1. Energy Security for India : A Long Term Perspective Seminar on Nuclear Power-Energy Security for India, Alumni Association N.C.E. Bengal and Jadavpur University, Mumbai Branch 20.3.2010 S. Banerjee Department of Atomic Energy

2. 2 Energy growth in India Strong correlation between per capita GDP and per capita electricity consumption. Ten fold growth in electricity generation capacity necessary over next fifty years. Shortage of energy resources is a major challenge. 20-25% share for nuclear power inevitable even after accounting for all other energy forms. India China OECD USA India in 2050 Per capita electricity consumption vs. per capita GDP for various nations of the world Percapita electricity consumption -kWh Percapita GDP (PPP US ($))

3. For a large developing country with large population density, nuclear power will play an important role for sustainable supply of energy. * References: {1} “Integrated Energy Policy”, report of the expert committee, Planning Commission, Government of India, 2006 {2} “A Strategy for Growth of Electrical Energy in India”, document 10, August 2004, DAE Nuclear share must increase multifold to meet energy demands without leading to unmanageable environmental burden Deficit: ~1094 GWe to be met with - Nuclear - Coal Case study- India Per Capita Electricity Consumption: 593 kWh/year Planning commission- 8% growth{1} Planning commission- 9% growth{1} DAE {2} Renewables including hydro {2} Installed capacity required to reach Per Capita Electricity Consumption of ~5000 kWh/year corresponding to Human Development Index of 0.8-0.85 3 ~4.7 billion tonne /year [>4 times current US coal consumption for electricity generation] ~7.7 Gte of CO2 emissions Coal

4. 4 Long term and sustainable primary sources of energy Only two long term and sustainable primary sources of energy Solar Energy Ideally suited for distributed applications including use in rural sector Nuclear Energy Highly concentrated form of energy more suited to urban sector and Industries though centralised production

5. Trough System Dish systems Power towers Solar Power Generation Technologies for solar power generation can be categorized broadly as Solar photovoltaic technology Solar photovoltaic cells convert sunlight falling onto it directly into electricity Solar thermal technology Various types of mirrors focuses/concentrates solar energy to produce steam (directly or indirectly through an intermediate working fluid) and generate electricity using conventional method. Major technologies for solar thermal power generation are trough systems, dish systems, power towers etc. Solar photovoltaic cell Solar thermal systems

6. ` ` Molten salt pump Heat utilization system Steam Generator Central receiver Power tower Hot storage tank Among all the solar thermal power generation technologies available, development of solar power tower is adopted in BARC because of following advantages, 1.It can be used for large power generation and connection to grid 2.High temperature can be achieved using molten salt, which is useful for following DAE programs, The high temperature process heat can be used for hydrogen production. Thermoelectric device can be incorporated into receiver to make a hybrid system to increase efficiency. molten salt technology has direct relevance to advanced reactor systems. Solar Test facility (SOTEF) in BARC

7. 7 Three Stage Indian Nuclear Power Programme

8. 88 Stage – I PHWRs 16 – Operating 16 – Operating 2 - Under construction 2 - Under construction Several others planned Several others planned Scaling to 700 MWe Scaling to 700 MWe Gestation period has been reduced Gestation period has been reduced POWER POTENTIAL  10 GWe POWER POTENTIAL  10 GWeLWRs 2 BWRs Operating 2 BWRs Operating 2 VVERs under 2 VVERs under construction construction Stage - II Fast Breeder Reactors Fast Breeder Reactors 40 MWth FBTR - Operating since 1985 40 MWth FBTR - Operating since 1985 Technology Objectives realised 500 MWe PFBR- 500 MWe PFBR- Under Construction TOTAL POWER POTENTIAL  530 GWe (including  300 GWe with Thorium) TOTAL POWER POTENTIAL  530 GWe (including  300 GWe with Thorium) Stage - III Thorium Based Reactors Thorium Based Reactors 30 kWth KAMINI- Operating 30 kWth KAMINI- Operating 300 MWe AHWR: Pre- licensing safety appraisal by AERB completed, Site selection in progress300 MWe AHWR: Pre- licensing safety appraisal by AERB completed, Site selection in progress POWER POTENTIAL IS VERY LARGE Availability of ADS can enable early introduction of Thorium on a large scale World class performance Globally Advanced Technology Globally Unique

9. 9 Comparison of eta (  ) of important fissile materials Variation of eta (  ) with energy for important fissile materials 233 U has an eta (  ) value greater than 2.0, which remains constant over a wide energy range, in thermal as well as epithermal regions, unlike 235U and 239 Pu. –The thorium fuel cycle is less sensitive to the type of thermal reactor

10. 10 Assuming 40 years reactor life, and need to commit uranium supply for full lifetime before launching a new reactor. With 5.47 million tonnes of uranium, a maximum installed capacity of 570 GWe can be attained, while ensuring lifetime assurance of fuel. With 16 million tonnes, a maximum installed capacity of about 1415 GWe can be attained, while ensuring lifetime assurance of fuel. For analysis, no losses are assumed. With IAEA INPRO moderate scenario, the requirement of uranium to sustain once-through use in LWRs soon exceeds uranium resources. Transition to closed nuclear fuel cycle is needed well in time. With reprocessing of spent fuel and use of Pu in Fast reactors, resources can be utilised for extended period of time delivering much larger energy. Thorium, available in larger amount in earth’s crust, can be utilised effectively to further extend the resource availability 10 Current uranium consumption: 436 reactors - installed capacity 370 GWe Uranium production in 2008 – 43,764 t Currently identified resources (5.47 million tonnes) Requirement of uranium as per INPRO moderate scenario

11. Strategies for long-term energy security (A case study) Hydroelectric Non-conventional Coal domestic Hydrocarbon Nuclear (Domestic 3-stage programme) Projected requirement * * Ref: “A Strategy for Growth of Electrical Energy in India”, document 10, August 2004, DAE No imported reactor/fuel Deficit to be filled by fossil fuel / LWR imports LWR (Imported) FBR using spent fuel from LWR LWR import: 40 GWe Deficit 412 GWe Required coal import: 1.6 billion tonne * in 2050 * - Assuming 4200 kcal/kg The deficit is practically wiped out in 2050 With thorium, nuclear installed capacity (600 GWe) can be sustained for very long period Year

12. Sites accorded ‘in principle’ approval PHWR Site LWR Site Existing Site New Site

13. New Launches - Indigenous Project 2010 -11 2011 -12 2012 -13 2013 -14 2014 -15 2015 -16 2016 -17 2017 -18 2018 -19 2019 -20 2020 -21 2021 -22 KAPP 3&4 (2 X 700 MW) RAPP 7&8 (2 X 700 MW) 7NP 5&6 (2 X 700 MW) 7NP 7&8 (2 X 700 MW) 7 NP 9&10 (2 X 700 MW) FBR 1&2 (2 X 500 MW) AHWR (300 MW) Indian PWR (600-700 MW) Small PHWR for Export LAUNCH PRE-PROJDEVELOPMENT

14. New Launches - Int’l Cooperation Project 2010 -11 2011 -12 2012 -13 2013 -14 2014 -15 2015 -16 2016 -17 2017 -18 2018 -19 2019 -20 2020 -21 2021 -22 KK 3&4 (2X1000 MW) JP 1&2 (2X1650 MW) Guj 1&2 (2X1100 MW) AP 1&2 (2X1350 MW) WB 1&2 (2X1000 MW) KK 5&6 (2X1000 MW) JP 3&4 (2X1650 MW) Guj 3&4 (2X1100 MW) AP 3&4 (2X1350 MW) WB 3&4 (2X1000 MW)

15. Indian Nuclear Power Programme - 2020 > 18 reactors at 6 sites in operation 4,340 4,340 Tarapur, Rawatbhata, Kalpakkam, Narora, Kakrapar and Kaiga  2 PHWRs under construction at 440 4,780 Kaiga 4 (220 MWe), RAPP-6(220 MWe)  2 LWRs under construction at 2,000 6,780 Kudankulam(2x1000 MWe)  PFBR under construction at Kalpakkam (1 X 500 MWe) 500 7,280 > Projects planned till 2020 7,900 15,180 PHWRs(8x700 MWe), FBRs(4x500 MWe), AHWR(1x300 MWe)  Additional LWRs through international ~ 20000 35000 cooperation CAPACITY (MWe) CUMULATIVE CAPACITY (MWe) REACTOR TYPE AND CAPACITIES

16. 16 Advanced Heavy Water Reactor Thorium utilization with closed fuel cycle Extensive deployment of passive safety features – 3 days grace period, and no need for planning off-site emergency measures Inherent safety features Design life of 100 years Improved economics Emergency core cooling water injected directly into the fuel cluster AHWR Vertical pressure tube type, boiling light water cooled and heavy water moderated reactor Power output – 300 MWe with 500 m 3 /d of desalinated water A large fraction (65%) of power from thorium Initial core with all fuel pins of (Th- Pu) MOX and equilibrium core with both (Th-Pu) MOX & (Th- 233 U) MOX Easily replaceable coolant channels

17. 17 High Temperature Reactor Concept White hot block of nuclear fuel, moderator and reflector HTR Cold Coolant in Hot Coolant out Reactor core at  1000  C Special fuel based on TRISO coated particle fuel Ceramic core consisting of graphite and BeO Lead alloy based coolant Normal operation core heat removal by natural circulation of coolant Upper plenum to secondary system heat transfer by sodium heat pipes Passive reactor regulation and shutdown system Passive postulated abnormal condition heat removal by heat pipes as well as a gas gap liquid metal filling system (Gas gap acts as insulation under normal operation) Gas gap Cold Coolant return Upper Plenum and secondary system Lower Plenum Natural convection basedpassive cooling system Gas gap liquid metal filling system to passively dissipate heat radially to heat sink in case of abnormal condition White hot block of nuclear fuel, moderator and reflector HTR Heat Sink

18. 18 CHTR has an all ceramic core containing mainly BeO and carbon based components

19. 19 Efficiency of hydrogen production from water - whether by electrolysis or by thermo-chemical splitting is higher at higher temperatures Electrolysis Thermo-chemical cycle Water Electrolysis Processes: AW: Alkali Water, MC: Molten Carbonate SP: Solid Polymer, HT: High Temperature Thermo-chemical Processes: Cu-Cl: Copper - Chlorine, Ca-Br 2 : Calcium- Bromine, I-S: Iodine-Sulfur Process Ref: High Efficiency Generation of Hydrogen Fuels Using Nuclear Power, G.E. Besenbruch, L.C. Brown, J.F. Funk, S.K. Showalter, Report GA–A23510 and ANL reports Ref: IAEA-TECDOC-1085: Hydrogen as an energy carrier and its production by nuclear power

20. 20 Future Perspectives Water splitting process Water Nuclear/ solar energy Synthetic fuel process Hydrogen Atmosphere O2O2 Energy System Fuel Cells Power plants Transport Industries Synthetic fuel CO 2 & H 2 O Atmosphere O2O2 CO 2 Renewable Source of carbon- biomass C & H 2 H2H2 CO 2

21. NUCLEAR POWER PROGRAMME THEN (1957)  Meager Financial Resources  Limited Scientific & Technological Manpower  Facing a Severe Technology Ban Regime  Inadequate Industrial and Manufacturing Base  Extremely Small resource of Fissile material R.K. Laxman’s famous cartoon depicting Pandit Nehru driving the common man on a bullock cart with a nuclear wheel - Appeared on 21 st January 1957, the day Pandit Nehru formally inaugurated Atomic Energy Establishment Trombay

22.  An Extensive Manpower Training system is in place  Developed our own Technologies in entirety  Developed Industrial and Manufacturing Base in India  Innovated the Uranium- Thorium route – 3 stage  Harnessed societal spin offs  Provided Strategic Security  Poised for a substantial growth Mastery on complete fuel cycle PHWRs - Capacity utilization exceeding 90% Fast reactor – 150,000 MWd/t burnup achieved Embarked on building commercial Fast Breeder Reactor Wide spread utilization of Radiation & Isotope technology for societal benefits 540 MWe PHWR NUCLEAR POWER PROGRAMME NOW (2010)

23. 23 Winds of change I do not want my house to be walled in on all sides and my windows to be stuffed. I want the cultures of all the lands to be blown about my house as freely as possible. But I refuse to be blown off my feet by any. - Mahatma Gandhi

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