India's three-stage nuclear power programme
India's three-stage nuclear power programme was formulated by Homi Bhabha in the 1950s to secure the country's long term energy independence, through the use of uranium and thorium reserves found in the monazite sands of coastal regions of South India. 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 it has only around 1–2% of the global uranium reserves, 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, and global uranium prices remain low enough that breeding is unnecessary.
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.
As of August 2014[update], India's first Prototype Fast Breeder Reactor had been delayed - with first criticality expected in 2015 - and India continued 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.
- 1 Origin and rationale
- 2 Fuel reserves and research capability
- 3 Stage I – Pressurised Heavy Water Reactor
- 4 Stage II – Fast Breeder Reactor
- 5 Stage III – Thorium Based Reactors
- 6 Linkages with the Indo-US nuclear deal
- 7 Indian nuclear energy forecasts
- 8 Thorium energy forecasts
- 9 See also
- 10 Footnotes
- 11 References
- 12 Sources
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 material, and thus cannot undergo fission to produce energy. Instead, it must be transmuted to uranium-233 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:
The total reserves of thorium in India amount to over 500,000 tons in the readily extractable form, while the known reserves of uranium are less than a tenth of this. The aim of long range atomic power programme in India must therefore be to base the nuclear power generation as soon as possible on thorium rather than uranium… The first generation of atomic power stations based on natural uranium can only be used to start off an atomic power programme… The plutonium produced by the first generation power stations can be used in a second generation of power stations designed to produce electric power and convert thorium into U-233, or depleted uranium into more plutonium with breeding gain… The second generation of power stations may be regarded as an intermediate step for the breeder power stations of the third generation all of which would produce more U-233 than they burn in the course of producing power.
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 Jawaharlal Nehru. 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.
|Energy resource type||Amount (tonnes)||Power potential (TWe-year)|
|Uranium (in PHWR)||61,000||0.3–0.42|
|Uranium (in FBR)||61,000||16–54|
|Thorium||~300,000||155–168 or 358|
Fuel reserves and research capability
According to a report issued by the IAEA, 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, 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 district near Hyderabad 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, 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 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 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 (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. Analysis shows that majority of the authors involved in thorium research publications appear to be from India. According to Siegfried Hecker, a former director (1986–1997) of the Los Alamos National Laboratory 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 fuelled pressurised heavy water reactors (PHWR) produce electricity while generating plutonium-239 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. 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.
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, with the exception of the two Boiling Water Reactor (BWR) units at Tarapur. The installed capacity of Kaiga station is now 880 MW, making it the third largest after Tarapur (1400 MW) and Rawatbhata (1180 MW). The remaining three power stations at Kakrapar, Kalpakkam and Narora all have 2 units of 220 MW, thus contributing 440 MW each to the grid. The 2 units of 700 MWe each (PHWRs) that are under construction at both Kakrapar and Rawatbhata, 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.
Stage II – Fast Breeder Reactor
In the second stage, fast breeder reactors (FBRs) would use a mixed oxide (MOX) fuel made from plutonium-239, 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 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 (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 at Kalpakkam was due to be completed in 2012. It is not yet complete. A start date in 2018 has been suggested.
In addition, the country proposes to undertake the construction of four FBRs as part of the 12th Five Year Plan spanning 2012–17, thus targeting 2500 MW from the five reactors. One of these five reactors is planned to be operated with metallic fuel instead of oxide fuel, since the design will have the flexibility to accept metallic fuel, although the reference design is for oxide fuel. Indian government has already allotted Rs.250 crore for pre-project activities for two more 500 MW units, although the location is yet to be finalised.
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.[a] 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.
|Fuel Type||U238–Pu cycle||Th–U233 cycle|
Stage III – Thorium Based Reactors
A Stage III reactor or an Advanced nuclear power system involves a self-sustaining series of thorium-232-uranium-233 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.[b] 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.
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 (AHWR) and Compact High Temperature Reactor. Molten Salt Reactor 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 (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 USA's Fermilab 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)
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.
|Type||Fissile Material Growth %|
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, the molten salt reactor, or the various accelerator driven systems.
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.
|Year||Pessimistic (GWe)||Optimistic (GWe)|
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."
- For analysis purposes, "doubling time" can be defined in three separate ways: Reactor Doubling Time (RDT) – which is the doubling that takes place within the reactor, System Doubling Time (SDT) – which is the doubling that takes into account all fuel losses that take place outside the reactor and Compounded System Doubling Time (CSDT) – which is the doubling that takes into account the fact that net gain in fissile material is promptly used to start up other reactors.(Tongia & Arunachalam 1997).
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