Overview of JT-60U Results for Development of Steady-State Advanced Tokamak Scenario
H. Takenaga1) and the JT-60 Team
21st IAEA Fusion Energy Conference16 - 21 October2006
Chengdu, China
OV/1-2
1) Japan Atomic Energy Agency
1997
Enhanced national and international collaborations.
National collaborations : as the central tokamak in Japanese fusion research.
International collaborations : including IEA/ITPA collaboration.
The JT-60 TeamJT-60U
N.Aiba1), H.Akasaka, N.Akino, T.Ando3), K.Anno, T.Arai, N.Asakura, N.Ashikawa4), H.Azechi5), M.Azumi, L.Bruskin6), S.Chiba, T.Cho7), B.J.Ding8), N.Ebisawa, T.Fujii, K.Fujimoto1), T.Fujita, T.Fukuda5), M.Fukumoto5), A.Fukuyama9), H.Funaba4), H.Furukawa2), M.Furukawa10), P.Gohil11), Y.Gotoh2), L.Grisham12), S.Haga2), K.Hamamatsu, T.Hamano2), K.Hanada13), M.Hanada, K.Hasegawa, H.Hashizume14), T.Hatae, A.Hatayama15), T.Hayashi2), N.Hayashi, T.Hayashi, H.Higaki7), S.Higashijima, U.Higashizono7), T.Hino16), T.Hiraishi17), S.Hiranai, Y.Hirano18), H.Hiratsuka, Y.Hirohata16), J.Hobirk19), M.Honda9), A.Honda, M.Honda, H.Horiike5), K.Hoshino, N.Hosogane, H.Hosoyama2), H.Ichige, M.Ichimura7), K.Ida4), S.Ide, T.Idehara20), H.Idei13), Y.Idomura, K.Igarashi2), S.Iio21), Y.Ikeda, T.Imai7), S.Inagaki4), A.Inoue2), D.Inoue7), M.Isaka, A.Isayama, S.Ishida, K.Ishii2), Y.Ishii, M.Ishikawa14), Y.Ishimoto1), K.Itami, T.Itoga14), Sanae Itoh13), Satoshi Itoh13), K.Iwasaki2), Y.Kagei1), S.Kajiyama22), S.Kakinoto7), M.Kamada1), Y.Kamada, A.Kaminaga, K.Kamiya, S.Kasai, K.Kashiwa, K.Katayama13), T.Kato4), M.Kawai, Y.Kawamata, Y.Kawano, T.Kawasaki13), H.Kawashima, M.Kazawa, K.Kikuchi2), H.Kikuchi2), M.Kikuchi, A.Kimura9), H.Kimura23), H.Kimura, Y.Kishimoto9), S.Kitamura, K.Kiyono, K.Kizu, N.Kobatake22), M.Kobayashi2), S.Kobayashi9), Y.Kobayashi9), T.Kobuchi4), K.Kodama, Y.Kogi13), Y.Koide, A.Kojima1), S.Kokubo17), S.Kokusen2), M.Komata, A.Komori4), T.Kondoh, S.Konishi9), S.Konoshima, S.Konovaliv24), A.Koyama9), M.Koyanagitsu23), T.Kubo5), H.Kubo, Y.Kudoh, R.Kurihara, K.Kurihara, G.Kurita, M.Kuriyama, Y.Kusama, N.Kusanagi2), J.Li24), J.Lonnroth25), T.Luce11), T.Maekawa9), K.Masaki, A.Mase13), M.Matsukawa, T.Matsumoto, M.Matsuoka26), Y.Matsuzawa2), H.Matumura2), T.Matunaga1), K.Meguro2), K.Mima5), O.Mitarai27), Y.Y.Miura5), Y.Miura, N.Miya, A.Miyamoto2), S.Miyamoto5), N.Miyato, H.Miyauchi23), Y.Miyo, K.Mogaki, Y.Morimoto23), S.Moriyama, M.Nagami, Y.Nagasaka22), K.Nagasaki9), Y.Nagase13), S.Nagaya, Y.Nagayama4), H.Naito28), O.Naito, T.Nakahata23), N.Nakajima4), Y.Nakamura4), K.Nakamura13), T.Nakano, Y.Nakashima7), M.Nakatsuka5), M.Nakazato2), Y.Narushima4), R.Nazikian12), H.Ninomiya, M.Nishikawa13), K.Nishimura4), N.Nishino29), T.Nishitani, T.Nishiyama, N.Noda4), K.Noto2), H.Nuga10), K.Oasa, T.Obuchi4), I.Ogawa20), Y.Ogawa10), H.Ogawa, T.Ohga3), N.Ohno17), K.Ohshima2), T.Oikawa, A.Oikawa, M.Okabayashi12), N.Okamoto17), K.Okano30), F.Okano, J.Okano, K.Okuno23), Y.Omori, A.Onoshi23), Y.Ono10), H.Oohara, T.Oshima, Y.Oya10), N.Oyama, T.Ozeki, V.Parail25), H.Parchamy4), B.J.Peterson4), G.D.Porter31), A.Sagara4), G.Saibene32), T.Saito7), M.Sakamoto13), Y.Sakamoto, A.Sakasai, S.Sakata, T.Sakuma2), S.Sakurai, T.Sasajima, M.Sasao14), F.Sato2), M.Sato, K.Sawada33), M.Sawahata, M.Seimiya, M.Seki, J.P.Sharpe34), T.Shibahara17), K.Shibata2), T.Shibata, T.Shiina, R.Shimada21), K.Shimada, A.Shimizu13), K.Shimizu, M.Shimizu, K.Shimomura21), M.Shimono, K.Shinohara, S.Shinozaki, S.Shiraiwa10), M.Shitomi, S.Sudo4), M.Sueoka, A.Sugawara2), T.Sugie, K.Sugiyama17), A.M.Sukegawa, H.Sunaoshi, Masaei Suzuki2), Mitsuhiro Suzuki2), Yutaka Suzuki2), S.Suzuki, Yoshio Suzuki, T.Suzuki, M.Takahashi2), R.Takahashi2), K.Takahashi2), S.Takamura17), S.Takano2), Y.Takase10), M.Takechi, N.Takei, T.Takeishi13), H.Takenaga, T.Takenouchi2), T.Takizuka, H.Tamai, N.Tamura4), T.Tanabe13), Y.Tanai2), S.Tanaka9), J.Tanaka9), S.Tanaka10), T.Tani, K.Tani, H.Terakado2), M.Terakado, T.Terakado, K.Toi4), S.Tokuda, T.Totsuka, Y.Toudo4), N.Tsubota2), K.Tsuchiya, Y.Tsukahara, K.Tsutsumi2), K.Tsuzuki, T.Tuda, T.Uda4), Y.Ueda5), T.Uehara2), K.Uehara, Y.Ueno9), Y.Uesugi35), N.Umeda, H.Urano, K.Urata2), M.Ushigome10), K.Usui, K.Wada2), M.Wade11), K.Watanabe4), T.Watari4), M.Yagi13), Y.Yagi18), H.Yagisawa2), J.Yagyu, H.Yamada4), Y.Yamamoto9), T.Yamamoto, Y.Yamashita2), H.Yamazaki2), K.Yamazaki4), K.Yatsu7), K.Yokokura, I.Yonekawa3), M.Yoshida1), H.Yoshida5), N.Yoshida13), M.Yoshida13), H.Yoshida16), H.Yoshida, A.Yoshikawa23), M.Yoshinuma4), H.Zushi13)
Japan Atomic Energy Agency, 1)Post-Doctoral Fellow, 2)Staff on loan, 3)Nippon Advanced Technology Co.Ltd., Japan
8)Southwestern Institute of Physics, China, 11)General Atomics, USA, 12)Princeton Plasma Physics Laboratory, USA, 19)Max-Planck-Institut fur Plasmaphysik, Germany, 24)JAERI Fellow, 25)Euratom/UKAEA Association, UK, 31)Lawrence Livermore National Laboratory, USA, 32)EFDA Closed Support Unit, Germany, 34)Idaho National Engineering and Environmental Laboratory, USA
4)National Institute for Fusion Science, Japan, 5)Osaka University, Japan, 6)Japan Society of the Promotion of Science Invitation Fellowship, 7)University of Tsukuba, Japan, 9)Kyoto University, Japan, 10)The University of Tokyo, Japan, 13)Kyushu University, Japan, 14)Tohoku University, Japan, 15)Keio University, Japan, 16)Hokkaido University, Japan, 17)Nagoya University, Japan, 18)National Institute of Advanced Industrial Science and Technology, Japan, 20)Fukui University, Japan, 21)Tokyo Institute of Technology, Japan, 22)Hiroshima Insitute of Technology, Japan, 23)Shizuoka University, Japan, 26)Mie University, Japan, 27)Kyushu Tokai University, Japan, 28)Yamaguchi University, Japan, 29)Hiroshima University, Japan, 30)Central Research Institute of Electric Power Industry, Japan, 33)Shinshu University, Japan, 35)Kanazawa University, Japan
0 1
Saf
ety
fac
tor
r/a
Strong p(r) and q(r) linkage among physics with various time scales
Transport
MHD stability
Current diffusion
Bootstrap current Plasma Wall Interaction
HeatingRotation controlCurrent driveFuelling
JT-60U objectives and strategy
ITER Physics R&D Advanced Tokamak (AT) Concepts for ITER & DEMO
AT plasmas : high N & high bootstrap current fraction (fBS) high p mode plasma
JT-60U
0 1
Pre
ssu
re
ITB
weakstrong
r/a
ETB
reversed shear (RS) plasma
Sustainment of high N below no wall ideal limit and high fBS longer than the current diffusion time.
High N exceeding no wall ideal limit. Integrated performance in the long high N discharges. Development of real time control systems towards intelligent control
for the high fBS plasmas.
'05-'06
'03-'04Main topics
Schematic view of research area in N-fBS spaceJT-60U
Ferritic Steel Tiles (FSTs) are installed inside the vacuum vessel to reduce toroidal field ripple.
Decrease in fast ion loss with the large volume configuration close to the wall, where wall stabilization effectively works.
N
DEMO
JT-60SA
ITER-SS
ITER-Hybrid
ITER-Inductive
NTM
RWM
fBS
p(r) & q(r) linkage
No wall limit
Ideal wall limit
High N exceeding no wall limit
– Wall stabilization effect– Suppression of resistive wall mode
(RWM) by plasma rotation
Integrated performance– Confinement improvement– Robustness for current profile diffusion– Effect of plasma wall interaction
Real-time control systems– Pressure profile control– Real-time current profile control
0
1
2
3
4
5
0 20 40 60 80 100
Contents
1. Installation of ferritic steel tiles and its effects in L- and H-mode plasmas
2. Extension of operation regime to high N exceeding no wall ideal limit and RWM study
3. Integration of plasma performance in the long high N discharges
4. Development of real time control with high bootstrap current fraction
5. Physics studies on issues implicated for ITER
6. Summary
JT-60U
1. Installation of ferritic steel tiles and its effects in L- and H-mode plasmas.
FSTs cover ~10% of the surface.
Large effect is obtained at BT < ~2 T.
3-D Monte-Carlo simulations (F3D OFMC) for fast ion behavior indicated that total NB absorbed power is increased by 30% (by 50% for perpendicular NB) in the large volume configuration.
K. Shinohara (FT/P5-32, Thu.)
FSTs
0.0
20.0
40.0
60.0
80.0
100.0
total perp. co ctr co
w/o FSTs w FSTs
Abs
orbe
d po
wer
(%
)
P-NB N-NB
Ip = 1.1 MA, BT = 1.86 T, VP = 79 m3
quasi-ripple well region
w FSTs
w/o FSTs
JT-60U
The present
Spin-up of toroidal rotation in co-direction due to
reduction of fast ion loss.
Ripple trapped loss
F3D OFMC calculation< 0.3 MW/m2 w FSTs > 1 MW/m2 w/o FSTs
< 0.2 MW/m2
Heat flux in the ripple trapped loss region measured with IRTV is consistent with that calculated by F3D OFMC.
Toroidal rotation shifts to co-direction due to the reduction of the fast ion loss.
K. Shinohara (FT/P5-32, Thu.) M. Yoshida (EX/P3-22, Wed.)
JT-60U
Ip = 1.2 MA, BT = 2.6 T, q95 = 4.1, Vp = 75 m3, L-mode
-50
0
50
100
150
0 0.2 0.4 0.6 0.8 1
VT (
km/s
)
r/a
w/o FSTs
w FSTs
1u perp. & 2u co-NB
w FSTs
w FSTs
w/o FSTs
Pedestal parameters and confinement are enhanced with co-rotation in H-mode.
Ip = 1.2 MA, BT = 2.6 T, q95 = 4.1, Vp = 75 m3
Pedestal pressure increases with the increase in toroidal rotation at the pedestal in co-direction.
Energy confinement is improved by enhancing core toroidal rotation in co-direction.
Pedestal pressure and confinement are raised with FSTs even at a given toroidal rotation.
H. Urano (EX/5-1, Thu.)
0.7
0.8
0.9
1
1.1
-300 -200 -100 0 100 200
HH
98(y
,2)
VT(r/a=0.2) (km/s)
2
4
5
6
7
-100 -50 0 50VT
ped (km/s)
P p
ed (
kPa)
JT-60U
3
ctr-
bal-co-NB
w FSTs
w/o FSTsctr- bal-co-NB
ctr-
bal-
co-NBw FSTs
w/o FSTsctr-
bal-co-
2. Extension of operation regime to High N exceeding no wall ideal limit and RWM study
• Suppression of RWM by plasma rotation is a key.• Estimation of critical rotation velocity for suppressing RWM is i
mportant.
N
DEMO
JT-60SA
ITER-SS
ITER-Hybrid
ITER-Inductive
NTM
RWM
fBS
p(r) & q(r) linkage
No wall limit
Ideal wall limit
0
1
2
3
4
5
0 20 40 60 80 100
0
1
2
3
4
5
0.8 0.9 1 1.1 1.2 1.3 1.4
N reaches ideal wall limit.
M. Takechi (EX/7-1Rb, Fri.)
High p ELMy H-mode plasma : BT=1.58 T, Ip=0.9 MA, 0~20 cm (d/a=1.2) Increase in net heating power due to the FSTs installation allows to acces
s high N up to 4.2 with li=0.8-1. n=1 mode at high beta region. Growth time of 1/~1 ms (< w~10 ms) before collapse. RWM is suppressed by plasma rotation (100km/s at r/a=0.3).
li
N
Vp>70 m3N=5xliN=4xli N=3xli
JT-60U
ideal wall limit
no wall limit
1/~1ms
w FSTs
w/o FSTsafter 20th IAEA
before 20th IAEA
-0.01
0
0.01
6.5 6.55 6.6 6.65 6.7Time (s)
3
3.5
4
-0.01
0
0.01
6.64 6.645 6.65 6.655 6.66Time (s)
NB
(a.
u.)
~B
(a.
u.)
~
li~0.9E045480
05
1015
5.5 6 6.5 7Time(s)
0
5
0
5
05
10152025
-100
-50
02
2.5
3
Small critical rotation velocity of VC/VA~0.3% is found at q95=3.5 for suppressing RWM.
JT-60U Less counter rotation due to the FSTs installation enables to change the r
otation in co-direction close to zero.
N
VT
(km
/s)
B (
G)
~P
NB
ctr
(MW
)P
NB
co
(MW
)P
NB
perp
(MW
)
ctr
co
M. Takechi (EX/7-1Rb, Fri.)
no wall ideal limit
VC~15 km/s Growth time of 1/~10 ms (~ W) No increase in VC for higher C. Large impact on ITER & DEMO.
no wall limit
( N
- N
no_w
all )
(N
idea
l_w
all -
Nno
_wal
l )C
=
at q=2
E046710E046743
G. Matsunaga (EPS 2006)
-0.2
0
0.2
0.4
0.6
0.8
1
-100 -50 0 50V
T (km/s)
ideal wall limit
switch from ctr- to co-NB
3. Integration of plasma performance in the long high N discharges.
• Confinement improvement is a key.• Robustness for current profile diffusion should be demonstrated.• Change of wall pumping with a long time scale is important issue.
N
DEMO
JT-60SA
ITER-SS
ITER-Hybrid
ITER-Inductive
NTM
RWM
fBS
p(r) & q(r) linkage
No wall limit
Ideal wall limit
0
1
2
3
4
5
0 20 40 60 80 100
High NHH98(y,2)=2.2 is sustained for 23.1 s (~12R) with f
BS=36-45% at q95~3.3.
• High p ELMy H-mode plasmas : Ip = 0.9 MA, BT = 1.6 T, Vp = 67 m3
• Increase in net heating power due to the FSTs installation allows flexible combination of NB units. peaked heating profile and co-injection.
• Density increase degrades confinement in the latter phase.
N. Oyama (EX/1-3, Mon.)
0 5 10 15 20 25 30 35Time (s)
0
3
12
1
0.5
0
0123
151050
4
2
0
I p (
MA
) N
, H
H98
(y,2
)
n e(1
019 m
-3)
PN
BI (
MW
)I D
(
a.u.
)
N
HH98(y,2)
JT-60U
R=0<>a2/12 : D.R. Mikkelsen, Phys. Fluids B 1 (1989) 333.
ITERBaseline
ITERHybrid
N H
H98
(y,2
) after 20th IAEAw FSTs
before 20th IAEA, w/o FSTs
.
1
1.5
2
2.5
3
0 5 10 15 20 25 30 35Sustained duration (s)
r/a
0
10
20
30
40
50
0
1
2
3
4
5
-60
-40
-20
0
20
4060
0 0.2 0.4 0.6 0.8 1
Pth (
kPa)
q
VT (
km/s
)
w FSTs
w FSTs
w/o FSTs
w/o FSTs
ITER-SS(I)ITER-hybrid (A C C Sips, et al., PPCF 47 (2005) A19.)w FSTs (45436@18s)w/o FSTs (44092@15s)
HH98(y,2)N
fBS
fCD
Fuel purity
Prad/Pheat
ne/nGW
0.56
0.83
1.32.56
0.5
1
0.77
Density is successfully controlled by divertor pumping in enhanced recycling region.
H. Kubo (EX/P4-11, Thu.)
1018 1019 1020
1020
1021
1022
Fuelling ofPNB~10 MW
Div
erto
r p
um
pin
g (
/s)
IDdiv (a.u.)
=0.3
=0.24
JT-60U
0 0
0
Wd
ia
(MJ)
ne
(1019
m-3)
PN
B
(MW
)
0
2
0
10
-0.5
(1022
s-1) 0
(1
022 s
-1)
I D
(1021
s-1)
1
4
200400
600
0 5 10 15 20 25 30Time (s)
T (
°C)
Divertor-plate temperature
NBIDivGas
E045334
Wall-pumping rate
4
1.5
2.5
800
8
20
The outgas could be attributed to increase in divertor plate temperature.
HH98(y,2) ~ 0.71 at 0.64nGW. High confinement at high density
is remaining issue.
Ip = 1.2 MA, BT = 2.2 T, q95 = 3.6
wall pumping
Divertor pumping depends o
n recycling.
4. Development of real time control with high bootstrap current fraction
Understanding of p(r) and q(r) linkage. Current profile control is important for AT plasmas.
p(r) q(r)
V(r)
MSELH
Fast-CXRSco- & ctr-NB
Fast-CXRSECEOn & off-axis NB
detector
actuator
N
DEMO
JT-60SA
ITER-SS
ITER-Hybrid
ITER-Inductive
NTM
RWM
fBS
p(r) & q(r) linkage
No wall limit
Ideal wall limit
0
1
2
3
4
5
0 20 40 60 80 100
6.8 s7.6 s
High fBS of 70% is sustained for 8 s by p(r) control at q
min= 4 with real time qmin estimation.
Y. Sakamoto (EX/P1-10, Tue.)
00.20.40.60.8
-0.500.51
I p (
MA
)
Vlo
op (
V)
00.5
11.5
051015
02468
10
0246810
0123
0
5
1
4 6 8 10 12 14Time (s)
PN
B (
MW
)T
e (
keV
)I D
(
a.u.
)
NT
i (ke
V)
n e(1
019 m
-3)
JT-60U
ctr-NB
q min
345
2
4
6
8
10
12
0 0.2 0.4 0.6 0.8 1
6.8 s8.3 s
q
r/a
02468
-500
50100150
0.4 0.6 0.8r/a
Ti (
keV
)V
T (
km/s
)
qmin=4
Wdia control by NB
RS plasma : q95~8.5, HH98(y,2)~1.8, N~1.4. Ctr-NB off for p(r) control at qmin=4 for 1.0s.
j(r) approaches SS, while, ne(r) still evolves for >
p*(~2s) and plasma collapses.p(r) control is important even with nearly SS j
(r) and qmin being not integer.
MSE
co- & ctr-NB
2
4
6
8
10
1208.3s09.3s10.3s11.3s12.3s13.3s
-0.1-0.05
00.05
0.10.15
5.8 - 6.8 s8.3 - 10.3 s11.8 - 13.3 s
0
1
2
3
4
5
0 0.2 0.4 0.6 0.8 1
t=10.3 st=13.3 s
r/a
E045903
Real time qmin control demonstrated with MSE diagnostics and LHCD at fBS=0.46.
• Reduction of fast ion loss due to the FSTs installation increases compatibility of LHCD with high power heating.
• qmin control is affected by dynamic behavior related to the strong linkage of p(r) and q(r).
T. Suzuki (EX/6-4, Thu.)
JT-60U
qMSE qmin qmin,ref
PLH
LHMSE
Real time qmin control scheme
0
10
20
0
0.8
1.6
0
0.5
1.0
1.5
1
1.5
2
7 8 9 10 11 12 13 14 15Time (s)
q min
PLH
(M
W)
PN
B (
MW
)
N
ref.
command
02468
Te
(keV
)
MSELH
Transport reduction at t=12.4 s
Time delay in response of qmin
jOH or jBS change
r/a~0.20.4
0.6
Control for bootstrap sustained plasma (fBS~100%) is challenging.
Y. Takase (EX/1-4, Mon.)
Bootstrap sustained plasma can reduce center solenoid (CS) coil capability, which has a large impact on the economic aspect.
Nearly constant current (~0.54 MA) is maintained by BS current with constant ICS and negative NBCD current for ~1 second.
Both Wdia and Ip gradually decrease in the strong linkage even with constant Wdia control.
0.6
01.5
04.5
020
01
03 4 5 6Time (s)
5
-525
04
0-2
-46
0V
loop
(V)
PN
B
(MW
) p
I CS
(kA
)S
n
(1014
s-1)
I p (
MA
)W
dia
(MJ)
N
n e(1
019 m
-3)
I VT, I
VR
(kA
)I D
(a.u
.)
N
Wdia
IVT
IVR
E046687
JT-60U
BT = 4 T, N=1.15ICS constantWdia constant FB
5. Physics studies on issues implicated for ITER.
NTM suppression by ECCDJEC/JBS
Dependence of EC deposition positionModeling
• Behavior of energetic ions with Alfvén eigenmodesNeutron emission profile measurementsComparison with classical calculation
• ELM propagation in SOL plasmaMeasurements with multi reciprocating probes (LFS and HFS)
JT-60U
2/1 NTM is suppressed at JEC=0.5JBS with well aligned ECCD to q=2 surface.
• 2/1 NTM is destabilized with the misalignment comparable to the island width.
• TOPICS simulation well reproduces the experimental results with the same set of coefficients of the modified Rutherford equation.
A. Isayama (EX/4-1Ra, Thu.)
EC
0
1
2
3
B (
a.u
.)~
EC0
1
2
3
EC
139 10 11 12time [s]
0
1
2
3
B (
a.u
.)~
B (
a.u
.)~
EC=0.62
EC=0.60
EC=0.44
JT-60U
0.5Wisland<<Wisland
~0.5Wisland
>Wisland
(A)
(B)
(C)
(A)
(B)(C)
=|EC-island-center|
Energetic ions are transported from core region due to AEs with moderate amplitude.
JT-60U
• Understanding of the alpha particle transport in the presence of AEs is one of the urgent research issues for ITER.
M. Ishikawa (EX/6-2, Thu.)
(A) with AEs (t=6.4s) (B) with weak AEs (t=7.8s)
The measured neutron yield is significantly smaller than the classical calculation during AEs with moderate amplitude in the central region.
Neutron measurements
0
2
4
6
8
10
5 5.5 6 6.5 7 7.5 8
time (s)
-- r/a ~ 0.19
-- r/a ~ 0.32
-- r/a ~ 0.46
-- r/a ~ 0.56
-- r/a ~ 0.73
-- r/a ~ 0.84
NNB NNB
20
40
60
80
100
(A) (B)
0
2
4
6
8
10 MeasurementTOPICS
0 0.2 0.4 0.6 0.8 1
r/a
02468
101214 Measurement
TOPICS
0 0.2 0.4 0.6 0.8 1
r/a
Non-diffusive ELM propagation is observed in LFS SOL, but not in HFS SOL.
N. Asakura (EX/9-2, Fri.)
-0.5
0
0.5
0123
0 0.1 0.2 0.3time (ms)
0.4
-0.5
0
0.5
0246rmid=1.0cm
R (m) 2 3 4
-1
0
Z (m)
SOL
SOL
Midplane Mach probe
X-point Mach probeHigh-field-side Mach probe
Target probe array (18 probes)
23cm
Probes and fast TV in JT-60U
rmid=0.8cm
HFS
LFS
JT-60U• Transient heat and particle load to the plasma facin
g components (PFC) is a crucial issue.• Vperp
mid(peak)=0.4-1.2 km/s (rmid<5 cm), 1.5-3 km/s (rmid>6 cm)
j sHF
S
(105
Am
-2)
B (
a.u.
)j sLF
S
(105
Am
-2)
B (
a.u.
)LFS
HFS
mid (peak)=25sperp
LFS
~LCHFS/Cs
~convection time scale
ELM crash
6. Summary
The installation of FSTs enables to access new regimes.
• High N exceeding no wall ideal limitN~4.2 (=ideal wall limit)Small critical rotation of VC/VA=0.3% and no increase of critical rotation velocity in high C regime for suppressing RWM
High N in ITER and DEMO
• Long sustainment of integrated performanceNHH98(y,2)=2.2 for 23.1 s (~12R) with fBS=36-45%
ITER hybrid scenario
Development of real time control methods for pressure profile control and current profile control.
intelligent control for the high fBS plasmas in DEMO
• Progress in physics studies implicated for ITER.NTM suppression, Energetic ions with AEs and ELM.
• JT-60SA (super advanced) design is optimized to support and supplement ITER toward DEMO. (M. Kikuchi, FT2-5, Fri.)
JT-60U
Presentations from JT-60U
Mon. Long high N dischargesBootstrap sustained discharges
Tue. ITB study in high p mode plasmasHigh bootstrap discharges
Wed. FSTs effects on rotation & momentum transport
Thu. NTM suppression by ECCDFSTs effects on pedestal and confinementEnergetic ions with AEsCurrent profile control & off-axis current driveParticle control under wall saturationHydrogen retention and carbon deposition Radiation processes of impurities and hydrogenITB study in RS plasmas Installation of FSTs
Fri. High N and RWM studyELM propagation and fluctuation in SOLSpontaneously excited waves near ICRF
Sat. High density limit with high liNTM suppression by ECCDHigh N and RWM study
JT-60UN. Oyama (EX/1-3)Y. Takase (EX/1-4)
S. Ide (EX/P1-5)Y. Sakamoto (EX/P1-10)
M. Yoshida (EX/P3-22)
A. Isayama (EX/4-1Ra)H. Urano (EX/5-1)M. Ishikawa (EX/6-2)T. Suzuki (EX/6-4)H. Kubo (EX/P4-11)K. Masaki (EX/P4-14)T. Nakano (EX/P4-19)K. Ida (EX/P4-39)K. Shinohara (FT/P5-32)
M. Takechi (EX/7-1Rb)N. Asakura (EX/9-2)M. Ichimura (EX/P6-7)
H. Yamada (EX/P8-8)A. Isayama (EX/4-1Ra, P)M. Takechi (EX/7-1Rb, P)
