India s Experience on the Operation of SMRs (PHWR, BWR and FBR)
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1 India s Experience on the Operation of SMRs (PHWR, BWR and FBR) Sudhinder Thakur Distinguished Scientist & Fellow, NPCIL May 3,2011. IAEA Vienna
2
3 Three Stage Nuclear Power Programme Natural Uranium PHWR 10 GWe ELECTRICITY Th Depleted U Pu Pu FUELLED FAST BREEDERS Pu U GWe ELECTRICITY Th U- 233 FUELLED BREEDERS Huge ELECTRICITY U STAGE 1 STAGE 2 STAGE 3 Optimum Utilization of Resources, Minimization of Waste
4 Development of Nuclear Technology BARC Jaduguda 1951 APSARA 1956 R&D Facilities 1957 Training School 1957 CIRUS 1960 Heavy Water Plant 1962 Calandria at manufacturer (L&T) shop ECIL 1967 NFC 1968 Industry Development
5 PRIME MINISTER ATOMIC ENERGY COMMISSION DAE Science Research Council ATOMIC ENERGY REGULATORY BOARD DEPARTMENT OF ATOMIC ENERGY R&D ORGANISATIONS Bhabha Atomic Research Centre, Mumbai Indira Gandhi Centre for Atomic Research, Kalpakkam Centre for Advanced Technology, Indore Variable Energy Cyclotron Centre, Kolkata Atomic Minerals Directorate for Exploration & Research, Hyderabad PUBLIC SECTOR UNDERTAKINGS Nuclear Power Corporation of India Indian Rare Earths Ltd., Uranium Corp. of India Electronics Corp. of India Bharatiya Nabhikiya Vidyut Nigam INDUSTRIAL FACILITIES Heavy Water Board, Nuclear Fuel Complex, Board of Radiation & Isotope Technology, Mumbai SERVICE ORGANISATIONS Directorate of Purchase & Stores, Mumbai Directorate of Construction, Services & Estate Management, Mumbai General Service Organisation, Kalpakkam Board for Research in Nuclear Sciences National Board of Higher Mathematics Tata Institute of Fundamental Research, Mumbai Tata Memorial Centre, Mumbai Saha Institute of Nuclear Physics, Kolkata Institute of Physics, Bhubaneswar Institute for Plasma Research, Ahmedabad Harish-Chandra Research Institute, Allahabad Institute of Mathematical Sciences, Chennai Atomic Energy Education Society, Mumbai
6 Nuclear Power in India - The Beginning October,1969 Set up on turnkey basis by GE, USA 41 years of successful operation
7 TAPS 1&2 Capacity Factor 100 2X210 MWe Derated to 2X160 MWe 80 Capacity Factor (%) Year
8 First PHWR 200 MW 1973 / 1981 Set up in technical cooperation with AECL, Canada
9 PHWR PROGRAM SINGLE UNIT 220 MW EXPORT FUTURE PROJECTS Haryana & MP 1980s INDIGENISATION 1970s TECHNOLOGY DEMONSTRATION 220 MWe 1980s STANDARDISATION 1990s CONSOLIDATION ONGOING PROJECTS KAPP-3&4 RAPP-7&8 2000s COMMERCIALISATION RAPP-3 to MW RAPS-1&2 MAPS-1&2 NAPS-1&2 KAPS-1&2 KAIGA-1 TO 4 TAPS-3& X 540 MW
10 Reactors in Operation 1/2 Tarapur Atomic Power Station (TAPS) Unit-1 BWR 160 MW October 1969 Unit-2 BWR 160 MW October 1969 Unit-3 PHWR 540 MW August 2006 Unit-4 PHWR 540 MW September 2005 Rajasthan Atomic Power Station (RAPS) Unit-1 PHWR 100 MW December 1973 Unit-2 PHWR 200 MW April 1981 Unit-3 PHWR 220 MW June 2000 Unit-4 PHWR 220 MW December 2000 Unit-5 PHWR 220 MW February 2010 Unit-6 PHWR 220 MW March 2010 Madras Atomic Power Station (MAPS) Unit-1 PHWR 220 MW January 1984 Unit-2 PHWR 220 MW March MW 1180 MW 440 MW
11 Reactors in Operation 2/2 Narora Atomic Power Station (NAPS) Unit-1 PHWR 220 MW January 1991 Unit-2 PHWR 220 MW July 1992 Kakrapar Atomic Power Station (KAPS) Unit-1 PHWR 220 MW May 1993 Unit-2 PHWR 220 MW September 1995 Kaiga Generating Station (KGS) Unit-1 PHWR 220 MW December 1973 Unit-2 PHWR 220 MW April 1981 Unit-3 PHWR 220 MW June 2000 Unit-4 PHWR 220 MW December 2000 Total Installed Capacity 440 MW 440 MW 880 MW 4780 MW
12 Operating Nuclear Power Plants in India TARAPUR 1&2 RAJASTHAN MADRAS TARAPUR 3&4 NARORA KAKRAPAR KAIGA
13 TARAPUR ATOMIC POWER STATION-3&4
14 Nuclear Power Plants in Operation 14 RawatbhataRaj MW 4 X 220 MW Narora, U.P. 2 X 220 MW Tarapur,Maharashtra 2 X 160 MW 2 X 540 MW Kakrapar, Gujarat 2 X 220 MW Kaiga, Karnataka 4 X220 MW Kalpakkam, T.N. 2 X 220 MW
15 Kudankulam Atomic Power Project 2X1000 MW VVERs Hydro test of primary circuit and containment pressure boundary test for unit 1 completed.
16 PFBR 500 MW
17 Kakrapar Atomic Power Project (3&4): 2X700 MW PHWRs
18 Rajasthan Atomic Power Project (7&8): 2X700 MW PHWRs
19 CAPACITY FACTOR (%) Presentation on India s Report, 5 th Review Meeting, CNS, 4-14 April 2011, IAEA, Vienna.
20 Availability Factor of Indian NPPs
21 Safety Assurance in all phases of NPPs Safety assurance during all phases of plant: Site selection, Design, construction, commissioning and operation Employment of Diverse, Redundant, Fail safe systems with defense in depth principle Quality Assurance & Audits Multi-tier Safety Reviews Robust Regulatory Mechanism Stage wise Authorisation Approval of Procedures Licensing of Personnel Review and analysis of all deviations Peer Reviews (WANO) Continuous Training & Upgradation of Personnel 21
22 Multi tier Review - Operating plants Atomic Energy Regulatory Board Expert Groups Reactor Physics Reactor Chemistry Control & Instrumentation Coolant Channel Safet In Service Inspection Safety Review Committee for Operating Plants (SARCOP) Unit Safety Committee (USC) Third Tier (AERB) Safety Review Committee (Operations) Second Tier (NPCIL HQ) Station Operation Review Committee (SORC) First Tier (Station) 22
23 Safety Performance 335 Reactor Years of safe, accident free operation Dose to Workers and Public a very small fraction of the permissible limit Average dose from NPPs at 1.6 km ( )
24 NPCIL Performance WANO PIs
25 Renovation & Modernisation EMCCR Moderator Sparger Supplementary C/Room 25 Feeder Replacement Gen. Stator wdg
26 Life Extension Programme (TAPS 1&2) 26
27 70 Reactors under Construction (last 20 years) Nos World India
28 Capacity Factors RAPS-2 RAPS-4 RAPS-5 TAPS-2 KAPS-1 TAPS-1 RAPS-3 KAPS-2 RAPS-6 KGS-4 TAPS-3 KGS-3 TAPS-4 MAPS-1 KGS-1 NAPS-1 NAPS-2 KGS-2 MAPS-2 RXs with Imported Fuel ( IAEA Safeguards) Reactors based on Indigenous fuel
29 Availability Factor in TAPS-1 TAPS-2 TAPS-3 TAPS-4 RAPS-2 RAPS-3 RAPS-4 RAPS-5 RAPS-6 MAPS-1 MAPS-2 NAPS-1 NAPS-2 KAPS-1 KAPS-2 KGS-1 KGS-2 KGS-3 KGS-4
30 Continuous Run in TAPS-1 TAPS-2 TAPS-3 TAPS-4 RAPS-2 RAPS-3 RAPS-4 RAPS-5 RAPS-6 MAPS-1 MAPS-2 NAPS-1 NAPS-2 KAPS-1 KAPS-2 KGS-1 KGS-2 KGS-3 KGS-4
31 NPCIL Performance 1. Safety Reactor years of safe operation. - No release of radiation in public domain. 2. Operation - 90% availability. - PLF upto 90%. - WANO Peer Review - Decision for IAEA OSART Mission 3. Financial - Profit making, Dividend Paying. - Cash reserve ~$ 2600 million. - AAA rating. - Budget Neutral.
32 In Conclusion: Infrastructure developments started years ahead of NPP Nuclear Power started as Government activity Transferred to commercial domain after 2 decades Strong support and linkages with R&D institutions With SMRs a modest capacity has been reached and further SMR capacity addition can be done with internal accruals FBRs (metallic fuel with higher breeding ratios) need more time for commercial deployment. In the intervening period, LWRs have a place for significant capacity addition. Future Plans are to reach 63 GW by 2032 through PHWRs, LWRs & FBRs.
33 Thank You
Module 09 Heavy Water Moderated and Cooled Reactors (CANDU)
Prof.Dr. Böck Technical University Vienna Atominstitut Stadionallee 2, 1020 Vienna, Austria ph: ++43-1-58801 141368 boeck@ati.ac.at Module 09 Heavy Water Moderated and Cooled Reactors (CANDU) 1.10.2016
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