India

1
Indias Strategy for Fusion Energy

• R. Srinivasan
• Institute for Plasma Research,
• Bhat, Gandhinagar 382 428, India.

2
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

• 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

We need to build and exploit Fusion reactors for
generating power for the future
3
Installed capacity

• 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

R. B. Grover et al., Energy Policy (2006) 2834
Shah RKD, Indian National Academy of
Engineering (1998)
4
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 2100
R. Srinivasan and the Indian DEMO Team, JPFRS
(2010)
5
Indian Fusion Program
DEMO 2037

• Qualification of Technologies
• Qualification of reactor components Process
• Qualification of materials

2 x 1GWe Power plant by 2060
SST-2 2027
Indigenous Fusion Experiment
Note Years represent start of project
6
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
7
Programs Initiated at present in 5-Year Plans

• 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
• 2007-2017
• 2012-2022

8
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

9
Other Areas

• 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

Some of these areas can be addressed with
international collaborations
10
Specific issues to be addressed before DEMO
11
Tritium fuel cycle

• Uncertainty in tritium loss from reactor
• What is the acceptable level of Tritium Breeding
  Ratio (TBR)?
• TBR gt 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

12
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

13
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
14
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 (Q10)
• ITER experiments may reveal the future direction
  in this aspect

Needs DEMO like machine
15
Future devices to address these issues
16
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

17
SST-2
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
ltTgt keV 4.5
?N 1.31

• 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

18
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

19
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
ltTgt keV 21.5
?N 3.3

• 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

20
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 lt 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
21
Indian R D efforts
22
RAFMS Structural Material Development

• 2 nos. of 3000 Kg commercial melts completed
• Chemical Composition under control
• Forging and rolling into Plates completed

Forging of IN-RAFMS
IN-RAFMS Plates
IN-RAFMS INGOT
22
22
Characterisation under progress
23
Photomicrograph of Li2TiO3 after sintering at
1250oC, 4 hours, by SOL-GEL Process

• Other materials
• SS316LN
• borated steel

Samples of various tungsten materials produced
using powder metallurgical route
Large scale production of materials has to be
established through Indian industries/national
labs
24
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

25
Preliminary results for CICC
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
  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.

26
Magnet testing
Large Experimental Cryostat (6 m high, 5 m
diameter
VPI Facility developed
Internal Tin Nb3Sn strands being characterized
27
Lead-Lithium Loop at IPR Experiment Corrosion
Studies
Loop Parameters Hot leg temperature 550
C Temperature difference between hot and cold
legs 95 C Flow velocity - 5 cm/sec. Corrosion
Sample - RAFMS
28
Neutral Beams Negative ion beams
RF based Source
Integrated source in operation (source under IPP
agreement)

• 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

28
29
Human Resource Development Program

• Initiated to bring various labs, universities
  and industries to participate in the RD 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

30
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.

31
Thank you