Prospect of Nuclear Energy in India

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Presentation transcript:

Prospect of Nuclear Energy in India INDIA@COP22 Prospect of Nuclear Energy in India DEB MUKHOPADHYAY Sustainable Lifestyle = Positive Climate Action www.indiaatcop22.org

Electricity Generation Scenario in India INDIA@COP22 All India Installed Capacity (MWe) as on September 2016 • At present India is ranked 5th in world in installed capacity and generation A shortfall of 10-12% remains during peak time to meet the GDP growth projection There is an urgent need to enhance power generation in the country without increase in the carbon emission Note: Captive Genaration is not included in the total Source: Executive Summary for the Month of Sept, 2016, Central Electricity Authority New Delhi, India www.indiaatcop22.org

Nuclear Power for Sustainable supply of Energy- Indian Scenario INDIA@COP22 Nuclear Power for Sustainable supply of Energy- Indian Scenario • 8-9% growth requires 800-1000 GW capacity by 2032 3-4 billion tonnnes of CO2 emission expected from fossil fuel used to meet the balance requirement • Renewable, Hydro and Nuclear Power are options for clean energy Nuclear program aims for 20.0 GWe by 2024 [Strategy for growth of Electricity in India, Primary Energyhttp://www.dae.nic.in/] Source: Integrated Energy Policies, Report of the expert committee, Planning Commission 2006 www.indiaatcop22.org

Indian Nuclear Power Program INDIA@COP22 The program is based on the reserves of Uranium (~61,000 tonnes) and large reserves of Thorium (~ 2,25,000 tonnes) Limited U resources and large Th resources lead to adoption of closed fuel cycle policy in the program to utilise the available resources to a best possible way 3-Stage Nuclear Power Program: Stage 1: Use of Natural uranium in PHWR Stage 2: Fast Breeder reactors using reprocessed Pu from Thermal Reactors and Thorium Blankets Stage 3: Thorium-Uranium 233 reactors Source: A strategy for growth of electrical energy in India, Department of Atomic Energy and http://barc.gov.in/about/anushakti_sne.html Natural Uranium deposits - ~70,000 tonnes  Thorium deposits - ~ 3,60,000 tonnes www.indiaatcop22.org

Indian Nuclear Power Program INDIA@COP22 Indian Nuclear Power Program The goal of three stage Indian nuclear power programme is longterm resource sustainability www.indiaatcop22.org

Indian Nuclear Power Program INDIA@COP22 Stage-I: Natural Uranium based PHWRs Projected Installation upto 2055: 7.26 Gwe Stage-II: Fast Breeder Reactors using re-processed Pu and at a later stage Th in the blanket and Metallic Fuel Projected Installation upto 2055: 200 GWe Stage-III: Self sustaining Th-U233 based reactors Results of a case study; assumptions 60000 te Uranium and short doubling time FBRs beyond 2021 www.indiaatcop22.org

Indian Nuclear Power Program INDIA@COP22 Indian Nuclear Power Program Stage-I: PHWRs : 18 operating (4460 MWe), 4 units of 700 Mwe under construction (2800 MWe) and 48 units planned LWRs: 2 BWRs Operating (320 MWe) and 2 VVERs Operating (2000 MWe). 2 more units of VVER (1000 MWe each) are planned Stage-II: Pu Cycle FBRs : One 40 MWth operating since 1985, 500 MWe PFBR under comissioning and two FBR units designed Stage-III: Thorium Cycle One 30 KWth KAMINI operating and 300 MWe Thorium based AHWR is ready for deployment. www.indiaatcop22.org

PHWR Technology –Stage I INDIA@COP22 PHWR Technology –Stage I Performance & Economics of Indian PHWR based NPPs Capital cost for construction is substantially lower as compared to world average Minimisation of construction period has helped to minimise the cost A lower Unit Energy Cost (UEC) is achieved as compared to global range An overall better capacity factor is achieved which helped to lower down the overall UEC www.indiaatcop22.org

PHWR Technology Evolution –Stage I INDIA@COP22 Major Components of PHWR: Industry Participation Primary Side: Reactor Channels and Fuel Bundles Calandria Vessel Steam Generators Circulating Pumps Headers Fuelling Machine Secondary Side Turbines Deaerator Condensor Pumps Containment Calandria Fuel Bundle PHWR Nuclear Containment F/M Head Steam Generator www.indiaatcop22.org

PHWR Technology Enhancement -Stage I INDIA@COP22 Post Fukushima Safety Enhancement Enhancing Severe Accident management Program Station specific accident management guidelines Hookup provisions for core cooling Solar lighting Strengthening hydrogen management provisions Indigenous Passive Catalytic Recombiner Device (PCRD) development and testing Additional provision of removal of fission product Indigenous Containment Filtered Venting System (CFVS) Development and testing Creation of on-site emergency support centre Additional safety features for new designs Passive Decay Heat Removal System, Melt Retention, Core Catcher Hook up arrangements PCRD test Facility CFVS Component www.indiaatcop22.org

LWR Program & Safety Enhancement –Stage I INDIA@COP22 LWR Program & Safety Enhancement –Stage I Operating LWRs based on foreign technical cooperation GE- BWR (TAPS-1&2): Installation of additional DGs etc. VVER 1000 (KK-1): Ultimate Heat Sink (Air cooled PHRS) Planned LWRs based on foreign technical cooperation VVER AP1000 EPR Indian PWR (IPWR) technology development Program for 900 MWe, a joint project of BARC & NPCIL Indian industry is poised to make heavy and critical equipment like Reactor Pressure Vessel (RPV), steam generators (SG), PHT Pumps, etc. www.indiaatcop22.org

Front end of Nuclear Fuel Cycle - Stage I INDIA@COP22 Front end of Nuclear Fuel Cycle - Stage I The Nuclear Fuel Complex (NFC)was established in the early 70s. Making nuclear fuel assemblies and core structural components for the entire nuclear power programme of the country.  Processing of uranium ore concentrate and zircon sand through a series of indigenously developed chemical and metallurgical operations.  Making seamless tubes by hot extrusion and cold pilgering process. the NFC has also ventured recently into export of some of its products like zirconium bars and anhydrous magnesium chloride.  www.indiaatcop22.org

Fuel Cycle & Sustainability INDIA@COP22 Fuel Cycle & Sustainability Reprocessing of spent fuel : A closed cycle for long term energy is envisaged in view of phased expansion for second and third stages Indigenous technology for reprocessing of the spent fuel is developed Waste management programme has been developed by its own comprehensive R&D efforts and reprocessing plants were set up and are in operation thereby attaining self reliance Vitrification facility Vitrified Waste Storage facility www.indiaatcop22.org

Fuel Reprocessing Cycle & Sustainability INDIA@COP22 Fuel Reprocessing Cycle & Sustainability Reprocessing of Spent fuel : PUREX Open Cycle: Disposal of the entire waste after subjecting to proper waste treatment Closed cycle: Separation of U-238 and Pu-239 Further recycled for other radioactive FP separation for useful purposes like production of Cs-137 pencils for medical purposes Appropriately disposed off with minimum environmental disturbance. Indian Nuclear Fuel Cycle: Today resulting huge underutilization of the energy potential of Uranium (~ 2 % is exploited) www.indiaatcop22.org

PFBR Technology – Stage II INDIA@COP22 PFBR Technology – Stage II Proto Type Fast Breeder Reactor (PFBR) –Under Commissioning Fuel : PuO2 + UO2 Electrical output : 500/470 MWe Coolant : Sodium Gross thermal Efficiency : 40% Economy Reactor Vessel www.indiaatcop22.org

PFBR Indigenous Technology – Stage II INDIA@COP22 PFBR Indigenous Technology – Stage II Proto Type Fast Breeder Reactor (PFBR) –Industry Participation Main vessel Safety vessel Steam generator Roof slab Sodium & argon buffer storage tanks Metal reflective thermal insulation panels Inclined fuel transfer arm Boron carbide shielding structure Dummy fuel blanket sub-assemblies www.indiaatcop22.org

Thorium Technology –Stage III INDIA@COP22 A Road Map for Deployment of Thorium Based Reactors Based on the study premature large scale deployment of thorium leads to sub-optimal use of indigenous energy resource Incorporation of thorium in the blankets of metallic fuelled fast breeder reactors – after significant FBR capacity built-up Necessary to build-up a significant level of fissile material before launching thorium cycle in a big way for the third stage Thorium based reactors expected to be deployed largely beyond 2070 AHWR – Thorium fuel cycle demonstrator by 2026 Surplus U-233 formed in future FBRs could drive HTRs programme including MSBRs www.indiaatcop22.org

Thorium Technology –Stage III INDIA@COP22 Advantages of Thoria Cycle: ThO2 - Physical and Chemical Properties Relatively inert as compared to UO2. Does not react with water. Higher thermal conductivity than UO2. Lower co-efficient of thermal expansion than UO2. Higher Melting point than UO2 Fission gas release rate one order of magnitude lower than that of UO2. Good radiation resistance and dimensional stability Radiation Stability Study ThO2-4% PuO2 UO2-4% PuO2 www.indiaatcop22.org

Thorium Technology –Stage III INDIA@COP22 Advantages of Thoria Cycle: Important Neutronic Characteristics Intrinsic Barrier to Proliferation η value for U233 remains nearly constant Helps of high conversion ratios with thorium utilisation U232 and U233 is formed from Th232 The half-life of U232 is about 69 years. The daughter products Tl and Bi are high energy gamma emitting isotopes. Presence of U232 in separated U233, offers good proliferation-resistant characteristics. www.indiaatcop22.org

Introduction of Thorium Technology –Stage III INDIA@COP22 Evolution of thorium fuel cycle development Thoria Irradiation in Indian reactors Irradiation of (Th-Pu)O2 in research reactors Thoria bundles irradiated in the blanket zone of Fast Breeder Test Reactor (FBTR) 232 Thorium bundle irradiation in PHWRs with 14,000 MWd/Te www.indiaatcop22.org

Thorium Fuel Fabrication –Stage III INDIA@COP22 Experience with fabrication of thoria-based fuel Thoria bundles for PHWRs Thoria assemblies for research reactor irradiation (Th-Pu) MOX pins for test irradiations Thoria microspheres and ThO2 Pellets fabricated for AHWR Critical Facility Thorium fuel cycle technologies is relatively complex because of inert nature of thoria radiological aspects MOX Powder Processing www.indiaatcop22.org

Thorium Technology Demonstrator- Stage III INDIA@COP22 Thorium Technology Demonstrator- Stage III Advanced Heavy Water Reactor (AHWR) –Ready for launching AHWR is a 300 MWe, vertical, pressure tube type, boiling light water cooled, and heavy water moderated reactor AHWR is a technology demonstration reactor, designed to achieve large-scale use of thorium for power generation Provides transition to 3rd stage of the Indian Nuclear Power Programme. Addresses most issues relevant to advanced reactor designs like sustainability, enhanced safety, proliferation resistance and economic competitiveness. Number of passive safety features to reduce environmental impact. Fuel cycle flexibility www.indiaatcop22.org

Thorium Technology - Stage III INDIA@COP22 Thorium Technology - Stage III Advanced Heavy Water Reactor (AHWR) –Passive Cooling for Strengthening Defense-in-Depth Approach Passive Core Cooling by Natural Circulation Passive decay heat removal by Condenser Passive Shutdown System Passive Emergency Core Cooling Injection by Accumulator and GDWP Passive Containment Coolers Project Status: Design Validation is done through extensive experimental program Pre-licensing safety appraisal by AERB Site selection is in progress www.indiaatcop22.org

Thorium Technology for Advanced Reactor Programme - Stage III INDIA@COP22 Thorium Technology for Advanced Reactor Programme - Stage III Technology development programs are launched for Thorium utilization High Temperature Reactor Program Compact High Temperature Reactor (CHTR) Indian High Temperature Reactor (IHTR) Indian Molten Salt Breeder Reactor (MSBR) Reasons for pursuing high temperature reactor program Higher thermal efficiency Hydrogen generation as a combustible fuel Low minor actinide generation –easy to handle for reprocessing Proliferation resistance H2 Generation www.indiaatcop22.org

Thorium Technology - Stage III INDIA@COP22 Thorium Technology - Stage III Indian High Temperature Reactor Program CHTR-Technology Demonstrator 100 kWth, 1000 °C, TRISO fuel passive systems for reactor heat removal Prolonged operation without refuelling IHTR-for Hydrogen Production 600 MWth, 1000 °C, TRISO fuel Active & passive control & cooling On-line refuelling MSBR Medium power, moderate temperature Reactor based on U233-Th fuel cycle www.indiaatcop22.org

Thorium Technology - Stage III INDIA@COP22 Thorium Technology - Stage III R&D Program for High Temperature Reactor Program: High packing density fuel compacts based on TRISO coated particle fuel Materials for fuel tube, moderator and reflector Carbon based materials (graphite and carbon carbon composite) Beryllia Graphite Oxidation & corrosion resistant coating Heat pipes www.indiaatcop22.org

Thorium Technology - Stage III INDIA@COP22 Thorium Technology - Stage III R&D Program for High Temperature Reactor Program: Metallic structural materials Nb-1%Zr-0.1%C alloy, Ta alloy Thermal hydraulics Studies for LBE coolant Molten Salt Coolant Kilo Temperature Loop (KTL) Molten Salt Corrosion Study www.indiaatcop22.org

Thorium Technology - Stage III INDIA@COP22 Thorium Technology - Stage III Major Challenges in Development of High Temperature Reactor Material development for high temperature reactors Remote handling Fuel reprocessing due to high gamma daughter products Nuclear Data Appropriate computational analysis tool for Thermal-Hydraulics and Neutronic coupled simulation for Molten Salt Breeder Reactor On-line fission product removal techniques for Molten Salt Breeder Reactor Natural circulation based reactors stability www.indiaatcop22.org

PRESENTATION SUMMARY INDIA@COP22 India’s 3 stage Nuclear Power Program is planned to achieve a sustained energy production by effective utilization of both fissile & fertile elements, thus aim to reduce carbon emission The Nuclear Program of Stage-I and Stage-II are matured and growing Advancements on better fuel utilization, higher energy conversion and reduction of activity levels in radio-active waste are pursued rigorously. Foreign Reactors based NPPs are making it’s way to boost the Energy Growth in Nuclear Based Power in India The Stage-III Program is evolving with Thorium utilization concept and Advance Heavy Reactor is readied for construction Technologies for thorium utilizations namely High Temperature Reactors under Stage-III Program are on-going for power and hydrogen generation and extensive R&D program is in place to overcome the technological challenges www.indiaatcop22.org

INDIA@COP22 Thanks for your kind attention!! www.indiaatcop22.org