india’s strategy for fusion energy

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India’s Strategy for Fusion Energy R. Srinivasan Institute for Plasma Research, Bhat, Gandhinagar – 382 428, India.

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India’s Strategy for Fusion Energy. R. Srinivasan Institute for Plasma Research, Bhat, Gandhinagar – 382 428, 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 2030. Aim for 25 % share by 2050. - PowerPoint PPT Presentation

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Page 1: India’s Strategy for Fusion Energy

India’s Strategy for Fusion Energy

R. Srinivasan

Institute for Plasma Research,

Bhat, Gandhinagar – 382 428, India.

Page 2: India’s Strategy for Fusion Energy

Energy scenario in India

Judicious mix of Non-fission & Fission to supply the immediate needs

Fission Projection: 20 GWe by 2020, 60 GWe by 2030. Aim for 25 % share by 2050

We need to build and exploit Fusion reactors for generating power for the future

• Total Power Generated: 180.4 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, 31-07-2011

Page 3: India’s Strategy for Fusion Energy

Installed capacity

R. B. Grover et al., Energy Policy (2006) 2834

• 1947 1363 MWe

• 1980-81 30,214 MWe

• 1990-91 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)

Page 4: India’s Strategy for Fusion Energy

Installed capacity : Beyond 2050

Without fusion With 10 % fusion

Shows 890 GWe (34 %) by Nuclear in 2100

Fall of contribution from coal near 2100. 2 GWe by 2060 and 250 GWe (10%) by fusion in 2100R. Srinivasan and the Indian

DEMO Team, JPFRS (2010)

Page 5: India’s Strategy for Fusion Energy

Indian Fusion Program

First Tokamak

ADITYA 1984

Steady State Physics and related technologies

SST-1 1996

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 2050

2 x 1GWe Power plant by 2060

Note: Years represent start of project

SST-2 2027

DEMO 2037

Page 6: India’s Strategy for Fusion Energy

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

Page 7: India’s Strategy for Fusion Energy

• 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

Color2007-2017

2012-2022

Programs Initiated at present in 5-Year Plans

Page 8: India’s Strategy for Fusion Energy

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

Page 9: India’s Strategy for Fusion Energy

• 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

Page 10: India’s Strategy for Fusion Energy

Specific issues to be addressed before DEMO

Page 11: India’s Strategy for Fusion Energy

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

Page 12: India’s Strategy for Fusion Energy

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

Page 13: India’s Strategy for Fusion Energy

Divertor

• ITER will establish the capability of handling heat load about 5-8 MW/m2

• For DEMO, this will be higher by a factor of 2 (15 -20 MW/m2)

• 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

Page 14: India’s Strategy for Fusion Energy

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

Page 15: India’s Strategy for Fusion Energy

Future devices to address these issues

Page 16: India’s Strategy for Fusion Energy

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

Page 17: India’s Strategy for Fusion Energy

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

R0 4.4

a 1.5

A 3.0

Bt (T) 5.4

Ip(MA) 11

fbs(%) 11.5

Ploss(MW) 40

Pfusion (MW) 100

Paux(MW) 20

Q 5

n/nGW 0.93

<T> keV 4.5

N 1.31

Page 18: India’s Strategy for Fusion Energy

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

Page 19: India’s Strategy for Fusion Energy

– 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

R0 7.7

a 2.6

A 3.0

Bt (T) 6.0

Ip(MA) 17.8

fbs(%) 50

Ploss(MW) 720

Pfusion (MW) 3300

Paux(MW) 110

Q 30

n/nGW 0.93

<T> keV 21.5

N 3.3

Page 20: India’s Strategy for Fusion Energy

Choices for Indian DEMO

• TF with Nb3Sn

• Plasma facing components with W and W-alloys

• Blanket concept : LLCB with Pb-Li and LiTi2O3

• 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

Page 21: India’s Strategy for Fusion Energy

Indian R & D efforts

Page 22: India’s Strategy for Fusion Energy

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RAFMS – Structural Material Development

22

Forging of IN-RAFMS IN-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

Page 23: India’s Strategy for Fusion Energy

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 Li2TiO3 after sintering at 1250oC, 4 hours, by SOL-GEL Process:

Page 24: India’s Strategy for Fusion Energy

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

Page 25: India’s Strategy for Fusion Energy

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 492Nb-Ti Filaments

• CICC developed at IPR and BARC have shown that 11000 A of current could be passed at 6 K against designed value of 10000 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

Page 26: India’s Strategy for Fusion Energy

VPI Facility developed

Large Experimental Cryostat (6 m high, 5 m diameter

Internal Tin Nb3Sn strands being characterized

Magnet testing

Page 27: India’s Strategy for Fusion Energy

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

Page 28: India’s Strategy for Fusion Energy

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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)

Page 29: India’s Strategy for Fusion Energy

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

Page 30: India’s Strategy for Fusion Energy

Conclusions• Indian DEMO roadmap is driven by the energy requirement• The commercial power plant is expected by 2060. 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.

Page 31: India’s Strategy for Fusion Energy

Thank you