TOKAMAK RESEARCH IN IOFFE INSTITUTE

27th IAEA Fusion Energy Conference (FEC 2018)

Gandhinagar, India 22 – 27 October 2018

TOKAMAK RESEARCH

IN

IOFFE INSTITUTE

N.N. Bakharev et al.

List of contributors

2/24

N.N. BAKHAREV, G.I. ABDULLINA, V.I. AFANASIEV, A.B. ALTUKHOV, L.G. ASKINAZI, N.A. BABINOV, A.N. BAZHENOV, A.A. BELOKUROV, I.M.

BUKREEV, F.V. CHERNYSHEV, I.N. CHUGUNOV, D.N. DOINIKOV, V.V. DYACHENKO, L.A. ESIPOV, D.B. GIN, A.D. GURCHENKO, E.Z. GUSAKOV,

V.K. GUSEV, M.V. ILIASOVA, M.A. IRZAK, A.N. KONOVALOV, E.M. KHILKEVITCH, S.A. KHITROV, N.A. KHROMOV, E.O. KISELEV, V.A. KORNEV,

A.N. KOVAL, D.V. KOUPRIENKO, S.V. KRIKUNOV, O.L. KRUTKIN, G.S. KURSKIEV, S.I. LASHKUL, S.V. LEBEDEV, A.D. MELNIK, V.B. MINAEV, I.V.

MIROSHNIKOV, E.E. MUKHIN, V.O. NAIDENOVA, A.N. NOVOKHATSKII, A.S. NAVOLOTSKY, K.YU. OSHUEV, M.I. PATROV, M.P. PETROV, S.Ya

PETROV, YU.V. PETROV, I.A. POLYNOVSKY, A.YU. POPOV, A.G. RAZDOBARIN, D.V. RAZUMENKO, V.V. ROZHDESTVENSKY, N.V. SAKHAROV,

D.S.SAMSONOV, A.N. SAVELIEV, P.B. SHCHEGOLEV, A.E. SHEVELEV, A.D. SLADKOMEDOVA, A.I. SMIRNOV, V.V. SOLOKHA, V.A. SOLOVEI, A.YU.

TELNOVA, V.A. TOKAREV, S.YU. TOLSTYAKOV, P.V. TRETINNIKOV, A.S. TUKACHINSKY, V.I. VARFOLOMEEV, N.A. ZHUBR

Ioffe Institute

St.-Petersburg, Russia

Email: [email protected]

C. LECHTE

Institute of Interfacial Process Eng.

and Plasma Technology

70569 Stuttgart, Germany

E.G. ZHILIN

Ioffe Fusion Technology Ltd.


S. HEURAUX

Institute Jean Lamour UMR 7198

CNRS, Université de Lorraine

54000 Nancy, France

M.D. BLEHSHTEIN, V.V. BULANIN, A.V. PETROV, A.YU.

YASHIN

Peter the Great St. Petersburg Polytechnic University


E.N. BONDARCHUK, S.N. KAMENSHIKOV, A.A. KAVIN,

K.M. LOBANOV, A.B. MINEEV

JSC «NIIEFA»,


V.I. DAVYDENKO, A.A. IVANOV, V.V. KOLMOGOROV,

I.V. SHIKHOVTSEV

BINP SB RAS

Novosibirsk, Russia

A.V. GORBUNOV

NRC Kurchatov Institute

Moscow, Russia

AL.P. CHERNAKOV

JSC «Spectral-Tech»,


S.P. PANDYA, S.N. PANDYA

Institute for Plasma Research

Gandhinagar, 382-428, India

T.P. KIVINIEMI, S. LEERINK, P. NISKALA

Aalto University

Espoo, Finland

Outline

• Introduction

• Globus-M • Energy confinement

• Alfven eigenmodes

• Discharge disruptions

• SOL study

• FT-2: benchmarking of the full-f gyrokinetic modeling against DR using synthetic

diagnostics

• TUMAN-3M • L-H transition induced by GAMs and pellet injection

• ICE in NBI-heated plasma

• ICE in OH plasma

• Alfven eigenmodes in OH plasma

• Theory group: anomalous absorption and emission in ECRH experiments

• ITER diagnostics development • NPA and GRS

• DTS and LIF

• Globus-M2 first plasma

• Summary

3/24

Introduction

• In 2018, Ioffe Institute celebrates its 100th anniversary.

• Fusion research in Ioffe Institute has been going on for more than 60 years.

• At present – theory group, ITER group, 3 tokamaks:

Globus-M2 FT-2 TUMAN-3M

R [cm]/a [cm] 36/24 = 1.5 55/8 = 6.8 53/22 = 2.4

BT [T] / Ip [kA] 1 / 500 3 / 40 1 / 180

4/24

Globus-M

parameter value

R [cm]/a [cm] 36/24 = 1.5

k 2.0

δ 0.5

BT, T 0.5

Ip , kA 250

t pulse , ms 130

PNBI [MW] 1

1999 – 2017

BT: 0.4 T → 0.5 T

Ip: 200 kA → 250 kA

Last experimental campaign:

[Bakharev N.N. et al. Nucl. Fusion 2018 accepted manuscript] 5/24

Globus-M: Energy confinement

0 1 2 3 40

1

2

3

4

WG

LB,

kJ

Wexp

, kJ

τEGLB~Ip

0.51±0.26 BT

1.2±0.1Pabs-0.54±0.26ne

0.67±0.04

MAST: τE~Ip0.59BT

1.4 NSTX: τE~Ip0.57BT

1.08 IPB98(y,2): τE~Ip0.93BT

0.15Pabs-0.69ne

0.4

0,0 0,1 0,2 0,3 0,40,0

0,5

1,0

1,5

2,0

BT

E~

*

-0.4

BT E

, T

ms

*

• Energy confinement time strongly depends on toroidal magnetic field.

• Normalized energy confinement time exhibits moderate dependence on collisionality.

• Ion heat transport is close to neoclassical level. Anomalous contribution is observed at low collisionality.

NSTX BTτE~ν* -0.79

MAST BTτE~ν *-0.82

EX/P5-2 (Thursday), Kurskiev G.S. et al [G.S. Kurskiev et al. PPCF 59 (2017)] 6/24

0.01 0.10.00

0.25

0.50

0.75

1.00

TC

XR

S

i0/T

ne

o

i0

Globus-M: TAE

[BULANIN V., et al. Tech. Phys. Lett. 43 12 (2017) 1067] [GUSEV V. et al. Tech. Phys. Lett. 44 1 (2018) 67]

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.70

10

20

30

40

50

60

70

80

180 kA

240 kA

B, 10-3T

drop of 28.5 keV CX neutral flux, %

137 138 139 140 141200

400

600

800

56

84

112

140

-3.0

-1.5

0.0

1.5

3.0

1.4

1.5

1.6

1.7137 138 139 140 141

NPA flux, E=27 keV (a.u.)

t, ms

neutron rate (a.u.)

MHD signal (a.u.)

<ne> (10

19*m

-3)

180 kA, 0.4T 240 kA, 0.5 T

• Modes became more frequent due to better fast ion (FI) accumulation

because of the better classical FI confinement and lower TAE-induced

losses.

1.0

1.5

2.0

2.5

145 146 147 148 149 150

-3.0

-1.5

0.0

1.5

3.0

145 146 147 148 149 150200

400

600

800

<ne> (10

13*cm

-3)

MHD signal (a.u.)

t, ms

NPA f lux, E= 26 keV (a.u.)

TAE-induced Fast Ion losses

• BT increase also resulted in FI

losses decrease, but this effect

was much weaker

7/24

Globus-M: TAE

[BULANIN V., et al. Tech. Phys. Lett. 43 12 (2017) 1067] [GUSEV V. et al. Tech. Phys. Lett. 44 1 (2018) 67]

-3

0

3

0,4

0,6

0,8

0,4

0,6

0,8

0,4

0,6

0,8

0

100

200

f, k

Hz

f, k

Hz

f, k

Hz

t, ms

f, k

Hz

MP

#36645

0,020000,040000,080000,1600

a

b

c

d

e

f

0

100

200

, a.u

., a.u

., a.u

.

DBS, 48 GHz

0

100

200

DBS, 39 GHz

140 142 144 146 148 150

0

100

200

DBS, 29 GHz

0,0

1,0

2,0

ne, 10

19 m

-3

Ip = 250 kA

Btor

= 0.5 T

MP

, a.u

.

0.2 0.4 0.6-0.4

-0.3

-0.2

-0.1

0

0.1

0.2

0.3

0.4

2/

A

2=0.1307

toroidal mode number n=1

𝐄𝐱𝐩𝐞𝐫𝐢𝐦𝐞𝐧𝐭: 𝝆 = 𝟎. 𝟒𝟓 − 𝟎. 𝟖𝟓

36 40 44 48 52 56 60

0

4

8

12

16

20

t = 141.2 ms

n=1

n=2

~B

[

gau

ss]

R [cm]

#37001 n=1

n=2

0

2

4

6

LCFS

q

q

𝐊𝐈𝐍𝐗 + 𝐊𝐀𝐗𝐄 𝐦𝐨𝐝𝐞𝐥𝐢𝐧𝐠: 𝝆 = 𝟎. 𝟒 − 𝟎. 𝟗

52 56 60 64 68 720.6

0.9

1.2

1.5

1.8

2.1

r = 18 cm

r = 0 cm

f, M

Hz

t, ms

kII=1.74 m-1

L -

H t

ran

sit

ion

r = 22 cm

TAE localization by DBS :

8/24

Z, m

R, m

Comparison of the experimental and calculated TAE localization

TUMAN-3M: OH GAE

9/24

Globus-M: disruption study

• tCQ ~ Ip like in NSTX, but not in IDDB

• Linear dependence, almost no difference for H and D

0

2

4

6

8

0 0,4 0,8 1,2

t CQ/(SL)

( m

s/m

2)

Ip/S (MA/m2)

ITERmin:

tCQ/SL ≥ 1.67 ms/m2

IDDB: tCQ/SL : 1,7-10 ms/m2

Globus-M

[SAKHAROV, N. et al, Plasma Phys. Rep. 43 (2017) 422] [SAKHAROV, N., GUSEV V., KAVIN A. et al, Plasma Phys. Rep., 44 (2018) 335]

17 kPa << Patm

IDDB: tCQ = (t20-t80)/0.6

[ABDULLINA G. et al. Tech. Phys. Lett. 44 (2018) 108]

10/24

Globus-M: SOL width

New adjustable 9-pin probe was installed at LFS midplane.

Typical Globus-M Te and ne profiles

λq ~ Ip-1.2BT

0.6 λq ~Ip-1.1BT

0.42

[Tokarev V.A. et al J. of Phys.: Conf. Series 1094 (2018) 012003]

[Eich 2011] scaling: [Eich 2013] scaling:

Globus-M database fitting: λq ~Ip-0.9

0 5 10 15 20 25 300

5

10

15

20

25

30

35

40

45

50

BT=0.4 T

BT=0.5 T42 eV

47 eV

Separatrix

Te (

eV

)

R-Rsep (mm)

0 5 10 15 20 25 300.0

0.5

1.0

1.5

2.0

2.5

3.0

3.5

4.0

4.5

BT=0.4 T

BT=0.5 T

1.9×1018 m-3

4.1×1018 m-3

Separatrix

ne (

10

18 m

-3)

R-Rsep (mm) 0 2 4 6 8 100

2

4

6

8

10

12 JET

AUG

C-Mod

MAST

NSTX

D3D

Globus-M

q Eich-2013 (mm)

q E

xp

eri

me

nta

l (m

m)

λq scaling fitting

Good agreement with both EICH scalings is observed:


11/24

FT-2 tokamak

High field high aspect ratio tokamak.

parameter value

R [cm]/a

[cm]

55/8= 6.8

BT, T 3

Ip , kA 40

qa 3 - 6

PLHH [kW] 180

12/24

COMPREHENSIVE BENCHMARKING OF FULL-F GLOBAL GK MODELING

AGAINST THE FT-2 TOKAMAK DOPPLER REFLECTOMETRY DATA

TH/8-2 (Friday-poster, Saturday-oral) A. B. Altukhov et al.

HFS X-mode DR experimental data VS ELMFIRE code modeling via fast linear synthetic diagnostic version based on the reciprocity theorem full-wave synthetic diagnostic version utilizing the IPF-FD3D code

• Good agreement between the measured and computed DR frequency spectra (the spectra frequency shift, width and form for all incidence angles). The mean fluctuation velocity and GAM characteristics were close thus indicating correct description of the global electric field dynamics by the code.

-800 -400 0 400 8000.0

0.2

0.4

0.6

0.8

1.0

f (kHz)

P (

no

rm.

un

.)

experiment

FS DR

FWS DR

-4 -3 -2 -1 0 1 2 3 40.0

0.2

0.4

0.6

0.8

1.0

synth.with phase

measur.

Co

her

ence

f (GHz)

synth.

full wave

-20 -10 0 10 200.00.10.20.30.40.50.60.70.80.91.01.1 -10 -5 0 5 10

(cm

-1)

ya (mm)

Ps (

no

rm.u

n.)

experiment

FS DR

FWS DR

• The variation of the DR signal at growing incidence angles in experiment is slower than predicted by both synthetic diagnostics because of the overestimation of the turbulence poloidal wavenumber spectrum decay rate with growing wavenumber due to incorrect modelling in the small-scale (ETG-mode) domain.

• The experimental radial correlation DR data is in agreement with full-wave synthetic diagnostic prediction thus indicating correct description of the turbulence radial wavenumber spectra. Substantial difference found for the fast synthetic diagnostic is related to the large contribution of long scale fluctuation, which is suppressed in experiment by the probing wave phase modulation (transition to the nonlinear regime of DR operation).

13/24

Compact tokamak TUMAN-3M

parameter value

R [cm]/a [cm] 53/22 = 2.4

BT, T 1

Ip , kA 180

t pulse , ms 80

PNBI [MW] 1

Compact conventional tokamak.

14/24

TUMAN-3M and FT-2: modeling of the GAM-triggered L-H transition

[L.G. Askinazi et al 2017 Plasma Phys. Control. Fusion 59 014037]

GAM-initiated LH-transition

0 20 40 60 80 100 120 1400

5

10

15

20

25

Is

FT-2 (DEUTERIUM) r = 4.5 cm

grad n - L-mode

grad n, 1019 m-4

, 10

19 m

-2s

-1

0 2 4 6 8 100

2

4

6

8

10

12

14

H-mode

GAM

L-mode

L-mode

r = 21.5 cm

t, ms

EOSC

= 4.5 kV/m

EOSC

= 5.5 kV/m

dn

/dr,

10

19 m

-4

• Observed at TUMAN-3M.

• Not observed at FT-2 for similar conditions.

Thresholds on GAM amplitude and duration exist.

15/24

TUMAN-3M: modeling of pellet-triggered L-H transition

[T.P. Kiviniemi et al 2018 Plasma Phys. Control. Fusion 60 085010] [A.A. Belokurov et al 2018 Nucl. Fusion 58 112007]

-1.0 -0.5 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5

0

20

40

60

0

20

40

60

80

0

1

2

3

4

5

gra

d n

, 1

01

9m

-4

t, ms

Sin

t, 1

01

9 m

-2s

-1

Gas puff

Pellet

0.21 m

D, m

2s

-1

Pellet injection

• Sufficient Er-shear and high particle source is needed for GAM- and pellet- H-mode triggering.

• If particle source is too low, self-sustaining H-mode is not possible for certain scenario.

The LH-transition occurred if the pellet evaporation

was peripheral.

0 10 20 30 40 500

5

10

15

20

25

30

35

40

grad n - L-mode

,

10

19 m

-2s

-1

grad n, 1019 m-4

IS - with pellet gas cloud

IS - before pellet

r/a = 0.96


16/24

TUMAN-3M: Ion Cyclotron Emission during NBI heating

[ASKINAZI, L. et al, Nucl. Fus. 58 (2018) 082003]

• NBI Ion Cyclotron Emission (ICE) frequency corresponds to the central IC resonance for minority ions.

• Comes from core plasma region. • ICE frequency depends on Btor but not on ne. • Fine structure, oscillating with sawtooth.

• CAE instability excited by stagnating fast ions:

• w = lwci + k||vb

• Beam with E0, E0/2, E0/3, 2E0/3 -> fine structure

• Sawtooth may induce redistribution of fast ions


17/24

TUMAN-3M: Ohmic Ion Cyclotron Emission

• Not caused by suprathermal ions.

• Spectrum typically consisted of 8-9 harmonics with frequencies

evolving with BT.

• Detected in H and D plasmas both in LFS and HFS.

• OICE fundamental depends on the probe position; it corresponds to

the ion-cyclotron resonance frequency of the main plasma ions in

the close vicinity of the corresponding magnetic probe.

• Could be understood in frames of the Ion Cyclotron Drift Instability

proposed by Mikhailovsky & Timofeev and based on ICE excitation

in inhomogeneous plasma: 𝝆𝒊 𝒂 ≥ 𝟐 𝒎𝒆 𝒎𝒊 𝟏 𝟐 , 𝐚 =𝟏

𝒏

𝒅𝒏

𝒅𝒓

−𝟏

Spectra of OH ICE, measured by the two

magnetic probes: LFS and HFS in H and D

plasmas.

18/24

ANOMALOUS ABSORPTION AND EMISSION IN ECRH EXPERIMENTS

DUE TO PARAMETRIC EXCITATION OF LOCALIZED UH WAVES

TH/P4-10 (Wednesday) E. Z. Gusakov et al.

18/24

A possibility of two-UH-plasmon parametric decay

instability excitation in X2 ECRH experiments in fusion

devices with non-monotonous density profile is

demonstrated in a wide plasma density range .

The instability leading to generation of the trapped UH

wave is excited at the pump power of about 100 kW.

Well above the threshold it is leading to anomalous

absorption rate of more than 10%.

The plasma microwave emission at the pump half

frequency ω0/2 and at the frequency 3ω0/2 is predicted

at the level of 50 W.

19/24

Neutral Particle Analyzer for ITER

Recent progress in the NPA developing. 3D design.

[Mironov M. et al., Nucl. Fusion 58 (2018) 082030]


20/24

ITER Gamma Ray Spectrometer

FIP/P7-15 D. (Friday) B. Gin et al.

• Detectors of the GRS and NS are located in the Neutron Dump of the NPA.

• 3D-model of the ND support and alignment system has been developed.

• Electromotors, solenoids and position switches of the GRS and NS positioners have been successfully tested under the integral neutron flux of 1013 n/cm2.

GRS positioner

NS positioner

NS el. motor

GRS el. motor

NPA neutron dump

ND support and alignment system

20/24

21/24

ITER Divertor Thomson scattering/Laser-induced Fluorescence

[GORBUNOV A., Fus. Eng. and Design 123 (2017) 695] [MUKHIN E.et al., Fus. Eng. and Design 123 (2017) 686] [A.Kornev et al SOFT 2018]

[E.Mukhin et al FED 2017]

DTS/LIF equipment situated in ITER Lower Port #8. 1 — Strike point on the outer divertor target; 2 — Laser beams; 3 —

Front and back racks used for arrangement of DTS/LIF in vessel equipment and neutron shield components

FIP/P1-5 (Tuesday) A. G. Razdobarin et al.

Hardware design development:

• Special lasers: Nd:YAG(1064 nm) – main diagnostic laser for ITER DTS

• Prototype of Nd:YAG(946 nm) – for double-wavelengths TS calibration ITER DTS

• Digital Filter Polychromator

Laser equipment

Spectroscopic room

22/24

ITER Divertor Thomson scattering/Laser-induced Fluorescence

FIP/1-5 (Monday) E. E. Mukhin et al.

[A. Gorbunov et al Plasma Fus. Eng. and Design 123 2017 695]

[A. Gorbunov et al, SOFT 2018]

Meeting the requirements in input parameters for divertor plasma modelling

DTS/LIF provides simultaneous measurements of Te, ne, Ti, ni nHe/H/D/T distribution

in ITER divertor SOL providing simulation of

- Ionization balance: Rates of ionization and recombination (Te, ne);

- Emission intensity (Te ne ni nHe/H/D/T);

- Frictional force of the plasma flow due to collisions with neutrals (Ti ni nHe/H/D/T);

- Pressure of the incoming plasma flow (Te ne Ti ni).

A new kind of LIF spectroscopic scheme based on laser induced quenching of the

most intensive hydrogen line Hα = 656.1 nm is proposed.

23/24

Globus-M2

• R [cm]/a [cm]= 36/24 = 1.5

• BT = 1T, Ip = 500 kA

• Diverse diagnostics, heating

and CD systems, including

2xNBI, ICRH, LHCD, plasma gun

• Extreme Pheat /V = 6 MW/m3

First plasma: April 23rd Experimental campaign: end of 2018 FIP/P7-34 (Friday) V. B. Minaev et al.


24/24

Conclusion

• Experiments with increased BT and Ip in Globus-M demonstrated discharge improvement.

• Strong dependence of τE on BT was observed.

• For the first time TAE localization using DBS was measured. It is in a good agreement with modeling.

• tCQ was in a good agreement with IDDB. Almost no dependence on mi and linear dependence on Ip

was observed.

• λq midplane dependence was estimated as ~ Ip-1.2.

• Global full-f GK code benchmarking against DR data demonstrated good agreement in radial electric

field dynamics and turbulence radial correlation properties, but not in poloidal wavenumber spectrum

thus appealing to the multi-scale GK modeling

• The importance of particle source and Er-shear was demonstrated for GAM- and pellet- induced L-H

transition.

• ICE was observed in NBI-heated discharges in TUMAN-3M. The possible explanation is CAE

instability, excited by stagnating fast ions. ICE was also observed in OH plasma.

• More than 10% anomalous absorption of the ECRH power is predicted due to parametric excitation

of a localized UH wave. A measurable level of the plasma microwave emission at harmonics of the

pump wave half-frequency is predicted .

• Considerable progress in ITER NPA, GRS, DTS\LIF development has been made.

• New Globus-M2 spherical tokamak is online.

24/24

Thank you

for your attention!

TOKAMAK RESEARCH IN IOFFE INSTITUTE

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