India’s Strategy for Fusion Energy R. Srinivasan Institute for Plasma Research, Bhat, Gandhinagar – , India.

Energy scenario in India  Judicious mix of Non-fission & Fission to supply the immediate needs  Fission Projection: 20 GWe by 2020, 60 GWe by Aim for 25 % share by 2050 We need to build and exploit Fusion reactors for generating power for the future Total Power Generated: GW 65.0 % Total Thermal Coal 54.6% Gas 9.8% Oil 0.7% 21.0 % Hydro 2.7 % Nuclear 11.2 % Renewable Ministry of Power, India,

Installed capacity R. B. Grover et al., Energy Policy (2006)  1363 MWe  30,214 MWe  66,086 MWe # 2003  138,730 MWe Growth rates : 9.54,8.14 and 6.26%/yr Beyond 2022, intensity fall by 1.2 %/yr # Shah RKD, Indian National Academy of Engineering (1998)

Installed capacity : Beyond 2050 Without fusion With 10 % fusion Shows 890 GWe (34 %) by Nuclear in 2100 Fall of contribution from coal near GWe by 2060 and 250 GWe (10%) by fusion in 2100 R. Srinivasan and the Indian DEMO Team, JPFRS (2010)

Indian Fusion Program First Tokamak ADITYA 1984 Steady State Physics and related technologies SST scientific and technological feasibility of fusion energy ITER Participation 2005 Qualification of Technologies Qualification of reactor components & Process Qualification of materials Indigenous Fusion Experiment Fusion Power Reactor Power Plant x 1GWe Power plant by 2060 Note: Years represent start of project SST DEMO 2037

Technologies to realize DEMO Technologies needed for DEMO Tritium breeding blankets Divertor components capable of taking high heat flux Fuel Cycle Materials which can withstand high heat flux and neutron irradiation and their joining technologies High Power Heating and Current Drive Systems Large sized superconducting magnets Kick-start activities for SST-2 & DEMO

Materials development & qualification program Blanket technology development program Divertor technology development program Fuel Cycle technology development program Magnet technology development program NBI system development program RF system development program Remote Handling Technology development program Color Programs Initiated at present in 5-Year Plans

Critical areas Fusion grade materials –Development of structural and functional materials –Irradiation & test facilities for qualification –Capacity building for large scale production Tritium fuel cycle –Tritium startup inventory –Tritium extraction and fuel processing –Storage Large size reactor components and their fabrication issues –Blanket, Divertor, Magnets and VV –Remote handling, fabrication techniques like hipping, EB wielding

Technologies related to auxiliary systems –RF sources : gyrotron, klystron, and tetrode tubes –Ion sources, high heat transfer elements, RHVPS –HTC leads –Cryosorption pumps, extruders for pellet injectors –Heat extraction system for Pb-Li loop and He loop –Plant control Other Areas Some of these areas can be addressed with international collaborations

Specific issues to be addressed before DEMO

Tritium fuel cycle Uncertainty in tritium loss from reactor What is the acceptable level of Tritium Breeding Ratio (TBR)? TBR > 1.1 or 1.2, decides the design of breeding blanket concept, thickness of breeding zones ITER TBM program may not be able to answer this Needs an integrated testing of breeding blanket Medium size tokamak with D-T operation to produce tritium may answer this

Reactor Availability Issues Indian DEMO is expected to have 30 % availability at the start and has to be maximized by gaining experience in operation Quantifying reactor availability before DEMO is crucial ITER operation may give estimate about availability but ITER is without breeding blankets The maintenance/ repairing requirements of breeding blankets may not be realized in ITER device Remote Handling of such module needs to be developed by experience There seems to be a need of a an interim device with all breeding blankets

Divertor ITER will establish the capability of handling heat load about 5-8 MW/m 2 For DEMO, this will be higher by a factor of 2 ( MW/m 2 ) Presently available materials are W and W-alloys Develop new materials to take such high heat flux Qualification for high dpa Innovative divertor concepts like X-div., liquid div., also need to explored during design. Experiments in SST-1 will demonstrate Double null Vs Single null operations. Innovative concepts will also be tried out

Ignited plasma issues Alpha particle will provide the dominant heating mechanism in DEMO Alpha particle heating has to be supported with external heating Identifying the state of plasma operation and control the power accordingly ITER may tell about the alpha heating in presence of dominant external heating (Q~10) ITER experiments may reveal the future direction in this aspect Needs DEMO like machine

Future devices to address these issues

SST-2 Should act as first step for verifying the choices being made for DEMO A medium size tokamak with pulsed D-T operation With breeding blanket at the outboard side Should provide the first integrated test of some systems being developed for DEMO Should address the tritium breeding, possible losses and recovery Will be able to address alpha particle issues Remote handling of components and maintenance Address availability of machine with breeding blankets

SST-2 –Build with existing technologies –Pulsed D-T machine –Low Q machine and less fusion power output –Experience in tritium handling –Achieving steady Q & Fusion power output –Tritium breeding will not be self-sufficient (should test the breeding performance) –Should be the test bed for all developmental activities Plasma parameters SST-2 R0R0 4.4 a1.5 A3.0 B t (T)5.4 I p (MA)11 f bs (%)11.5 P loss (MW)40 P fusion (MW)100 P aux (MW)20 Q5 n/n GW 0.93 keV4.5 NN 1.31

DEMO DEMO should have most features of the power plant Thermal efficiency should be maximized Should couple electricity to the grid Should address the integrated machine performance Tritium self-sufficiency should be achieved Machine availability should be enhanced for realizing a power plant All the issues expected in an ignited plasma scenario should be addressed in this device

–Production of more than 1 GW of net electricity –with 30 % availability –Less aggressive (any improvement will be a boost) –Try to improve the availability –Performance of reactor and its optimization Indian DEMO Plasma parameters Indian DEMO R0R0 7.7 a2.6 A3.0 B t (T)6.0 I p (MA)17.8 f bs (%)50 P loss (MW)720 P fusion (MW)3300 P aux (MW)110 Q30 n/n GW 0.93 keV21.5 NN 3.3

Choices for Indian DEMO TF with Nb 3 Sn Plasma facing components with W and W-alloys Blanket concept : LLCB with Pb-Li and LiTi 2 O 3 Structural : IN-RAFMS VV : SS316LN Shielding : borated steel Allowable dpa on structural material < 50 (?) Double null or Single null Thermal efficiency with 30 % Design will have many variants with mid-term, long- term projections. Few choices on dream materials or concepts have to be made and pursued

Indian R & D efforts

22 RAFMS – Structural Material Development 22 Forging of IN-RAFMSIN-RAFMS PlatesIN-RAFMS INGOT 2 nos. of 3000 Kg commercial melts completed Chemical Composition under control Forging and rolling into Plates completed Characterisation under progress

Samples of various tungsten materials produced using powder metallurgical route Other materials : SS316LN borated steel Large scale production of materials has to be established through Indian industries/national labs Photomicrograph of Li 2 TiO 3 after sintering at 1250 o C, 4 hours, by SOL-GEL Process:

Test facilities to qualify materials High- heat flux facility –200 kW of electron beam testing facility to test the helium and water cooled components –To simulate HHF during ELMs, a test facility is being planned Neutron Irradiation facility –fission reactors available to test up to a fraction of dpa –Effect of 14 MeV neutrons will be important to qualify materials –SST2 will be used as the test facility for 14 MeV neutrons –Interested to participate in other international irradiation facilities

Cross section of 20x20mm CICC containing 336 wires of 0.8mm dia out of which 48 nos. are SC wires 0.8mm dia SC wire having 492 Nb-Ti Filaments CICC developed at IPR and BARC have shown that A of current could be passed at 6 K against designed value of A at 4.5 K supercritical helium. This hybrid conductor has about 25% less superconductor compared to that of SST-I conductor. Preliminary results for CICC

VPI Facility developed Large Experimental Cryostat (6 m high, 5 m diameter Internal Tin Nb3Sn strands being characterized Magnet testing

Loop Parameters: Hot leg temperature : 550 C Temperature difference between hot and cold legs ~95 C Flow velocity - 5 cm/sec. Corrosion Sample - RAFMS Lead-Lithium Loop at IPR Experiment: Corrosion Studies

28 Neutral Beams : Negative ion beams Experimental program of production of RF based Negative ion  Experience in coupling of RF power to produce plasma in the source; Characterization of plasma  Study various filter field configurations for optimal solution  Beam extraction, acceleration & characterization RF based Source Integrated source in operation (source under IPP agreement)

Human Resource Development Program Initiated to bring various labs, universities and industries to participate in the R&D program of fusion reactor Provided engineering services to many ITER tasks and this is available for our own program These activities will nucleate various working groups required for the fusion reactor Future human resources for fusion will be developed through this program Need of innovative ideas to attract young minds to sustain this long term program

Conclusions Indian DEMO roadmap is driven by the energy requirement The commercial power plant is expected by If this can be accelerated, this will have major impact on Indian energy scenario Materials and other fusion technologies pursued with definite goals Network research and a strong interaction between R & D labs and the Indian industries is being pursued Through BRFST, a reasonable achievement in network research has been achieved and is expected to grow rapidly in the coming decades Fusion program has a strong momentum now which is going to become more intense and focused in the coming decade Interaction with like minded groups around the world is going to play a crucial peer group role in these developments.

Thank you