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Current Status and Future Plan of Fast Reactor

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Current Status and Future Plan of Fast Reactor CURRENTCURRENT STATUSSTATUS ANDAND FUTUREFUTURE PLANPLAN OFOF FASTFAST REACTORREACTOR DEVELOPMENTDEVELOPMENT ININ INDIAINDIA BaldevBaldev RajRaj Distinguished Scientist & Director Indira Gandhi Centre for Atomic Research Kalpakkam Oarai R&D Centre, Japan Atomic Energy Agency May 21, 2009 Motivation for More & Clean Energy -> Better quality of life Increase in Demand Cost effectiveness Energy Challenges Reduced Emissions Public and Political acceptance Energy defines the index of quality of life. But has to meet many challenges 22 THREE STAGE NUCLEAR POWER PROGRAM 95 89 90 84 86 84 90 85 79 85 (% ) 80-----> 75 82 72 80 75 69 75 70 Capacity Factor / 71 65 67 60 A vailability 60 55 50 1995-96 1996-97 1997-98 1998-99 1999-00 2000-01 2001-02 2002-03 Stage – I PHWRs Stage - II Stage – III and Beyond Fast Breeder Reactors Fast Breeder Reactors Thorium Based Reactors • 15 - Operating • 3 - Under construction • 40 MWth FBTR - Operating • 30 kWth KAMINI - Operating • Several others planned Technology Objectives realised • 300 MWe AHWR - Under • Construction planned Regulatory Examination for 700 MWe units • Gestation period • 500 MWe PFBR - • POWER POTENTIAL = being reduced under construction 155,000 GWe -y ≅≅≅ • POWER POTENTIAL • Availability of ADS 10,000 MWe • POWER POTENTIAL: Minimum can enable early LWRs 530 GWe introduction of Thorium • 2 BWRs Operating • Participation in ITER • 2 VVERs under towards development of construction fusion technology Kalpakkam – Unique Nuclear Site in the World housing all Three Stages & Clo sed Fuel Cycle Facilities IGCAR – Mission Oriented Centre for Development of Science Based Techno logy for FBR Indian energy resources and Nuclear Contribution ADVANTAGESADVANTAGES OFOF FASTFAST BREEDERBREEDER REACTORSREACTORS Energy Potential 1 kg of coal 3 kWh 1 kg of oil 4 kWh 1 kg U (natural) 50,000 kWh (if reprocessed) 3,500,000 kWh No. of neutrons generated from fission perneutron absorbed in the fissile material Reactor Nat.U U-235 U-233 Pu-239 (BTCE) Thermal 1.34 2.04 2.26 2.06 Fast < 1 2.20 2.35 2.75 Ø Effectively utilizes the natural uranium (nearly 80 %) Ø Consumes the depleted fuel discharged from thermal reactors Ø Breeds more fissile material (plutonium) than consumed With a large number of thermal reactors operating and planned worldwide, the limited available natural uranium would be consumed very fast. On the other hand, with FBRs, energy supply can be ensured over a few centuries. AdvantagesAdvantages ofof FBRFBR –– contdcontd …… FBR is important from waste management and environmental considerations. Burns actinides and long lived radioactive fission products. Generation of precious metals such as Cs, Pd etc which have many important societal applications and can be extracted from its waste (wealth from waste). Current trends in oil prices and available uranium resources bring FBR with closed fuel cycle to focus WORLDWORLD FASTFAST REACTORREACTOR SCENARIOSCENARIO The interest in FBR has been renewed internationally • China, France, India, Japan, Korea, Russia, and USA have interest in FRs • France, Japan, and USA have signed an MOU to cooperate under the Global Nuclear Energy (GNEP) Partnership to demonstratethefeasibility of the sodium-cooled fast reactor technologyto accomplish sustainability requirements • International collaborative programmes on innovative reactorssuch asGeneration-IV & INPRO arefocusing on FRs • 390reactor yearsoperating experienceincluding test reactors FBR providesever growing challenges & opportunities in scienceand technology FBRFBR PROGRAMMEPROGRAMME ININ INDIAINDIA Ø India started FBR programme with the construction of FBTR Ø FBTR is a 40 MWt (13.5 MWe) loop type reactor. The design is same as that of Rapsodie-Fortissimo except for incorporation of SG and TG (agreement signed with CEA, France in 1969). Ø FBTR is in operation since 1985. Ø 500 MWe Fast Breeder Reactor Project (PFBR) through Indigenous design and construction Ø Govt. granted financial sanction for construction in Sep 2003. Ø Construction of PFBR has been undertaken by BHAVINI. Ø PFBR will be commissioned by 2010. Ø Beyond PFBR: 4 units of 500 MWe FBR (twin unit concept) similar to PFBR with improved economy and enhanced safety by 2020. Ø Subsequent reactors would be 1000 MWe units with metallic fuel FastFast BreederBreeder TestTest ReactorReactor Credible Backbone of confidence in regulatory perception fuel cycle in INDIA C 20 years of radl e for successful hu operation man r esou rces 1250 MWt, 500 MWe, Pool Type, UO2-PuO2 ology techn APPROACHAPPROACH TOTO BIGBIG LEAPLEAP ININ FBRFBR PROGRAMMEPROGRAMME based ience •Sc ws R&D • 380 r-y worldwide FBR operational Revie DAE, •Peer mong • experience ism a ynerg • Rich experience with MOX fuel •S ons stituti • 30 y of focused R&D programme In tries Indus • involving extensive and • testing and validation , e C W U - M 5 C . u 3 P 1 , t , e p W y M t p 0 o 4 o L PFBR REACTOR ASSEMBLY 01 MAIN VESSEL 02 CORE SUPPORT STRUCTURE 03 CORE CATCHER 04 GRID PLATE 05 CORE 06 INNER VESSEL 07 ROOF SLAB 08 LARGE ROTATABLE PLUG 09 SMALL ROTATABLE PLUG 10 CONTROL PLUG 11 CSRDM / DSRDM 12 TRANSFER ARM 13 IHX 14 PRIMARY SODIUM PUMP 15 SAFETY VESSEL 16 REACTOR VAULT PFBR SECONDARY SODIUM MAIN SYSTEM Number of sodium loops : 2 Primary Pumps : 2 Nos. Secondary Pumps : 2 Nos. IHX : 4 Nos. SG Modules : 8 Nos. Turbo-Generator : 1 No. CHALLENGES IN SCIENCE AND TECHNOLOGY OF FBR Science Engineering Technology • Metals and their performance • Design for components at • Manufacture of large under high temperature, high temp & long life dimensioned welded thin sodium, irradiation • Design of mechanisms shell structures made of environments over the long operating in sodium and austenitic stainless steel reactor life argon cover gas space petals with close tolerances • Development of non-metallic • Design to accommodate Na (~thickness) eg. Main & materials operating at high leak & Na water reactions safety vessels, inner temperatures and radiation • Seismic design of vessel, thermal baffles, etc environments (special high interconnected buildings, density concrete, elastomers, • Machining of large components and thin shells ceramics, cables, etc) dimensioned and tall with fluid-structure interaction slender components with • Sodium chemistry, aerosol • ISI &repair of reactor internals stringent tolerances (grid behaviour, sodium fire and sodium water reactions • High temp. fission chamber plate, absorber rod drive and component handling • Special sensors for sodium systems) applications (detection of water leaks in steam generator, • Fabrication of large size sodium leaks, purity box structures with measurements, level detectors) controlled distortions • Thermal hydraulics and • Hard facing technology Structural mechanics (turbulences, instabilities, gas • Development of Inflatable entrainments, thermal striping, seals and large size stratifications, ratcheting, etc) bearings DESIGNDESIGN OFOF CORECORE FORFOR HIGHHIGH BURNUPBURNUP Design Parameters for High Burnup • Increasing fission gas plenum • Increasing the pellet density • Decreasing the smeared density • Annular pellet concept • High performance materials (High void swelling resistance, low Irradiation creep and improved high temperature properties POOLPOOL THERMALTHERMAL HYDRAULICSHYDRAULICS IHX • Large temperature difference (150 K) existing in IHX CP hot pool leads to risk of thermal stratification. CP • Stratification causes sharp axial gradient in the adjoining metal wall. • Stratified layers oscillate causing high cycle fatigue Core Core • Mitigation of stratification calls for novel thermal hydraulic design of hot pool component • Due to large pool surface area and free surface velocity, there is risk of argon gas entrainment within hot & cold pools. • Gas entrainment can cause reactivity oscillations in case of bulk of argon bubble entering in to the core • General design guidelines is to Minimize the Free Surface Velocity to Mitigate Gas Entrainment in Hot Pool THERMALTHERMAL STRIPINGSTRIPING DESIGNDESIGN Thermal striping limits on structural wall Thermal striping values (CFD) SEISMICSEISMIC DESIGNDESIGN • Development of seismic design criteria • Ensuring the reactorscramability • Analysis of nuclearisland connected buildings • Investigation of pump seizure (NICB) and also extract floorresponse spectra at • Shake table testing forvalidation of analysis and various component support locations qualification • Seismic analysis of reactorassembly to derive • Long term R&D: behaviourof bearing, non-linearsloshing, seismic forces parametric instability of thin shells, study of cliff-edge • Investigation of buckling of thin shells effects, fluid-structure interaction of perforated structures NICB model for seismic analysis FEM model of RA Buckling modes of thin vessels Drop time of absorber rods Shake table tests on RA model Experiment TheoryTheory Experiment Theory ANALYSIS OF SHOCK -STRUCTURE INTERACTION: HIGHLIGHTS Mechanical consequences of Core Disruptive Accident (CDA) • Complicated loading scenarios on the vessel & top shield have been realistically simulated • A series of ~65 tests have been conceived in a novel way and successfully completed at Terminal Ballistic Research Laboratory, Chandigarh over the period of 4 years • Sophisticated instrumentations were deployed to Structural integrity analysis of PFBR RA underCDA derive extensive data for investigations. Demonstration of structural integrity by tests Validation of computercode FUSTIN CHALLENGING R&D: COMPONENT TESTING Seismictestingofreactor assembly Simulationofcomplexthermal
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