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Optimizing ion-cyclotron resonance frequency heating for ITER: dedicated JET experiments

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2012 Plasma Phys. Control. Fusion 54 069601

(http://iopscience.iop.org/0741-3335/54/6/069601)

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Plasma Phys. Control. Fusion 54 (2012) 069601 (6pp) doi:10.1088/0741-3335/54/6/069601

Erratum: Optimizing ion-cyclotronresonance frequency heating for ITER:dedicated JET experiments2011 Plasma Phys. Control. Fusion 53 124019

E Lerche1, D Van Eester1, J Ongena1, M-L Mayoral2, M Laxaback3,F Rimini2, A Argouarch4, P Beaumont2, T Blackman2, V Bobkov5,D Brennan2, A Brett2, G Calabro6, M Cecconello7, I Coffey2, L Colas4,A Coyne2, K Crombe8, A Czarnecka9, R Dumont4, F Durodie1, R Felton2,D Frigione6, M Gatu Johnson7, C Giroud2, G Gorini10, M Graham2,C Hellesen7, T Hellsten3, S Huygen1, P Jacquet2, T Johnson3, V Kiptily2,S Knipe2, A Krasilnikov11, P Lamalle12, M Lennholm2, A Loarte12,R Maggiora13, M Maslov14, A Messiaen1, D Milanesio13, I Monakhov2,M Nightingale2, C Noble2, M Nocente10, L Pangioni2, I Proverbio10,C Sozzi10, M Stamp2, W Studholme2, M Tardocchi10, T W Versloot15,V Vdovin16, M Vrancken1, A Whitehurst2, E Wooldridge2, V Zoita17 andJET EFDA Contributors18

JET-EFDA Culham Science Centre, Abingdon, OX14 3DB, UK1 LPP-ERM/KMS, Association Euratom-‘Belgian State’, TEC Partner, Brussels, Belgium2 EURATOM–CCFE Fusion Association, Culham Science Centre, UK3 Fusion Plasma Physics, Association EURATOM–VR, KTH, Stockholm, Sweden4 CEA (IRFM)–EURATOM Association, Saint-Paul-lez-Durance, France5 IPP (MPI)–EURATOM Association, Garching, Germany6 C R Frascati, EURATOM–ENEA sulla Fusione, Frascati, Italy7 Uppsala University, Association EURATOM–VR, Uppsala, Sweden8 Department of Applied Physics, Ghent University, B-9000 Ghent, Belgium9 Institute of Plasma Physics and Laser Microfusion, Warsaw, Poland10 Instituto di Fisica del Plasma, EURATOM-ENEA-CNR Association, Milan, Italy11 SRC RF Troitsk Institute for Innovating and Fusion Research, Troitsk, Russia12 ITER Organization, Saint-Paul-lez-Durance, France13 Politecnico di Torino, EURATOM-ENEA sulla Fusione, Torino, Italy14 CRPP-EPFL, Association EURATOM–Confederation Suisse, CH-1015 Lausanne, Switzerland15 FOM Institute ijnhuizen, Association EURATOM–FOM, Nieuwegein, the Netherlands16 RNC Kurchatov Institute, Nuclear Fusion Institute, Moscow, Russia17 National Institute for Plasma Physics, Association EURATOM–MEdC, Bucharest, Romania

Received 28 March 2012Published 17 May 2012Online at stacks.iop.org/PPCF/54/069601

(Some figures may appear in colour only in the online journal)

The original paper was erroneously published with preliminaryversions of some figures. The final versions of affected figuresare appended below.

18 See the appendix of Romanelli F et al 2010 Proc. 23rd IAEA Fusion EnergyConf. 2010 (Daejeon, Korea).

0741-3335/12/069601+06$33.00 1 © 2012 IOP Publishing Ltd Printed in the UK & the USA

Plasma Phys. Control. Fusion 54 (2012) 069601 Erratum

Transmission Line~

Antenna

Matching circuit

RF GeneratorPlasmaseparatrix

SOL

FW evanescentForward power (VFOR)

Reflected power (VREF)

Rant

PRF

Pabs

ω =

ω

= ω

ci

JG11.88-1c

Figure 1. Chart illustrating the principle of the ICRF heating process.

0

1

2

3

4

5

6

7

8

9

10

PR

F (

MW

)

(a)

10 11 12 13 14 15 160

0.5

1.0

1.5

2.0

2.5

Dα (

a.u)

time (s)

(b)

ILA

C+D

A+B

TOTAL

JPN 78070

JG11

.883

c

Figure 3. ELM resilient operation of the ICRF system in JET: (a)ICRF power coupled by antennas A + B (dotted), antennas C + D(dashed) and by the ILA (solid), (b) Dα-emission illustrating thestrong type-I ELMs in the discharge.

2

Plasma Phys. Control. Fusion 54 (2012) 069601 Erratum

0

1

2

3

4

5

PR

F

(a)

2

4

6

Te0

(ke

V)

(b)

10 12 14 16 180

10

20

30

Van

t (kV

)

time (s)

(c)

JPN 75500

JG11

.884

a

0

1

2

PR

F (

MW

)

0

5

10

15

Dα (

au)

10 12 14 16 180

10

20

30

40

Van

t (kV

)time (s)

JPN 73906

(a)

(b)

(c)

JG11

.884

b

Figure 4. Left: high power density ILA pulse (L-mode): (a) ICRF power, (b) central electron temperature, (c) voltage on four antennastraps. Right: High antenna voltage ILA pulse (H-mode): (a) ICRF power, (b) Dα emission, (c) voltage on four antenna straps.

15 17 19 21 23 250.6

0.8

1

1.2

1.4

1.6

time (s)

JPN 77852

d x 10 [m]

R’ (

Ω/m

)

R’

JG11

.885

a

0.09 0.1 0.11 0.12 0.13 0.14 0.150.4

0.6

0.8

1

1.2

1.4

1.6

1.8

antenna–plasma (m)

R’ (

Ω/m

)

TOPICA

JPN 77852

JG11

.88–

5b

Figure 5. Left: time traces of the coupling resistance of one pair of the ILA straps together with the antenna–plasma distance (×10) inL-mode pulse 77852 at f = 42 MHz. Right coupling resistance versus antenna–plasma distance for the same discharge together with thenumerical modelling done with the TOPICA code.

3

Plasma Phys. Control. Fusion 54 (2012) 069601 Erratum

0.09 0.1 0.11 0.12 0.13 0.14 0.150.4

0.6

0.8

1

1.2

1.4

1.6

1.8

antenna–plasma (m)

R’ (

Ω/m

)

33MHz

42MHz

(L–mode)

JG11

.88–

6a

0.09 0.1 0.11 0.12 0.13 0.14 0.150.4

0.6

0.8

1

1.2

1.4

1.6

1.8

antenna–plasma (m)

R’ (

Ω/m

)

(42MHz)

L–mode

H–mode

JG11

.88

6b

Figure 6. Left: comparison of the coupling resistance obtained in the reference pulse 77852 (L-mode, 42 MHz) with a similar dischargewith the RF operating frequency reduced to f = 33 MHz (JPN 77847). Right: comparison of the reference pulse with a discharge with thesame operating frequency but in H-mode (JPN 77851), where steeper density gradients are present in the plasma edge.

0 2 4 6 81

1.5

2

2.5

3

3.5

<k//> [1/m]

Ran

t (Ω

)

Antenna AAntenna B

0π0π

0ππ0

00ππ

0π/2π3π/2

00π/2π/2

(f=42MHz)

JG11

.887

a

–10 –5 0 5 100

0.01

0.02

0.03

0.04

0.05

k// [1/m]

|Jan

t|2

0π0π

0ππ000ππ

JG11

.88

7b

Figure 7. Left: coupling resistance of the A2 antennas as a function of the dominant k‖ wavenumber excited in different phasingconfigurations (JPN 74091-74094, 78727-78732); (right) Example of the k‖-spectra excited by the A2 antennas computed with theANTITER II code for three cases: 0π0π (solid), 0ππ0 (dashed) and 00ππ (dashed–dotted).

4

Plasma Phys. Control. Fusion 54 (2012) 069601 Erratum

4 5 6 7 8

–4

–3

–2

–1

0

1

2

3

4

5

R(m)

Z(m

)B

0=2.65,T, f=42MHz

N=

1 H

N=

2 D

N=

1 3 H

e

N=

2 3 H

e

(a)

JG11

.88–

8a

4 5 6 7 8

–4

–3

–2

–1

0

1

2

3

4

5

R(m)

Z(m

)

B0=2.65,T, f=53MHz

(b)

N=

2 3 H

e

N=

1 H

N

=2

D

N=

3 D

JG11

.88–

8b

4 5 6 7 8

–4

–3

–2

–1

0

1

2

3

4

5

R(m)

Z(m

)

B0=5.3T, f=53MHz

(c)

N=

1 D

N=

1 3 H

e

N=

2 T

JG11

.88–

8c

Figure 8. Location of the main fundamental (solid), 2nd harmonic (dashed) and 3rd harmonic (dashed–dottted) ion cyclotron resonances ofvarious ion species under different conditions for ITER: (a) B0 = 2.65 T and f = 42 MHz, (b) B0 = 2.65 T and f = 53 MHz, (c) full-fieldDT operation at B0 = 5.3 T and f = 53 MHz.

1.8 2 2.2 2.4 2.60

0.1

0.2

0.3

0.4

0.5

Te0

(keV)

heat

ing

effic

ienc

y

elecs

ions

total

JG11

.88–

9a

0 5 10 15 200

0.1

0.2

0.3

0.4

0.5

0.6

0.7

0.8

mul

tipas

s ab

sorp

tion

T (keV)

ITE

R

total

elecs

ions

JG11

.88–

9b

Figure 9. Left: experimental heating efficiencies (ions—squares, electrons—circles, total—triangles) obtained in the H majority heatingexperiments in JET (JPN 79330-79335) as a function of the plasma temperature together with the multi-pass absorption predictions(ions—dashed–dotted, electrons—dashed, total—solid) based on the single pass absorption values computed with the TOMCAT code(light grey curves) by considering 22% of power losses per wave pass in the plasma. Right: Multi-pass absorption (ions—dashed–dotted,electrons—dashed, total—solid) estimated from the TOMCAT results for ITER’s half-field plasma conditions adopting the same losses asfound from the JET experiments (again, the grey curves indicate the single pass absorption values used in the multi-pass model).

5

Plasma Phys. Control. Fusion 54 (2012) 069601 Erratum

5 10 15 20 250

0.1

0.2

0.3

0.4

0.5

3He conc (%)

heat

ing

effic

ienc

y

total

elecs

ions

JG11

.88–

10a

0 5 10 15 20 250

0.2

0.4

0.6

0.8

1

mul

ti–pa

ss a

bsor

ptio

n

He3 conc (%)

total

elecs

3He ions H ions

ITE

R

JG11

.88–

10b

Figure 10. Left: experimental heating efficiencies (ions—squares, electrons—circles, total—triangles) obtained in the N = 2 3Heheating experiments in JET (JPN 79352) as a function of the 3He concentration together with the multi-pass absorption predictions(ions—dashed–dotted, electrons—dashed, total—solid) based on the single pass absorption values computed with the TOMCAT code(grey curves) considering 26% of power losses per wave pass in the plasma. Right: multi-pass absorption (ions—dashed–dotted,electrons—dashed, total—solid) estimated from the TOMCAT results for ITER’s half-field plasma conditions adopting the samelosses as found from the JET experiments (the grey curves indicate the single pass absorption values used in the multi-pass model).

0 1 2 3 4 5 60.5

1

1.5

2

2.5

3

3.5

4

4.5

PICRH

(MW)

Pra

d (M

W)

N=1 H

N=2 3He

JG11

.88–

11a

0 1 2 3 4 5 60

2

4

6

8

10

12

14x 10

12

PICRH

(MW)

Be

emis

sion

(a.

u.)

N=1 H N=2 3He

JG11

.88–

11b

Figure 11. Total radiated power (left) and intensity of the Be line (right) as a function of the ICRF power in a series of discharges of theN = 1 H majority (circles) and the N = 2 3He (triangles) ICRF heating experiments (JPN 79330-79335, JPN 79343-79352).

6