papers on role of thorium, he pictured a doubling time of 5–6 years for breeding U-233 in the Th–U233 cycle. This estimate has now been revised to 70 years due to technical difficulties that were unforeseen at the time. Despite such setbacks, according to publications done by DAE scientists, the doubling time of fissile material in the fast breeder reactors can be brought down to about 10 years by choosing appropriate technologies with short doubling time. Another report prepared for U.S. Department of Energy suggests a doubling time of 22 years for oxide fuel, 13 years for carbide fuel and 10 years for metal fuel.


Stage III – Thorium Based Reactors

A Stage III reactor or an Advanced nuclear power system involves a self-sustaining series of
thorium-232 Thorium-232 () is the main naturally occurring isotope of thorium, with a relative abundance of 99.98%. It has a half life of 14 billion years, which makes it the longest-lived isotope of thorium. It decays by alpha decay to radium-228; its decay ...
uranium-233 Uranium-233 (233U or U-233) is a fissile isotope of uranium that is bred from thorium-232 as part of the thorium fuel cycle. Uranium-233 was investigated for use in nuclear weapons and as a reactor fuel. It has been used successfully in exp ...
fuelled reactors. This would be a thermal breeder reactor, which in principle can be refueled – after its initial fuel charge – using only naturally occurring thorium. According to the three-stage programme, Indian nuclear energy could grow to about 10 GW through PHWRs fueled by domestic uranium, and the growth above that would have to come from FBRs till about 50GW. The third stage is to be deployed only after this capacity has been achieved. According to replies given in Q&A in the Indian Parliament on two separate occasions, 19 August 2010 and 21 March 2012, large scale thorium deployment is only to be expected "3–4 decades after the commercial operation of fast breeder reactors with short doubling time". Full exploitation of India's domestic thorium reserves will likely not occur until after the year 2050.


Parallel approaches

As there is a long delay before direct thorium utilisation in the three-stage programme, the country is looking at reactor designs that allow more direct use of thorium in parallel with the sequential three-stage programme. Three options under consideration are the Indian Accelerator Driven Systems (IADS),
Advanced Heavy Water Reactor The advanced heavy-water reactor (AHWR) or AHWR-300 is the latest Indian design for a next-generation nuclear reactor that burns thorium in its fuel core. It is slated to form the third stage in India's three-stage fuel-cycle plan. This phase ...
(AHWR) and Compact High Temperature Reactor.
Molten Salt Reactor A molten salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a molten salt mixture. Only two MSRs have ever operated, both research reactors in the United States. The 1950's ...
may also be under consideration based on some recent reports and is under development.


Advanced Heavy Water Reactor (AHWR)

Of the options, the design for AHWR is ready for deployment. AHWR is a 300 MWe vertical pressure tube type, boiling light water cooled and heavy water moderated reactor, using uranium233–thorium MOX and plutonium–thorium MOX. It is expected to generate 65% of its power from thorium and can also be configured to accept other fuel types in full core including enriched uranium and uranium–plutonium MOX. There was a plan for constructing such an AHWR with a plutonium–thorium core combination in 2007. This AHWR design was sent for an independent pre-licensing design safety review by the Atomic Energy Regulatory Board (AERB), the results of which were deemed satisfactory. AHWR would offer very little growth for the fuel build up that is essential for wide deployment of the third stage, and perhaps the impact on the accumulated fissile material could even be negative. The AHWR design that will be taken up for construction is to be fueled with 20%
low enriched uranium Enriched uranium is a type of uranium in which the percent composition of uranium-235 (written 235U) has been increased through the process of isotope separation. Naturally occurring uranium is composed of three major isotopes: uranium-238 (238 ...
(LEU) and 80% thorium. The low enriched uranium (LEU) for this AHWR design is readily available on the world market. As of November 2011, construction will start after the site is identified in 6 months time. It will take another 18 months to get clearances on regulatory and environmental grounds. Construction is estimated to take six years. If everything goes according to plan, AHWR could be operational in India by 2020. In Aug 2017 the AHWR location was still not announced.


Accelerator Driven System

India's Department of Atomic Energy and US's
Fermilab Fermi National Accelerator Laboratory (Fermilab), located just outside Batavia, Illinois, near Chicago, is a United States Department of Energy national laboratory specializing in high-energy particle physics. Since 2007, Fermilab has been opera ...
are designing unique first-of-its-kind accelerator driven systems. No country has yet built an Accelerator Driven System for power generation. Dr Anil Kakodkar, former chairman of the Atomic Energy Commission called this a mega science project and a "necessity" for humankind.


Indian Molten Salt Breeder Reactor (IMSBR)

The Indian Molten Salt Breeder Reactor (IMSBR) is under development. Studies on conceptual design of the Indian Molten Salt Breeder Reactors (IMSBR) have been initiated.


Linkages with the Indo–US nuclear deal

In spite of the overall adequacy of its uranium reserves, Indian power plants could not get the necessary amount of uranium to function at full capacity in the late 2000s, primarily due to inadequate investments made in the uranium mining and milling capacity resulting from fiscal austerity in the early 1990s. One study done for U.S. Congress in that time period reaches the conclusion, "India’s current fuel situation means that New Delhi cannot produce sufficient fuel for both its nuclear weapons programme and its projected civil nuclear programme." An independent study arrives at roughly the same conclusion, "India’s current uranium production of less than 300 tons/year can meet at most, two-thirds of its needs for civil and military nuclear fuel." This uranium shortfall during the deal negotiations was understood by both players to be a temporary aberration that was poised to be resolved with requisite investments in India's uranium milling infrastructure.


Drivers for the deal from the Indian side

It was estimated that after attaining 21 GW from nuclear power by 2020, further growth might require imported uranium. This is problematic because deployment of third stage requires that 50 GW be already established through the first and second stages. If imported uranium was made available, Department of Atomic Energy (DAE) estimated that India could reach 70 GW by 2032 and 275 GW by 2052. In such a scenario, the third stage could be made operational following the fast breeder implementation, and nuclear power capacity could grow to 530 GW. The estimated stagnation of the nuclear power at about 21GW by 2020 is likely due to the fact that even the short "doubling time" of the breeder reactors is quite slow, on the order of 10–15 years. Implementing the three-stage programme using the domestic uranium resources alone is feasible, but requires several decades to come to fruition. Imports of fissile material from outside would considerably speed up the programme. As per research data, the U238–Pu cycle has the shortest doubling time by a large margin, and that technology's compounded yearly fissile material growth rate has been calculated as follows, after making some basic assumptions about the operating features of the fast breeder reactors. Indian power generation capacity has grown at 5.9% per annum in the 25-year period prior to 2006. If Indian economy is to grow at 8–9% for the next 25-year period of 2006 to 2032, total power generation capacity has to increase at 6–7% per annum. As the fissile material growth rate does not meet this objective, it becomes necessary to look at alternative approaches for obtaining the fissile material. This conclusion is mostly independent of future technical breakthroughs, and complementary to the eventual implementation of the three-stage approach. It was realised that the best way to get access to the requisite fissile material would be through uranium imports, which was not possible without ending India's nuclear isolation by U.S. and the NSG. U.S. analyst Ashley J. Tellis argues that the Indo–US nuclear deal is attractive to India because it gives it access to far more options on its civil nuclear programme than would otherwise be the case, primarily by ending its isolation from the international nuclear community. These options include access to latest technologies, access to higher unit output reactors which are more economical, access to global finance for building reactors, ability to export its indigenous small reactor size PHWRs, better information flow for its research community, etc. Finally, the deal also gives India two options that are relatively independent from the three-stage programme, at least in terms of their dependencies on success or failure. The first option is that, India can opt to stay with the first stage reactors as long as the global supply of uranium lasts. The plus side of this is that it covers any risk from short term delays or failures in implementing the three-stage programme. On the negative side, this is an option that is antithetical to the underlying objective of energy independence through the exploitation of thorium. The second option, and perhaps the more interesting one, is that India can choose to access the third stage of thorium reactors by skipping the more difficult second stage of the plan through some appropriately selected parallel approach such as the
high-temperature gas-cooled reactor A high-temperature gas-cooled reactor (HTGR), is a nuclear reactor that uses a graphite moderator with a once-through uranium fuel cycle. The HTGR is a type of high-temperature reactor (HTR) that can conceptually have an outlet temperature of ...
, the
molten salt reactor A molten salt reactor (MSR) is a class of nuclear fission reactor in which the primary nuclear reactor coolant and/or the fuel is a molten salt mixture. Only two MSRs have ever operated, both research reactors in the United States. The 1950's ...
, or the various accelerator driven systems.


Stakeholder views on the linkages

Indian commentators welcomed the opportunity simply because they could see that India would be able end its international isolation on the nuclear front and obtain a de facto acknowledgement of it as a nuclear weapon state to some degree, in addition to it being able to obtain the uranium that would increase the success potential of its three-stage programme as well as its efforts to build a "minimum credible nuclear deterrent". It was estimated that the power produced by imported reactors could be 50% more expensive than the country's existing nuclear power cost. However, this was perceived as a minor point in the larger context of the deal. In a U.S. Senate Foreign Relations Committee hearing, Under Secretary for Political Affairs Nicholas Burns' prepared remarks stated that "India had made this the central issue in the new partnership developing between our countries". Indian government proceeded to negotiate and execute the Indo–US Nuclear Deal, which then paved the way for the NSG waiver on international uranium imports to India in 2008. According to one foreign analyst, the deal could "over time… result in India being weaned away from its… three-phase nuclear program involving FBRs and advanced PHWRs. This would occur should India become confident that it would have assured supplies of relatively cheap natural uranium, including from Australia. Of course, nobody in the Indian nuclear establishment would yet admit to that possibility." Anil Kakodkar, then Chairman of the Atomic Energy Commission, went to the extent of making public, the milder position of keeping the country's indigenous fast breeder programme out of the ambit of international safeguards, saying "in the long run, the energy that will come out from the nuclear fuel resources available in India (from domestic uranium and thorium mines) should always form the larger share of the nuclear energy programme..." and "our strategy should be such that the integrity and autonomy of our being able to develop the three-stage nuclear power programme, be maintained, we cannot compromise that." The full demand of the Indian scientists, to have the ability to reprocess plutonium from spent fuel of the imported reactors (goes beyond the defensive position of Kakodkar), appears to have been met in the final deal. According to the Indian government's official position, India's indigenous three-stage nuclear power programme is unaffected by the Indo–US Nuclear Deal; "Its full autonomy has been preserved." Both right and left-wing political parties opposed the deal in the Parliament. The left feared the deal would make the country subservient to U.S. interests, while the right felt it would limit further nuclear testing. According to one view within the Indian defence establishment, the deal "has for all practical purposes capped Indian ability to field test and proof high yield nuclear weapons till some time in future (about 20 years) when Indian three-stage nuclear fuel cycle based on Thorium fuel matures into mainstream power production, thus eliminating Indian dependence on imported nuclear fuel from NSG countries or if there is a breakout in global nuclear test moratorium."


Indian nuclear energy forecasts

On the basis of the three-stage plan and assuming optimistic development times, some extravagant predictions about nuclear power have been made over the years:
Bhabha announced that there would be 8,000 MW of nuclear power in the country by 1980. As the years progressed, these predictions were to increase. By 1962, the prediction was that nuclear energy would generate 20,000–25,000 MW by 1987, and by 1969, the AEC predicted that by 2000 there would be 43,500 MW of nuclear generating capacity. All of this was before a single unit of nuclear electricity was produced in the country. Reality was quite different. Installed capacity in 1979–80 was about 600 MW, about 950 MW in 1987, and 2720 MW in 2000.
In 2007, after five decades of sustained and generous government financial support, nuclear power's capacity was just 3,310 MW, less than 3% of India's total power generation capacity. The Integrated Energy Policy of India estimates the share of nuclear power in the total primary energy mix to be between 4% to 6.4% in various scenarios by the year 2031–32. A study by the DAE, estimates that the nuclear energy share will be about 8.6% by the year 2032 and 16.6% by the year 2052. The possible nuclear power capacity beyond the year 2020 has been estimated by DAE is shown in the table. The 63 GW expected by 2032 will be achieved by setting up 16 indigenous Pressurised Heavy Water Reactors (PHWR), of which ten is to be based on reprocessed uranium. Out of the 63 GW, about 40 GW will be generated through the imported Light Water Reactors (LWR), made possible after the NSG waiver. Indian Prime Minister Manmohan Singh stated in 2009 that the nation could generate up to 470 GW of power by 2050 if it managed the three-stage program well. "This will sharply reduce our dependence on fossil fuels and will be a major contribution to global efforts to combat climate change", he reportedly said. According to plan, 30% of the Indian electricity in 2050 will be generated from thorium based reactors. Indian nuclear scientists estimate that the country could produce 500 GWe for at least four centuries using just the country's economically extractable thorium reserves.


Thorium energy forecasts

According to the Chairman of India's Atomic Energy Commission, Srikumar Banerjee, without the implementation of fast breeders the presently available uranium reserves of 5.469 million tonnes can support 570 GWe till 2025. If the total identified and undiscovered uranium reserves of 16 million tonnes are brought online, the power availability can be extended till the end of the century. While calling for more research into thorium as an energy source and the country's indigenous three-stage programme, he said, "The world always felt there would be a miracle. Unfortunately, we have not seen any miracle for the last 40 years. Unless we wake up, humans won't be able to exist beyond this century."


See also

; Nuclear and energy related *
Energy security Energy security is the association between national security and the availability of natural resources for energy consumption. Access to (relatively) cheap energy has become essential to the functioning of modern economies. However, the uneven d ...
*
Energy policy of India The energy policy of India is to increase energy in India and reduce energy poverty, with more focus on developing alternative sources of energy, particularly nuclear, solar and wind energy. India attained 63% overall energy self-suff ...
*
Nuclear Liability Act The Civil Liability for Nuclear Damage Act, 2010 or Nuclear Liability Act is a highly debated and controversial Act which was passed by both houses of Indian parliament. The Act aims to provide a civil liability for nuclear damage and prompt co ...
*
Nuclear power in India Nuclear power is the fifth-largest source of electricity in India after coal, gas, hydroelectricity and wind power. , India has 22 nuclear reactors in operation in 8 nuclear power plants, with a total installed capacity of 7,380 MW. Nuclear p ...
*
Thermal reactor A thermal-neutron reactor is a nuclear reactor that uses slow or thermal neutrons. ("Thermal" does not mean hot in an absolute sense, but means in thermal equilibrium with the medium it is interacting with, the reactor's fuel, moderator and struct ...
; Weapons of mass destruction *
India–United States Civil Nuclear Agreement The 123 Agreement signed between the United States of America and the Republic of India is known as the U.S.–India Civil Nuclear Agreement or Indo-US nuclear deal. The framework for this agreement was a July 18, 2005, joint statement by then ...
*
Weapons of mass destruction A weapon of mass destruction (WMD) is a chemical, biological, radiological, nuclear, or any other weapon that can kill and bring significant harm to numerous individuals or cause great damage to artificial structures (e.g., buildings), natu ...
*
Nuclear Command Authority (India) The Nuclear Command Authority (NCA) of India is the authority responsible for command, control and operational decisions regarding India's nuclear weapons programme. It comprises a Political Council headed by the Prime Minister of India and an E ...
* Indian weapons of mass destruction


Footnotes


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Primary sources

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IEEE Spectrum
Q&A With: Sudhinder Thakur
IEEE Spectrum
Q&A: Thorium Reactor Designer Ratan Kumar Sinha


Further reading


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Web books

* {{DEFAULTSORT:India's Three Stage Nuclear Power Programme Nuclear power in India Nuclear history of India