JT-60SA!%"$*&#),




1.  2. JT-60SA 
3. %"$*&#),#'(+-#),
4. %"$*&#),#'(+-#), 
5. 

1

@=A>

2. Research Strategy of JT-60SA

2.1. Mission and Plasma Regimes ofJT-60SA
The project mission of JT-60SA [1,2] is to contribute to early realizationof fusion energy by supporting theexploitation of ITER and by./3*,*7"3*.-.' ./&1"3*.- complementing ITER in resolving key
physics and engineering issues for
2$&-"1*.2DEMO reactors (Fig.2-1).
The JT-60SA device is capable of%&,.-231"3*.-"-%234%6.'23&"%6confining break-even-equivalent classhigh-temperature deuterium plasmas
23"3&)*()#&3"./&1"3*.lasting for a duration (typically 100 s) Fig.2-1 Roles of JT-60SA contributing to ITER
longerthanthetimescales and DEMO
characterizing key plasma processes,
such as current diffusion and particle recycling, using superconducting toroidal and poloidal
field coils. The maximum plasma current is 5.5 MA. The device should also pursue fully
non-inductive steady-state operations with high values of the plasma pressure exceeding theno-wall ideal MHD stability limits. The target regimes of JT-60SA are shown in Fig.2-2. The
JT-60SA experiments should explore ITER and DEMO-relevant plasma regimes in terms ofnon-dimensional plasma parameters at high densities in the range of 11020 m-3.

*22*.-.' *23.$.-31*#43&"-%24//+&,&-3 3.5"1%

l

JOG 9!PQl IMFK P0 8
l HCEMIDLNHCEMIDLN>;:B?
l2<100Fig.2-2 Target regimes of JT-60SAMAGWQFV\FTUZ]FV\<'=7: <+*;"8>@?

MAGWQFV\FTUZ]FV\• ,^_2
• O[]2
• QWHS2<1%1• <(9<$ <1• …

0!
• #%
•  
• .XTJ• R]NQWD

QWHS
• &
• KBP]JCILN• KBP]JEBY• R[BKYEBY• N[BKYEBY• 3/(EBY(FPCC)• RWME\N[]YEBY(RWMC)• -$ )EBY^EFCC_EBY+*2 +*56443

$ "!%#$"%#4"( #&$!('% ) *5

.+-3/,25,0146,25()DINA**
Vacuum vessel (double wall)• Material: SS316L• Thickness: 18mm
• Separated 112 toroidal passive plates
Stabilizing plate (double wall)• Material: SS316L• Thickness: 10mm
• Separated 66 toroidal passive plates
Case

Event

1

Downward VDE
Disruption

2

Upward VDE
Disruption

3

Conditions Event• Caused by vertical instability due to loss of control.
• Disruption (thermal quench) starts at qedge=1.5.
• Current quench starts 0.5 ms after thermal quench.
• Plasma Current decreases linearly in 10 ms and 30 ms.

• Plasma stays at center when disruption (thermal quench)
starts.
Major Disruption• Current quench starts 0.5 ms after thermal quench.
• Plasma Current decreases linearly in 4 ms.

'"%$ & %# %"  !'##&    
%# '"%$ &#'##! "$#&   !

6

JT-60SA   5.5MA • As the initial plasma for DINA simulation we adopted the plasma equilibrium at end ofburn with maximum current 5.5MA and typical other parameters.
EF3



bp0.83



0.71

k1.86

a1.14m

Rcur

2.97m

Zcur

0.034m

q95

2.70

Te

9.1keVZeff

2.0

ne5x1019m-3

M. Takechi et al. FED (2019)

VV EF2CS1SPFPCC

CS2

EF1

CS3
CS4

EF6

EF4

EF57

downward VDE with tCQ=10ms• DINA calculates once every 10ms before thermal quench and every 0.1ms after TQ• Width of SOL before TQ: 1.0cm, after TQ: 3.0cm• Current quench time was adjusted by changing Te.
• Maximum poloidal halo current is 0.99 MA.

8Halo current at upward VDE with tCQ=30ms• Maximum poloidal halo current at upward VDE with tCQ=30ms is 1.03MA, andsmaller than that at downward VDE (1.31MA), andlarger than that at tCQ=10ms (0.74MA)
TQ

CQ (after 0.5ms TQ)
30ms

(b)

(d)

z [cm]

(c)

(a)

(d)

Te [eV]

q95

(c)

(b)
(a)

9

Halo current at central MD with tCQ=4ms• Simulation of central MD was performed with theplasma initially at the neutral point.
• Poloidal halo current at MD is 0.06MA and muchsmaller than that at VDE.
TQCQ(after 0.5ms TQ)
4ms

(g)

Te [eV]

q(c)
(d)
(e)
(f)
(g)

z [cm]

(a)

(b)

(b)
(a)

(f)
(e)
(d)
(c)

10


JT-60SA

Torus Development Gr.

 PF at MD with tCQ=4msEuratom1301/57246326

1• Induced current at disruption of all PF coils are in the same direction as
plasma current. However, Initial current of All CS, EF1, EF2, EF6 coils atdisruption are opposite in sign to plasma current, therefore absolutevalue of current of them decrease after disruption.
• On the other hand, absolute value of current of EF3, EF4, EF5 increaseat disruption. Maximum over current of them is ~1.3kA for EF5. It meansthat if we use EF5 with maximum rated current of 20kA, the current
reach to 21.3kA at disruption.
• Induced current are little affected by change of direction of disruption,difference of current quench time and difference of initial current of PFcoils.
+').,**'-'#) $.,,&*- !( "*'-'#) $.,,&*- !(" % !( "

% !("
14 (FPCC)••••

To hold the horizontal position andto suppress the vertical instability.
Composed of copper conductors
with the hole for water cooling.
Each coil has the independent
power supply.
Maximum rated current is 5kA.
24 turns

15

FPCC

 

JT-60SA

Euratom

Torus Development Gr.

• Previous DINA simulation was performed for the 24-turns FPCC with large crosssection conductor and without SP hole and feeder cable.
• DINA simulations are performed for 23-turns FPCC of current (original) design
consisting of 31mm x 31mm hollow conductor with water channel of f12mm and with
SP hole with/without cable.
• Also DINA simulations are performed for 23-turns and 19-turns FPCC with half crosssection of current (original) design with SP hole and cable.
conductor

Turns

waterchannel
radiussize

SP holecablecrosscoil resist.
resist.
section [m3] [mW][mW]Cabletotal
resist.
resist.[mratioW]

Small

19(23x23)

(12)

YY

4.13E-04

19.3

8.45

27.8

2.37

Small

23(23x23)

(12)

Y

Y

4.13E-04

23.4

8.45

31.8

2.72

original

23

31x31

12

YY

8.26E-04

11.7

8.45

20.1

1.72

original

23

31x31

12

Y

N

8.26E-04

11.7

0

11.7

1.00

previous

24?

?

YN

1.65E-03

5.70

0

5.70

0.49

previous

24?

?

NN

1.65E-03

5.70

0

5.70

0.49

16   
Upper 23 turns FPCC at MD for tCQ=4ms with SP hole and Cable• Resistance = 11.69mΩ (coil) 8.447mΩ (cable)= 20.1mΩ
• Max. IFPCC ~18.8kA• Max. |Br| and |Bz| at FPCC is 0.27T and 0.58T
Fz max Fz min
[MN]
[MN]

Fr max Fr min
[MN]
[MN]

w/ Cable(23)0.8257-0.8208 1.7389 -5.362

w/o Cable(24)0.7889-0.7850 1.6993 -5.699

17

JT-60SAFPCC
Euratom

Torus Development Gr.

• Difference of EM force at FPCC is relatively small (~18%) though the difference ofresistance of FPCC circuit is very large (~5 times)• We cannot decrease the stress requirement for FPCC fixture.

Upper FPCC
conductor Turns SP hole Cable Max IFPCC [kA]
Small
19YY
19.9
Small23
YY
17.3
original
23
YY
18.8
original
23
YN
20.3
previous
24
YN
20.1
previous
24
NN
19.8

IFPCC ratio Fr min [MN] Fr ratio
0.98
-5.39
0.95
0.85
-5.01
0.88
0.93
-5.36
0.94
1.00
-5.68
1.00
0.99
-5.70
1.00
0.98
-5.15
0.91

Lower FPCC *previous results utilized for design
conductor Turns SP hole Cable Max IFPCC [kA]
Small
19YY
18.50
Small23
YY
16.20
original
23
YY17.70
original
23YN
19.10
previous 24
YN
20.30
previous 24
NN
20.00

IFPCC ratio Fr min [MN] Fr ratio
0.97
-5.99
0.94
0.85
-5.56
0.88
0.93
-5.96
0.94
1.00
-6.34
1.00
1.06
-6.70
1.06
1.05
-6.14*
0.97

18



FEMANSYS 

MD 4msS. Asakawa, et al, ” Design of the Fast Plasma Position Control Coils for JT-60SA “
J. Plasma Fusion Res. SERIES, Vol. 9 (2010)19 FPCC Luca Novello, et al. “Overview of the new Magnet Power Supply Systems of JT-60SA
procured by EU “, FED 98–99 (2015) 1122–1126
20

Shibama et al, "Manufacturing Status of JT-60SA Vacuum Vessel and the Related Technology of Welding." Proceedingsof the ASME 2011 Pressure Vessels and Piping Conference. Volume 1: Codes and Standards. Baltimore, Maryland, USA.
July 17–21, 2011. pp. 291-300. ASME. https://doi.org/10.1115/PVP2011-5744021


  

23

24



25     
Plasma current decay and profile, Halo current
waveform (DINA code: toroidal symmetry)
Eddy current and its EMF (EDDYCAL code:3D)

Color10-degree model

Eddy current EMF
at 4.5ms
in MD 4ms caseMaterialEffectiveresistivity

SUS316L

7.70E-7 (Wm)Cu alloy

2.35E-8 (Wm)

SUS 15mm + Cu 25mm

3.70E-8 (Wm)

SUS 15mm + Cu 20mm

4.03E-8 (Wm)

SUS 20mm + Cu 25mm

4.13E-8 (Wm)(Pa)

Max. halo current was normalized as
Ihalo/Ip*TPF<0.5. (ITER physics basis)
Inlet and outlet position of halo current wereartificially provided.

Eddy current EMF
at 20msin VDE 30ms case(Pa)

Halo current EMF
at 20msin VDE 30ms case(Pa)Halo current

S. Sakurai et al. “Design of lower divertor for JT-60SA” FED 85 (2010) 2187–2191

26  Tresca stress (Pa) Tresca stress of a cassette frame and support

VDE 30ms

structure of PFCs are generally small (<0.5Sm).
Overturning force on an outer baffle causes
large local stress in MD 4ms case.
Integrity of bolts and keys fixing a cassettest (MPa) for bolts

ss for keys (MPa)

Inner

Bottom

Outer

Inner

BottomOuter

VDE 30ms

14-30

5.4

8.1

7.8

MD 4ms5844421444

4.4caseATresca stress (Pa) Local stress near the welding joint of cassette

MD 4ms

A: sm+b =132MPa <1.5Sm (VDE 30ms)
B: sm+b =176MPa ~1.5Sm (MD 4ms)

D

B
CIntegrity of fixing bolts for PFC support
ft(MPa) : 69(SUS316), 196(A-286),
300(SUS316L-HiMo class100)
C: st = 109MPa
D: st = 142MPa
Outer baffle support structure shall be improved.
27djk;)RY\;+T3-,
• (@Q1/T=.&lmY[>
T.P.F.(Troidal Peaking Factor)RYZK'S>

T.P.F– T.P.F x Ihalototal / Ip ≦ 0.7 l1/XWLm– T.P.F x Ihalototal / Ip ≦ 0.5 lJT60>JET>DIII-D
PBML1/R:ILm

JT-60SATYCQ1/T>A\fj_bi!
T.P.F x I
/ I = 0.7<^[J\djk;)T$lT.P.F x
IhalototalmU>T.P.FTRYZKeh`g;)T0.5
^4DQB?
EZ>2.5MA75#Tdjk;)$U>
T.P.F x I
/ I = 0.5
1.25MAPJ\?
• cj_bi"RkTa_i^8BL> *Qdjk;)U T(k+1)6HRQ\
Ihalototal / Ip
FA[> R2N(k+1)P0D\VGOA\?
djk;)PT.P.F.T9
lProgress in the ITER Physics Basis Chapter3,cj_bi1L[T$djk;)U>
2007, Nucl. Fusion 47, S128-S202 Y[m1250/72 x (k+1)=17.4(k+1) kA•  R2N>a_i1%R)]\djk;)T$
U>cj_bi1L[Tdjk;)
l=17.4(k+1) kAmPJ\?
halo

halo

total

totalpp

D. Tsuru et al. “Design of inboard first wall for initial operation of JT-60SA”, FED 146 (2019) 1267–1271

28

:'qx{:+ }2i` "rr$ }%3
:'2.5MA +4TFAHXP8n5y|pdml:'s,6,;qj{(/=DCAGX?FAH> XP M<[DJAGX?HAK\XNZGSZDHWY

5.8kA

5.8kA

,6!;k~!
 106k~!
M HAE=X@D>XP B =E]ZDDYY<Z<DCYY>

M DHAD=X@D><OQV

M<=DCAGX?FAH>XP B<=FWY<ZDHWY>

M<=EAFX?CAK><OQV
,6!;#h
M<=DCAGX?FAH>XP Z<HWYBE B =FWYUEZDHWYBI>

M<=DDAIX?FAL><OQV

5.8kA

5.8kA

(17.4n-11.6)kA 5.8kA

5.8kA

5cm 5cm 5cm

k x 17.4 kA

MHAE=X@D> XP

FAHXP M HAKXNZGSZDHWY87clr:'e`,6q9j{5.8kA

5.8kA

15cmRTR
.ECCZDCC

5.8kA(/.DHCZDHC ff70860 50

[MPa]7clr:'s`, 40  44MPa
6q9j{a )
k 30^ (/r4 s#hGGOQV 20 14MPatk~!DGOQVnb{lv` 10xz:'EAHONrqs`X 0
r4-sX_Ea
k= 1
k= 4
k= 3
k= 2
k= 0
k= 534.7kA
86.8kA
69.4kA
52.1kA`(/}7ge$n 17.4kA 7f ko:' t(/ 104.2kA:'2.5MA
wDdblzE unnb{*&ns`:+ s4-a^29

ist6#Z^`6*
2qme[1,DINA[-!W\YQL [T.P.F x Ihalototal [Ojpdl6#[1/2[a(NVFEM (FemtetvW a1,• ist6#y2.5*0.5/6=0.21 [MA]• hsbfr*y2.8 [T] (R=2.387)• ksbfr*y0.8 [T] (DINA^_v• $+\ksbfrw+• $hsbfr ksbfr
' 7R

5R0
-!
0x0
• aQSV] !YS• $4W3/u0W\$4Z x0x0
3/v
• \1,Z^`&)%ungcoaRQS x0x0V]PQYUVSYNvx0• 250x100x400L
10mma"XT`Mx0


=@;
=@;
=?;
=?;
=?;
=?;
=?;
=?;
=?;=?;<;;=;;<;;=;;
@;
=;;
<;;
@;
<;;<;?;;?;;
?;;
?;;
?;;
?;;
?;;
?;;
?;;
?;;

JIK8
GFHEH
9 .v
D AD:?<C
D @<:@=><; BC:;=<<; BA:AD@<; C?:BC@@ =<>:A@D@ <?=:<?>@ <?B:@?A
C D<:<?><; @=D:;C=30

525#"##% &(• &6'5'(#"$/909;4 .)3- :* !#"$
• ,1975
2+8*!#"##%
()

1!" = & * + ,+% '()- (6 )!- = ) & +* + ,+% '()31        

 

          
  

              

            
                                

 

           



32






  

        



JT-60SA

Four types of long Rogowski coils
A. Around VV
B. Inside VV
C. For eddy current of stabilizing plate
D. Plasma current– Length~10m-17m (JT-60U:9.5m)– Outside diameterf8.5mm– With connector for MIC
VV eddy current = IA – IB
Plasma current = IB – IC - IFPCC = ID

A
BC

D

MGI34

ASDEX-U JT-60SA  
Valve Type 5
Gas reservoir [cm³]833Max. gas pressure [MPa]7.5

Max. gas amount [Pam³]

6247

Max. inj. Particles

1.5*1024

Opening time [ms]<2Valve plate lift [mm]7Nozzle diameter [mm]28Size l x b x h[mm]140 x 110 x 305

Piezoelectric stacks

8Required nitrogen pressure
[MPa]

1.5

Closure volume [cm³]94

Dibon et al.,” Spring-driven high speed valve
for massive gas injection in tokamaks “, RSI
88, 033508 (2017)

35

2-3
C7=MG<LR<JKPS<LR0#1+. 0&%/,465




FEM



HQ8AO;8O)

DINA')

FPCC;8O*)

DINA')* *RWMC;8O*)

DINA')*

 *GM>I) Femtet, COMSOL

! * DINAGM>I)*EQS)*')
ITER PB EQS)$

EDDYCAL, ANSYS

(NJ@DINAITER PB EQS)$Femtet

HSDGM:DINA

ANSYS

"

ITER PB EQS)$

A8FS@9?BD

DINA

A8FS@

ITER PB EQS)$GM>I)

GM>I)*EQS)*')
ITER PB EQS)$ANSYSEDDYCAL, ANSYS

36