!"#$%&'()*+,-$(.$%/#0(1/-#/"2(

-3(4$5,"((

!"#$%$&'()*'

'

!"#$%&%'()*+(,-.#/.(0'#'.+123(

42.%3(5."627".8.+(9:;<;:(

5th INTERNATIONAL CONFERENCE ON THE FRONTIERS OF

PLASMA PHYSICS AND TECHNOLOGY

April 21, 2011, Singapore

Outline

•  Early history – the underpinnings in Basic Studies

•  Tokamak program – Aditya and SST-1

- Some highlights

- present status

•  Technology program

•  ITER-India

•  Future roadmap - DEMO

6(

•  +),$**$*,-.''

' '/01-21'/#3-$4-'/56,512'*740)1&)8'1&'&#)'/#3-$410'

'9)-)154#':1"651&653;'!#2)81"18'$*'<=>?'"3'@)A&B'''''

'''''''''''''6C''(4B'D'E)4#B'F@(EG''

'

•  +)412)'1*'H*8)A)*8)*&'1*8'17&6*6267-',51*&I$*I1$8'

H*-J&7&)'6C'@(E'$*'<=>K'1*8'26L)8'&6'&#)'A5)-)*&'412A7-'

'

•  E51*-C)55)8'&6''@)A&B'6C'!&62$4'M*)5,3''$*'<==K'7*8)5'1*'NOP'")&Q))*'&#)'&Q6'8)A15&2)*&-'

'

((

4$+&7*7%(3-/(18"+2"(9%+%"/':(

5

4$+&7*7%((3-/(18"+2"(9%+%"/':(((((((

•  ;<=>?(@%7(*A(B0(7:%(C%A"/72%$7(-3(

@',%$'%((D(E%':(

–  !"#"$"%&"'()*+)",-%.&-.")&/")**0-%)1./"

2.-3&0(04%.*"5%13"*6.-%)(".+63)*%*"0&"

13.7+0&8-(.)7"98*%0&"

–  FC4EGF(7-H"2"H(

•  ;<<>?(I%'"2%("(CF.((3*$5%5(

,$+&7*7%(

–  @@EJ;(7-H"2"H(

•  6KK>?(C-2%+&'(F#%$'0(3-/(4E.9(

•  6KKL?(FAA/-M"8+(-B7",$%5(3-/(

–  E%+7(I8"$H%7(!-5*8%(F'&M,70(

–  1/-7-70A%(F'&M,70(

–  @7"/&$#(7:%(N"&-$"8()*+,-$(1/-#/"2((

Programs at IPR

•  Fundamental Plasma sciences

•  Industrial applications

•  Fusion Technology

Development

•  ITER Collaboration

)*$5"2%$7"8(18"+2"(@',%$'%+(

E:%-/%&'"8("$5(%OA%/,2%$7"8(+7*5,%+(

•  E:%-/0(D(@,2*8"&-$(?(8"+%/JA8"+2"(,$7%/"'&-$P($-$8,$%"/(50$"2,'+P(7-H"2"H(A:0+,'+((

•  .OA%/,2%$7+(?(I.EFP(N-$J$%*7/"8(A8"+2"P(QR1C(

•  C%M%8-A,$#(:*2"$(/%+-*/'%+(3-/(7:%(4$5,"$(3*+,-$(A/-#/"2(

LVPD

BETA

)*+,-$(9%+%"/':(

(

)-'*+%5(-$(C.!S("$5(B%0-$5(

–  E-H"2"H(5%M,'%+(3-/(/%+-8M,$#(,++*%+(%OA%'7%5(,$(3*7*/%(/%"'7-/+(

–  R"/,-*+(A8"+2"(5,"#$-+&'+("$5(A8"+2"('-$7/-8(3-/(-A%/"&-$(

–  .$"B8,$#(7%':$-8-#,%+($%%5%5(3-/(7:%(+7%"50(+7"7%(-A%/"&-$(-3(

7-H"2"H(

–  3*+,-$(B8"$H%7(5%M%8-A2%$7(

–  T*2"$(/%+-*/'%(5%M%8-A2%$7(

8

Existing tokamak devices ADITYA and SST-1

ADITYA

SST-1

9

ADITYA TOKAMAK

•  First Tokamak designed by IPR and

fabricated in India.

•  Commissioned in September 1989

•  Physics :

–  Plasma edge-sol experimental

study led to the discovery of

plasma phenomena

“intermittency” and later to

observe, blob transport, etc.

•  Realized technologies:

–  Large volume UHV toroidal vessel,

–  large copper magnets,

–  various plasma diagnostics,

position and current control

systems

•  Technologies for next device:

–  RF heating and current drive systems developed and tested

in this machine

Achievements

FC4EGF(((.U1EQV((9.@WQE@(

•  4$(7-H"2"H+(%5#%("$5('-/%(A8"+2"("/%(

,$7%#/"7%5("$5(A:%$-2%$"(,$(%5#%(,$X*%$'%(

'-/%(7/"$+A-/7(A/-3-*$580(V((FC4EGF(5%5,'"7%5(

7-(%5#%(7*/B*8%$'%(+7*5,%+(

•  C,+'-M%/%5(,$7%/2,Y%$'0(,$(7-H"2"H(%5#%(

7*/B*8%$'%((Z(1:0+(9%M(Q%Y%/+((><(P(;[L\((((((((((

;<<6](

9%'%$7(%OA%/,2%$7+(,$(FC4EGF(

•  Fluctuation suppression

using gas puff [PPCF 51

(2009) 095010]

•  Discharges with –ve spikes

followed by +ve spikes

[Phys. Plasmas (2010)]

(

48 49 50 51 52 53 54

-15

-10

-5

0

5

10

15

48 49 50 51 52 53 54

-15

-10

-5

0

5

10

15

Experiment

Lo

op

Vo

lta

ge

(V

olt)

Minor Radius (cm)

Simulation

FC4EGF((E.^TNSQS_4.@(

•  Q"/#%(R-8*2%(WTR(E-/-,5"8(R%++%8(

•  Q"/#%(^-AA%/(!"#$%7+(

•  \K(`,8-"2A(+:"A%5(A-a%/(+*AA8,%+(

•  N-M%8(C,"#$-+&'+(

•  C"7"(F'b*,+,&-$("$5(^-$7/-8(@0+7%2+(

•  419("$5(,$5*+7/,%+(8,H%(IT.QP(Q(D(E(P(TIIP(N_.)P((Q"O2,(R,c"0((VVVVV(d-/H%5(7-#%7:%/(

14

ADITYA RF Systems

A 28 GHz 200kW Gyrotron based ECRH system

A 20-40 MHz 200 kW ICRH system for heating

FC4EGF(F@(F(dS9`TS9@.(

•  4^9)(T%"&$#(.OA%/,2%$7((((6KK(`a"Y+(

•  QT^C(.OA%/,2%$7(

•  .^9T((1/%,-$,e"&-$(.OA%/,2%$7((=K(`d(

•  C,"#$-+&'(C%M%8-A2%$7+(?(((((((((((((((((((((((((((((!d(4$7%/3%/-2%7%/(P(Q"+%/(E:-2+-$(@'"Y%/,$#P(@-f(UJ9"0(,2"#,$#P((.^.(9"5,-2%7%/(P(1/-B%+P((R,+,B8%("$5(WR(@A%'7/-+'-A0(P((^:"/#%(.O':"$#%(P(((VVVVV(

@@E(;(

•  @7"7%J-3J7:%J"/7(@*A%/'-$5*'&$#(@7%"50(@7"7%(

E-H"2"H(a,7:(+:"A%5(A8"+2"(D(5,M%/7-/+(

•  C%+,#$%5(3-/("(;KKK(+%'-$5(A*8+%(

•  4$(7:%(+"2%('8"++("+(.F@EP(`@EF9(P(gEJ>K(@W(

Expected parameters

•  n~2x1019 m-3 (nGreenwald ~ 1.8x1020 @ 220kA)

•  Te~1.5-3 keV

•  Ti~1 keV

•  τE~10-20 ms

•  τp~30-60 ms

•  τcd~1-10 sec (current diffusion time)

•  τwall~100-1000 sec

@@E((E.^TNSQS_4.@(

•  @*A%/'-$5*'&$#(!"#$%7+(

•  T,#:(1-a%/(^d((9)((E%':$-8-#,%+(((((((((((((((((

4^9)((h(i\("$5(<K((!Te(((((((((((;V\(!d"Y+(((((((((((((((((((((((((

QT^C((((([VL(_Te((((((((((((((((((((((;((((!d"Y((((((((((((((((((((((((

.^9T((((((=6(_Te((((((((((((((((((((((KV6(!a"Y(

•  N%*7/"8(I%"2+((h(((\K(`%R((((((((6V\((!a"Y(

•  T,#:(:%"7(X*O(/%2-M"8((h((;!d"Yj2(+b(

E%':$-8-#0("':,%M%2%$7+(

C%M%8-A%5(?(

•  Q"/#%(+*A%/'-$5*'&$#(2"#$%7+P('/0-#%$,'(+0+7%2P(7:%/2"8(+:,%85+(

•  F*O,8,"/0(+0+7%2+(8,H%(NI4P(4^9TP(.^9TP(QT^C(%7'V(

•  C,"#$-+&'+P(C"7"("'b*,+,&-$("$5('-$7/-8(+0+7%2+(3-/(+7%"50(+7"7%(-A%/"&-$(-3(7-H"2"H(

•  18"+2"(3"',$#('-2A-$%$7+(8,H%(8,2,7%/(Z+:-/7(5*/"&-$]P(A"++,M%(+7"B,8,e%/("$5(C,M%/7-/(3-/(+7%"50(+7"7%(-A%/"&-$(

E-(B%("':,%M%5(3-/(3*7*/%(/%"'7-/+?(SA%/"&-$"8(%OA%/,%$'%P(A8"+2"('-$7/-8P('-*A8,$#(-3(:%"&$#("$5('*//%$7(5/,M%(+0+7%2P(A"/&'8%("$5(:%"7(:"$58,$#(3-/(+7%"50(+7"7%(-A%/"&-$((

Beam

Voltage

(kV)

Extracted

current

(A)

Extracted

Ion Beam

Power

(MW)

NB

Power

(MW)

30 (H) 35 1 0.5

55 (H) 90 5 1.7

80 (H) 60 4.8 1.5

;(

6(

[\

i

L

>

1. Ion source (PINI) 4 .Deflection Magnet

2 . Gate valve 5 .Cryo Condenstation pump

3 .Neutralizer IInd stage 6 .Ion Dump 7. Beam dump

High voltage power supplies

SST-1 NBI system

100kW beam intercepted by a beam dump

LHCD system 3.7 GHz

ECRH LFS Launcher

ECRH system 82.6 GHz

SST-1 RF system

ICRH system 20-40,91.2 MHz

Summary of research program of SST-1

•  SST-1 tokamak will explore a unique regime of long pulse operation with reactor-like first-wall geometry,

time-integrated heat and particle fluence and similar q-

profiles

•  How to retain good confinement modes in steady-state

will be a major focus

•  The key issues in AT :maintaining a stable equilibrium by

feedback stabilization of locked modes, RWMs, NTMs and control of ELMs for enhancing performance in

steady state – will be researched upon for generating a

database for future reactors(

24

To Study Physics of Plasma

Processes under steady-state

conditions

•  Particle Control

•  Heat removal

•  Current maintenance

SST-1 Progress:

•  First assembled in 2004

•  Integral testing continued up to 2007

•  Leaks were identified and

analyzed

•  New techniques developed to

resolve this and refurbishment was initiated

•  Joints with sub nano-ohms

developed, tested & implemented

•  5 K SHe cooled bubble type shields developed

•  TF coils tested successfully

•  Expected first plasma – Dec.

2012

TF Magnets are through !

ITER-India

General

•  India formally joined the ITER Project in the year 2005.

•  ITER-India is an empowered group created in Institute for

Plasma Research (IPR) to deliver the Indian commitments to

the ITER project.

•  IPR is committed to the long term fusion reactor

programme.

@',%$&+7P(6[(

.$#,$%%/+P(\=(T9(^-$7/"'7P(;[(

.$#,$%%/,$#(@%/M,'%+P(;;(

F52,$,+7/"&-$P(;[( @',%$&k'(F++7VP([(

ITER-India Personnel Distribution

?R'

Procurement Packages

Diagnostic Neutral Beam

RF sources with monitoring and control for IC H&CD

Gyrotrons for plasma start up

Power supplies for DNB, RF, Gyrotrons

Cryo distribution and Cryo line system

Cryostat

Vacuum Vessel In-Wall Shields

Component Cooling, Chilled Water & Heat Rejection System

S(.'S7*4J6*10'(A)4$T41J6*U(+E/.'+7$0&'&6'/5$*&'

Diagnostics

Upper Port Plug

?>'

•  Reinforced, single walled vacuum

vessel with dome-shaped top and

flat-bottom head

•  Overall Dia. ~ height ~29 m, about

400 penetrations, fully welded 50

mm thick SS304

•  Provides a vacuum environment to

avoid excessive thermal loads to

t h e c r y o g e n i c a l l y c o o l e d

components

•  Transfers all loads to the floor

through pedestal columns

•  Provides a secondary confinement

barrier

•  Passive removal of decay heat by

gas conduction and convection

CRYOSTAT & VVPSS

?='

•  Only diagnostics for Helium ash measurement. Supports CXRS, BES Diagnostics

•  Package Type BTP with some FS & DD components

•  Negative H beam, ~60 Amp accelerated & ~20 Amp neutral current injected to

ITER at 100 keV. Development of Beam Source & transport involves R&D

•  Configuration similar to HNB enabling same maintenance protocol

DIAGNOSTIC NEUTRAL BEAM INJECTOR

NB Cell

DNB integrated 3D view

VW'

Aditya

Fusion Plasma Research

Tokamak DEMO Reactor

ITER

ITER&DEMO Physics Support Activities

Component Technology

Test Blanket Module

Blanket Technology Heavy Irradiation

Material Testing Facility Structure Development

Structural Material Dev.

Fusion Engineering

Research

SST-1

Roadmap for Tokamak Reactor Development

Int. Test

Future

)*+,-$(E%':$-8-#0(5%M%8-A2%$7(

1/-#/"2(

•  C%+,#$(-3(C.!S(/%"'7-/(

•  4$7%#/"7%5(A:0+,'+(2-5%8,$#(

•  !"#$%7+(5%M%8-A2%$7(A/-#/"2(

•  C%M%8-A,$#(C,M%/7-/("$5(,7+(/%8"7%5(7%':$-8-#,%+(

•  RRP(^/0-A*2A("$5(3*%8,$#(7%':$-8-#,%+(

•  !"7%/,"8+(5%M%8-A2%$7(A/-#/"2(D(E%+7(3"',8,&%+(

•  NNI4(+0+7%2(

•  9)(+0+7%2(

•  I8"$H%7(+0+7%2(

Road Map envisaged for next twenty years

~2m X 1.8m

SST1:5T,NbTi

~MJ (2005)

~ 4m X 3m

Prototype

6T ,12 T

NbTi, Nb3Sn

Tens of MJ

(2012)

Nb3Sn, Nb3Al

Hundreds of MJ

(2017)

> 12 T

~ 12m X 11m

DEMO relevant

> 12 T

Nb3Sn, Nb3Al GJ class

(2027)

ID 0.6 m X OD 0.9m

ID 1.6m X OD 2.8 m ID 2.0m X OD 4.0 m

Prototype-I

6T, NbTi,

~MJ (2011)

Prototype-II:12 T,Nb3Sn

~ hundreds MJ (2012-17)

12 T, Nb3Sn

~ hundreds MJ (2027)

Magnet Program

IPR & AFD(BARC) have launched a joint initiative towards realizing fusion grade superconductors (NbTi) & Nb3Sn &

Cable-in-conduit-conductors (CICC) since Sep 2006. Several critical technologies & mile stones have been

achieved since then (validated experimentally)

Fusion grade CICC designed (NbTi) Cabled strand NbTi

Strand X-section (NbTi, 0.8 mm dia)

Strand (NbTi)

CICC (NbTi) 30 kA, hybrid

Prototype Magnet

Fusion grade Nb3Sn strand and CICC realization have also been initiated through `Internal Tin’ route for possible PROTOTYPE magnets

Prototype magnet

has been designed

Nb3Sn cables

has been designed

Nb3Sn strands

Trails have begun

Hi Ho Nb rods, OFE Cu

are being developed

Micrograph of pure Nb sample developed

Billet design & billet

OFE Cu billets

C,M%/7-/(A/-#/"2(

•  C,M%/7-/(+:-*85(7"H%(:%"7(8-"5(-3(;\J6K(!dj26(3-/(C.!S(

•  !"7%/,"8+(7-(B%(5%M%8-A%5("/%(d(D(dJ"88-0+P(^)^P(I%(

•  9%2-7%(:"$58,$#(7--8+(7-(B%(5%M%8-A%5(7-(,$+A%'7P(:"$58%("$5(

/%A",/(7:%(5,M%/7-/('"++%Y%((

•  C%M%8-A,$#(3"B/,'"&-$(7%':$-8-#0("$5(7%+7(3"',8,&%+(7-(b*"8,30(

7:%(5,M%/7-/('-2A-$%$7+((

•  C%M%8-A("5M"$'%5(2"7%/,"8+(3-/(C.!S("$5(5%M%8-A(

,$$-M"&M%('-$'%A7+(7-(:"$58%(:,#:(:%"7(X*O((

'E+N'A56,512'

  4$5,"$(EI!(7%"2(,+(5%M%8-A,$#(B-7:(Q,b*,5("$5(@-8,5(

I/%%5%/(B8"$H%7('-$'%A7+?(

(

–  :$X7$8'+5))8)5'&3A).'Q%"5JQ,7:,*2('--8%5(^%/"2,'(I/%%5%/(F::Y+G''

FE6'")'&)-&)8'$*'6*)'#10C'6C'HEM9'A65&'*6I?G'

'

–  (60$8'+5))8)5'&3A)?(T%8,*2(^--8%5(@-8,5(I/%%5%/(FZY(+G'F(7"I

N6870)'&3A)'&)-J*,'$*'46001"651J6*'Q$&#'6&#)5'

HEM9'A15&*)5-G'

(

LLCB TBM Parameters

90 % in Pb-Li Li-6 enrichment

350/480 oC Pb-Li inlet/outlet

0.3 MPa He pressure drop in module

8 MPa Helium pressure

350 / 480 oC He inlet/outlet

Helium and Pb-Li Primary coolant

Al2O3 or Other choice

MHD insulation

SS 316 LN IG Neutron reflector / shield

Pb-17Li, Li2TiO3 Breeder

IN-RAFMS Structural material

;V>>(2(Z:](O(KVi=i(2(Za](O(KV\i(2(Z7]((

QQ^I(

Pb-Li Inlet pipe

Pb-Li Outlet pipe

He Inlet/Outlet

concentric pipe

Bottom Plate

Top Plate

Outer Back Plate

Inner Back Plate

Pb-Li Inlet Manifold

First Wall

Ceramic

Breeder

zones

Helium as Purge gas for Tritium extraction

S7:%/(+0+7%2+(

•  )*%8,$#(+0+7%2(

–  1%88%7(,$c%'7-/(+0+7%2(7-(3*%8(7:%(:,#:(5%$+,70(/%"'7-/(#/"5%(A8"+2"+(

–  4$c%'7(A%88%7+("7("(3"+7%/(/"7%(7-(:"M%('-$&$*-*+(3*%8,$#(

•  R"'**2(M%++%8(D(^/0-(A*2A(

–  C-*B8%(a"88%5(R"'**2(R%++%8(

–  1*2A,$#(/%b*,/%2%$7(-3(C.!S(a,88(B%(-3([(O(;K\(8,7%/+j+(ZN%%5(-3('/0-A*2A(a,7:(;K\(8,7%/+j+](

(Single and double embossed Cryo-panel for

cryo-pump developed and tested

Pellet injector under commissioning

Materials for Blanket (breeding & shielding)

Materials for Magnet

Materials for Divertor

Materials for other systems

Establish the processes

&

make components

Test facility (functionality, heat flux

& neutron irradiation)

Develop materials for DEMO components (2007 – 2027)

modification in choice of materials

for DEMO

2027

Materials program

Like to participate in component test

facility : IFMIF, CTF,

VNS

NBI program

•  C%M%8-A%5(NI4(+0+7%2(3-/(@@EJ;(

Z;VL(!d](

–  T%"7(7/"$+3%/(+0+7%2+(Z;K(!dj

26](

–  )"+7(+a,7':,$#(9TR1@(Z=(!dP(=K(

HR](

–  ^/0-'-$5%$+"&-$(A*2A(Z;K\(

8,7%/+j+](

–  E%':$-8-#,%+(/%8"7%5(7-(,-$(

+-*/'%(

•  1/-M,5,$#(CNI4(3-/(4E.9(Zhi(!d](

•  C%M%8-A,$#(NNI4(3-/(C.!S(ZLK(

!d](

–  1-a%/(+*AA8,%+(-3(;!R(a,7:(

/%b*,/%5('*//%$7(

42

[)7&510'+)12-'.'[),1JL)'$6*'")12-''   M\A)5$2)*&10'A56,512'6C'

A56874J6*'6C'9S'"1-)8'[),1JL)'

$6*''

O"%)4JL)-.'

!  (E6':)15*'467A0$*,'6C'9S'A6Q)5'&6'

A56874)'A01-21'$*'&#)'-6754)U'

Y#1514&)5$]1J6*'6C''A01-21'

!  (&783'L15$67-'T0&)5'T)08'

46*T,751J6*-''C65'6AJ210'-607J6*'

!  +)12')\&514J6*';'144)0)51J6*''D'

4#1514&)5$]1J6*''

RF based Source''

  Present Status:

– Lab established

– CODAC developed inhouse

– Plasma produced by coupling power from 100 kW, 1 MHz RF generator

(R,%a(-3(9)(

2"7':,$#(',/'*,7(

4$7%#/"7%5(+-*/'%(,$(

-A%/"&-$(Z+-*/'%(*$5%/(411(

"#/%%2%$7](

RF system

ICRH 35 MW 20-40 &

91.2 MHz,

1.5/3 MW

SST-1 DEMO

LHCD 3.7 GHz, 1/2 MW

20 MW

ECRH 82.6/140 GHz, 0.2/0.5 MW

20 MW

Activities by RF group

ITER ICRH

20 MW

Human Resource Development Program

•  Initiated a program to bring various labs, universities and industries to participate in

the R&D program of fusion reactor

•  Providing engineering services to many

ITER tasks and available for our own

program

•  Such activities will nucleate various

working groups required for the fusion

reactor

•  Future human resources for fusion will be

developed through this program

SST-1 Tokamak

2004 ADITYA

Tokamak

1986

ITER Participation: 2006

Fusion Tech. Activities 2008

Integrated Tests while doing

experiments on ITER 2030