2. BARC roadmap of R & D for the thermo-chemical process based hydrogen production Demonstration using 600 MW Th HTR : ~ 80,000 m 3 H 2 /hr Demonstration with metallic chemical reactors :~ 13 m 3 H 2 /hr Lab scale demonstration : ~ 50 L H 2 /hr Early R&D -Studies on reactions & separations Experimental studies for improving specific processing methods Evaluation & Development of materials System design : Process, chemical reactors FLOWSHEETING Process simulation using chemical process simulator
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4. Nuclear hydrogen production system being developed in BARC is to satisfy total energy needs of a region in the form of hydrogen, electricity and potable water
5. Several innovations in the areas of fuel, materials, passive reactor safety, efficient heat removal systems & liquid heavy metal coolant technology mark CHTR configuration.
6. Nuclear Power is the greatest facilitator of energy security in countries with inadequate domestic energy resources REACTOR Requirement of natural uranium for a 1000 MWe Nuclear Power Plant: ~ 160 t /Year. Requirement of coal for a 1000 MWe Coal fired plant ~ 2.6 million t / Year (i.e. 5 trains of 1400 t /Day)
7. 'The ice is melting much faster than we thought' “ Even if they (opponents of nuclear energy) were right about its dangers, and they are not, its worldwide use as our main source of energy would pose an insignificant threat compared with the dangers of intolerable and lethal heat waves and sea levels rising to drown every coastal city of the world. We have no time to experiment with visionary energy sources; civilisation is in imminent danger and has to use nuclear - the one safe, available, energy source - now or suffer the pain soon to be inflicted by our outraged planet.” - Eminent Environmental Scientist, James Lovelock, The Independent, May 24, 2004
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9. Development of Nuclear Power - Chronology 1970's – Oil Shock 1979 - TMI Accident 1986 - Chernobyl Accident Major Events Affecting Growth of Nuclear Power 1990's – Liberalisation of electricity market and availability of cheap gas
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11. The fission reaction Fission of 1 gm of U-235 per day generates ~1 MW Power 92 U 235 + 0 n 1 36 Kr 92 + 56 Ba 141 + 3( 0 n 1 ) + Energy 92 U 235 + 0 n 1 42 Mo 95 + 57 La 139 + 7( -1 e 0 ) + 2( 0 n 1 ) + Energy Mass 'm1'= 236.0526 g Mass 'm2'= 235.8332 g Difference in mass Δm = 0.2194 gm E = Δm * c 2 c, velocity of light = 3 x10 8 m/s Neutron Nucleus n Radiation Fission Fragments ~200 MeV of Energy Compound Nucleus in an excited state of high internal energy Fast-n
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13. Slowing down (thermalisation or moderation) of fission neutrons facilitates lower critical mass, but leads to some loss of neutrons through absorption in the moderator Energy distribution of fission neutrons peaks at ~ 0.7 MeV with average energy at ~ 1.9 MeV. Variation of fission cross-section (barns) of U-235 with neutron energy (eV) Thermal Reactors Fast Reactors Cross-section : The effective target presented by a nucleus for collisions leading to nuclear reactions . 1 barn = 10 -24 cm 2
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15. Conversion of fertile material to fissile material is made possible by neutron capture reactions 92 U 238 + 0 n 1 92 U 239 + (Fertile) 93 Np 239 + (Fissile) 94 Pu 239 + (n, ) 90 Th 232 + 0 n 1 90 Th 233 + (Fertile) 91 Pa 233 + (Fissile) 92 U 233 + (n, )
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17. There are two options for a “Nuclear Fuel Cycle” : “Open”, and “Closed” FRESH FUEL RECYCLED FUEL FABRICATION REPROCESSING REFINING (U & Th CONCT.) 235 U ENRICHMENT NUCLEAR POWER PLANT SPENT FUEL WASTE CONDITIONING MINING U & Th ORES CLOSED CYCLE OPEN CYCLE WASTE DISPOSAL Th 232, U 238 U 233, Pu 239 FISSION PRODUCTS ENERGY
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20. The three stage Indian Nuclear Power Programme aims to achieve long-term energy security through self-reliance. 3 rd Stage: Thorium- 233 U based reactors 2 nd Stage: Fast Breeder Reactors using Pu as fuel and breeding Pu and 233 U. 1 st Stage: Pressurised Heavy Water Reactors using Natural Uranium as fuel and producing Plutonium which is recovered in reprocessing plants for initiating the 2 nd Stage
21. The current Indian nuclear power reactors belong to six different configurations DIFFERENT POWER REACTOR CONFIGURATIONS ORDINARY WATER MODERATED REACTORS PRESSURISED WATER Cooled HEAVY WATER MODERATED REACTORS FAST BREEDER REACTORS BOILING WATER Cooled PRESSURISEDHEAVY WATER Cooled Tarapur 1&2 Rajasthan Kalpakkam Narora Kaiga Kakarapar, Tarapur Kalpakkam GAS COOLED REACTORS OTHER REACTORS Kundankulam BOILING WATER Cooled AHWR CHTR
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23. Indian Nuclear Power Programme till 2020 21,080 13,900 Projects planned till 2020 PHWRs(8x700 MWe), FBRs(4x500 MWe), LWRs(6x1000 MWe), AHWR(1x300 MWe) 7,180 500 PFBR at Kalpakkam under construction ( 1 X 500 MWe) 6,680 2,000 2 LWRs under construction at Kudankulam(2x1000 MWe) 4,680 1,420 5 PHWRs under construction at Tarapur (1x540 MWe),Kaiga (2x220 MWe), RAPS-5&6(2x220 MWe) 3,260 3,260 13 reactors at 6 sites under operation Tarapur, Rawatbhata, Kalpakkam, Narora, Kakrapar and Kaiga CUMULATIVE CAPACITY (MWe) CAPACITY (MWe) REACTOR TYPE AND CAPACITIES
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26. These fuel clusters reside in 452 out of 505 lattice positions in a vertical core having Heavy Water moderator Typical incore detector (36 positions) 452 Fuel Channels 4 4 4 41 Shim Rod SR Regulating Rod RR Absorber Rod AR Shut off Rod N 20,000 MWd/Te 23,500 MWd/Te 30,000 MWd/Te
27. The reactor is located in the basement with four steam drums located at the top GDWP Header Moderator System Tail Pipe Tower Down comers Advanced Accumulators Isolation Condensers Feeder pipes MHT Purification system PW Header ECC Pipes Tail pipes Steam drums Vertical Sectional View
28. Boiling water under natural circulation (i.e., no pumps are used in the main coolant circuit) cools the fuel clusters Heat removal from core under both normal full power operating condition as well as shutdown condition is by natural circulation of coolant.
29. Even if the largest size pipe suddenly breaks, the Emergency Core Cooling System (ECCS) will flood the core with cold water, without any operator or control action Passive injection of cooling water, initially from accumulator and later from the overhead GDWP, directly into fuel cluster. (Th + Pu)O 2 24 pins (Th + U 233 )O 2 30 pins Water Tube Displacer Rod
30. The reactor has unique advanced safety features to reliably cool it and shut it down even with human failure, power failure, and failure of all wired controls. Pressure 70 bar Pressure 71 bar Pressure 76.5 bar Pressure 82 bar Steam overpressure can passively shut down reactor
31. “ There is no power as costly as no-power” – Homi Bhabha
44. Production in 2000 34,746 Total world 422 others 319 France 200 India (est) 500 Czech Republic 500 Ukraine (est) 500 China (est) 878 South Africa 1,456 USA 1,752 Kazakhstan 2,000 Russia (est) 2,350 Uzbekistan 2,714 Namibia 2,895 Niger 7,578 Australia 10,682 Canada 2000 Priargunsky 2018 KazAtomProm 2239 Rossing 2400 Navoi 3564 ERA 3693 WMC 6643 Cogema 7218 Cameco tonnes U company
Combustion of 1 atom of C => 4 eV; Fission of 1 atom of U => 200 MeV
In thermal reactors, the fission is caused by thermal neutrons having energy less than 0.025 eV. This type of reactor uses natural uranium as fuel. The neutrons generated during fission posses very high energy which are slowed down with the help of a moderators to reduce the energy of neutrons less than 0.025 eV. In fast reactors, fission is basically caused by neutron possessing energy more than 1 MeV. Another important process that is taking place in the fast reactor is breeding of fissile material.
In the first stage of our programme we have 12 PHWRs and 2 boiling water reactors operating with high capacity ratio. 8 more reactors are under construction and several other are planned to have potential od generating 10 GWe. A fast breeder test reactor (FBTR) of 40 MW thermal capacity is operating and has given us experience in fast breeder reactor technology. In this category, a 500 Mwe Prototype Fast Breeder Reactor (PFBR) is under construction. We have now initiated the third stage also with a 30 MW thermal reactor named KAMINI which uses thorium fuel. As a futher development in this stage an Advance Heavy Water Reactor (AHWR) and Compact Heavy Water Reactor (CHTR) are being developed. The development of ADS I.e Accelerated Driven Systems can enable early introduction of Thorium on a large scale.
