Acknowledgments: L. Horton, D. Borba, G. Sips and JET Task Force - - PowerPoint PPT Presentation

acknowledgments l horton d borba g sips and jet task
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Acknowledgments: L. Horton, D. Borba, G. Sips and JET Task Force - - PowerPoint PPT Presentation

Acknowledgments: L. Horton, D. Borba, G. Sips and JET Task Force Leaders F. Romanelli 1 FEC 2014 Saint Petersburg 13-18 October 2014 DT integrated experiment Plasma scenarios ITER-like Plasma scenario in ITER wall compatibility


slide-1
SLIDE 1
  • F. Romanelli

1 FEC 2014 Saint Petersburg 13-18 October 2014

Acknowledgments:

  • L. Horton, D. Borba, G. Sips

and JET Task Force Leaders

slide-2
SLIDE 2
  • F. Romanelli

2 FEC 2014 Saint Petersburg 13-18 October 2014

Plasma scenarios in ITER configuration Plasma scenario compatibility ITER-like wall experiment DT integrated experiment

[J. Paméla, Fusion Eng. Des. 82 (2007) 590]

slide-3
SLIDE 3
  • F. Romanelli

3 FEC 2014 Saint Petersburg 13-18 October 2014

Plasma scenarios in ITER configuration Plasma scenario compatibility ITER-like wall experiment DT integrated experiment

[J. Paméla, Fusion Eng. Des. 82 (2007) 590]

The JET programme in support of ITER is now completing the characterization of the ITER-like wall and progressing towards the DT experiment.

slide-4
SLIDE 4
  • F. Romanelli

4 FEC 2014 Saint Petersburg 13-18 October 2014

JET ITER-like Wall

4 ¡

Upper ¡ Dump ¡ Plate ¡ Inner ¡ Wall ¡ Guard ¡ Limiters ¡ Mushrooms ¡ Saddle ¡coil ¡ protec:on ¡ Saddle ¡Coil ¡ Protec:ons ¡ Poloidal ¡ Limiters ¡ LH ¡+ ¡ICRH ¡ Protec:on ¡

Beryllium ¡

Normal ¡NBI ¡IW ¡ Cladding ¡ Magne:c ¡ covers ¡ B&C ¡ :les ¡

W-­‑coated ¡CFC ¡

Divertor ¡

Re-­‑ionisa:on ¡ Protec:ons ¡ Restraint ¡Ring ¡ Protec:ons ¡ Normal ¡NBI ¡Inner ¡ Wall ¡GL’s ¡ Inner ¡Wall ¡ Cladding ¡

Inconel+8µm ¡Be ¡ Bulk ¡W ¡

Bulk ¡W ¡

slide-5
SLIDE 5
  • F. Romanelli

5 FEC 2014 Saint Petersburg 13-18 October 2014

2009 2010 2011 2012 2013 2014 PNBI (MW)

ILW ¡shutdown ¡

ERFA ¡

2012 ¡shutdown ¡ NBI ¡water ¡ leak ¡

30 20 10

FEC 2010 FEC 2012 FEC 2014

Total power NBI Octant 4 NBI Octant 8

Max possible

CFC Be/W

Max possible Max possible

NB project targets Pref Pmax

New hardware of Neutral Beam enhancement performing according to design. Maximum power approaching target value

slide-6
SLIDE 6
  • F. Romanelli

6 FEC 2014 Saint Petersburg 13-18 October 2014

JET-­‑CFC ¡(2009) ¡ JET-­‑ILW ¡ ¡2014 ¡ Ip ¡ 4.5MA ¡ 4.0MA ¡ PNBI ¡ 23.2MW ¡ 28MW ¡ PICRH ¡ 8.7 ¡MW ¡(+ ¡ILA) ¡ 6 ¡MW ¡ NBI ¡input ¡ 185MJ ¡ 230MJ ¡ Pulse ¡rate* ¡ 18 ¡/day ¡ 17.5 ¡/day ¡

After 3 years of

  • peration with the ITER-

like wall:

  • System capabilities at

a similar level compared to the carbon wall.

  • Higher NBI power and

input energy

*: Successful physics pulses

Main limitation: Surface temperature (Be and W), to avoid melt damage.  Substantial increase in real-time protection systems (as required in ITER):  Infra Red protection of PFC’s  Closed-loop use of Massive Gas Injection for disruption mitigation  Disruption avoidance and plasma termination scenarios

slide-7
SLIDE 7
  • F. Romanelli

7 FEC 2014 Saint Petersburg 13-18 October 2014

JET-­‑CFC ¡(2009) ¡ JET-­‑ILW ¡ ¡2014 ¡ Ip ¡ 4.5MA ¡ 4.0MA ¡ PNBI ¡ 23.2MW ¡ 28MW ¡ PICRH ¡ 8.7 ¡MW ¡(+ ¡ILA) ¡ 6 ¡MW ¡ NBI ¡input ¡ 185MJ ¡ 230MJ ¡ Pulse ¡rate* ¡ 18 ¡/day ¡ 17.5 ¡/day ¡

After 3 years of

  • peration with the ITER-

like wall:

  • System capabilities at

a similar level compared to the carbon wall.

  • Higher NBI power and

input energy

*: Successful physics pulses

Main limitation: Surface temperature (Be and W), to avoid melt damage.  Substantial increase in real-time protection systems (as required in ITER):  Infra Red protection of PFC’s  Closed-loop use of Massive Gas Injection for disruption mitigation  Disruption avoidance and plasma termination scenarios

JET experience with Be+W shows the need

  • f a careful preparation (as now integrated

in the ITER research plan with the choice

  • f the W divertor from the beginning) to

achieve continuous improvement in the plasma performance.

slide-8
SLIDE 8
  • F. Romanelli

8 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-9
SLIDE 9
  • F. Romanelli

9 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-10
SLIDE 10
  • F. Romanelli

10 FEC 2014 Saint Petersburg 13-18 October 2014

2013 programme focussed on the support to an ITER decision on the day-one W divertor

B

  • One lamella on stack A

intentionally misaligned

  • IR measurements on

the top surface.

  • Modelling of lamella

temperature evolution by conduction through supporting structure

  • Note: the temperature
  • n the vertical surface

is not resolved. New stack to be installed in the next shutdown.

[G. Matthews EX/4-1 Wednesday,

  • J. Coenen, PSI 2014]

A B C D

slide-11
SLIDE 11
  • F. Romanelli

11 FEC 2014 Saint Petersburg 13-18 October 2014

Shallow W-melting does not impact JET operation

  • Strategy: 1s heating to

raise bulk lamella temperature to facilitate shallow melting by ~300 kJ ELMS q|| = 0.5 – 1.0 GW/m2

  • Results consistent with

melting followed by resolidification.

  • Small W events

associated with the

  • ccasional expulsion of

droplets but no impact

  • n JET operation!
slide-12
SLIDE 12
  • F. Romanelli

12 FEC 2014 Saint Petersburg 13-18 October 2014

84686 – Before melting

Special lamella 5.5mm Special lamella 5.5mm Special lamella 5.5mm Special lamella 5.5mm

q|| q||

Low Field Side High Field Side

slide-13
SLIDE 13
  • F. Romanelli

13 FEC 2014 Saint Petersburg 13-18 October 2014

After 84724

Special lamella Low Field Side High Field Side

slide-14
SLIDE 14
  • F. Romanelli

14 FEC 2014 Saint Petersburg 13-18 October 2014

After 84778

Special lamella Low Field Side High Field Side

slide-15
SLIDE 15
  • F. Romanelli

15 FEC 2014 Saint Petersburg 13-18 October 2014

After 84779

Special lamella Low Field Side High Field Side

slide-16
SLIDE 16
  • F. Romanelli

16 FEC 2014 Saint Petersburg 13-18 October 2014

After 84781

Special lamella Low Field Side High Field Side

slide-17
SLIDE 17
  • F. Romanelli

17 FEC 2014 Saint Petersburg 13-18 October 2014

After 84782

Special lamella Low Field Side High Field Side

slide-18
SLIDE 18
  • F. Romanelli

18 FEC 2014 Saint Petersburg 13-18 October 2014

After 84783

B

⊗ Jthermionic

JxB

Erosion: 150-300µm per pulse, 5-10µm per ELM (frequency 30Hz) Total volume moved: ~6mm3 High Field Side Low Field Side 5.5mm

slide-19
SLIDE 19
  • F. Romanelli

19 FEC 2014 Saint Petersburg 13-18 October 2014

After 84783

B

⊗ Jthermionic

JxB

Erosion: 150-300µm per pulse, 5-10µm per ELM (frequency 30Hz) Total volume moved: ~6mm3 HFS 5.5mm

Molten material on the lamella observed to coalesce and grow, which increases the risk for longer pulse duration above the melt threshold.

slide-20
SLIDE 20
  • F. Romanelli

20 FEC 2014 Saint Petersburg 13-18 October 2014

Side heat load lower than expected

Matching the experimental measurements requires mitigation factors instead of pure geometrical assumptions qn = qperp * fn; fn = 1 qs = q|| * fs; fs = 0.4 Vapour shielding included Larmor radius smoothing not sufficient

slide-21
SLIDE 21
  • F. Romanelli

21 FEC 2014 Saint Petersburg 13-18 October 2014

Side heat load lower than expected

Matching the experimental measurements requires mitigation factors instead of pure geometrical assumptions qn = qperp * fn; fn = 1 qs = q|| * fs; fs = 0.4 Vapour shielding included Larmor radius smoothing not sufficient

Potentially positive implications for ITER, which may be less sensitive than previously feared to exposed edges created by chipping of mono- block edges or components outside tolerance

slide-22
SLIDE 22
  • F. Romanelli

22 FEC 2014 Saint Petersburg 13-18 October 2014

Modelling of Melt layer

  • The melt layer

motion is modelled correctly by MEMOS by including the mitigation factors and the JxB force.

1 mm after seven pulses

[Bazylev TH/P3-40]

JxB

slide-23
SLIDE 23
  • F. Romanelli

23 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-24
SLIDE 24
  • F. Romanelli

24 FEC 2014 Saint Petersburg 13-18 October 2014

Material Migration

!"# $"#

  • !"#$

%&' !"#$ %&'

  • Sputtering at inner wall and

limiter at low impact energies (<10 eV)

  • At low energy, Be sputtering

yield (JET-ILW) is lower than total C sputtering yield (JET-C)

  • Spectroscopy and ex situ

analysis revealed a factor 4-5 smaller primary source

  • Absence of chemical erosion by

low energy particles in case of ILW!

  • Majority of Be transported in

SOL towards inner divertor

[S. Brezinsek, EX/P5-26]

slide-25
SLIDE 25
  • F. Romanelli

25 FEC 2014 Saint Petersburg 13-18 October 2014

  • ¡Measured long-term fuel retention by post-mortem analysis is below 0.25%
  • WallDYN ¡code ¡validated ¡by ¡gas ¡balance ¡and ¡post-­‑mortem ¡analysis ¡in ¡JET-­‑C ¡and ¡JET ¡ILW ¡
  • WallDYN confirms material migration path in JET in divertor configuration

ITER fuel retention predictions

slide-26
SLIDE 26
  • F. Romanelli

26 FEC 2014 Saint Petersburg 13-18 October 2014

  • ¡Measured long-term fuel retention by post-mortem analysis is below 0.25%
  • WallDYN ¡code ¡validated ¡by ¡gas ¡balance ¡and ¡post-­‑mortem ¡analysis ¡in ¡JET-­‑C ¡and ¡JET ¡ILW ¡
  • WallDYN confirms material migration path in JET in divertor configuration
  • WallDYN confirms fuel retention rate (absolute values) in JET-C and JET-

ILW ¡

ITER fuel retention predictions

[K. Schmid, EX/P5-32, K. Heinola, PSI 2014]

slide-27
SLIDE 27
  • F. Romanelli

27 FEC 2014 Saint Petersburg 13-18 October 2014

  • ¡Measured long-term fuel retention by post-mortem analysis is below 0.25%
  • WallDYN ¡code ¡validated ¡by ¡gas ¡balance ¡and ¡post-­‑mortem ¡analysis ¡in ¡JET-­‑C ¡and ¡JET ¡ILW ¡
  • WallDYN confirms material migration path in JET in divertor configuration
  • WallDYN confirms fuel retention rate (absolute values) in JET-C and JET-

ILW ¡

ITER fuel retention predictions

[K. Schmid, EX/P5-32, K. Heinola, PSI 2014]

ITER with Be+W walls 3000-20000 full power DT discharges before reaching the maximum tritium inventory.

slide-28
SLIDE 28
  • F. Romanelli

28 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-29
SLIDE 29
  • F. Romanelli

29 FEC 2014 Saint Petersburg 13-18 October 2014 Just before TQ: no RE Just after: TQ: 850 kA RE plateau

Runaway Electron suppression

  • Runaway electron beams are

not normally produced with the

  • ILW. They can be generated and

studied using massive Ar injection above some threshold value

  • Runaway avoidance is possible

using a second MGI as long as it comes before the thermal quench

  • Thereafter, runaway beam

suppression using high-Z MGI was found to be ineffective (Ar, Kr and Xe have been tried)

[C. Reux, EX/5-2 Thursday]

slide-30
SLIDE 30
  • F. Romanelli

30 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-31
SLIDE 31
  • F. Romanelli

31 FEC 2014 Saint Petersburg 13-18 October 2014 20 10 10 5 3.0 1.5 10 5 6 3 1.4 0.9 0.4 PNBI (MW) Gas dosing rate (1x1022/s) Line integrated density (1x1019 m-3) Central electron temperature (keV) Pulse 82122 8 12 16 20

fELM ~ 15 Hz

FEC 2012

  • W-accumulation avoided

by controlling ELM frequency through gas fuelling

Time (s) Be II

n/nGW = 0.80 Zeff = 1.4

  • Conf. time normalized to ITER98 scaling

ITER-relevant energy confinement re-established

H98y2

ITER reference

slide-32
SLIDE 32
  • F. Romanelli

32 FEC 2014 Saint Petersburg 13-18 October 2014 20 10 10 5 3.0 1.5 10 5 6 3 1.4 0.9 0.4 PNBI (MW) Gas dosing rate (1x1022/s) Line integrated density (1x1019 m-3) Central electron temperature (keV) 8 12 16 20 Time (s)

fELM ~ 15 Hz n/nGW = 0.80 Zeff = 1.4 n/nGW = 0.64 Zeff = 1.2 fELM ~ 40 Hz

Pulse 85290

FEC 2012

  • W-accumulation avoided by

controlling ELM frequency through gas fuelling FEC 2014

  • Strike point optimised for

maximum pumping

  • Higher ELM frequency
  • Long pulse operation (10s)
  • Te0 ~ 4.5keV
  • H98 =1 for > 9s

Pulse 82122 Be II

[E.Joffrin EX/P5-40]

  • Conf. time normalized to ITER98 scaling

ITER-relevant energy confinement re-established

H98y2 1.4 0.9

ITER reference

slide-33
SLIDE 33
  • F. Romanelli

33 FEC 2014 Saint Petersburg 13-18 October 2014 2012 data New data at q95~3

Optimisation, including placing the divertor strike point so as to maximise pumping, allows access to the ITER targets of H98=1 and βN=1.8  Also at ITER levels of input power of PNET/PLH ~1-2

ITER-relevant energy confinement re-established

  • Conf. time normalized

to ITER98 scaling Input power normalized to the threshold power for H-mode access

slide-34
SLIDE 34
  • F. Romanelli

34 FEC 2014 Saint Petersburg 13-18 October 2014

W control by ICRH successful

W accumulation determined by inward neoclassical convection due to density peaking of main plasma

[M. Valisa EX/6-1 Thursday] [M. Goniche, EPS 2014,

  • E. Lerche EX/P5-22]

!"

#$%&'()*

!+ !, !- !" +" , + !./ "./ " + , +

  • 01(23*

456 789:'(23* ;& !"+"(%<=* #& (>&?* @A0 BC8& %$:<89:$D) BC8& &:E& BC8& %$:<89:$D)

FG/,!+

slide-35
SLIDE 35
  • F. Romanelli

35 FEC 2014 Saint Petersburg 13-18 October 2014

Power scan with JET ITER-like wall at constant: IP, B, Meff, ne, a, R, κ

IPB98(y,2) scaling experiment

[C. Challis, Ex/9-3 Friday]

Weak confinement degradation with power

  • Power scan performed in type I

ELMy H-mode with low level gas injection shows weaker confinement degradation with power than expected from the IPB98(y,2) scaling

  • Rapid increase in β with

heating power due to:

– Increase in core temperature consistent with transport modelling including fast ion effects [J. Garcia, TH/5-2 Thursday] – Increase in density peaking correlated with collisionality – Increase in pedestal pressure consistent with peeling- ballooning modelling [C. Maggi, EX/3-3 Wednesday]

slide-36
SLIDE 36
  • F. Romanelli

36 FEC 2014 Saint Petersburg 13-18 October 2014

Power scan with JET ITER-like wall at constant: IP, B, Meff, ne, a, R, κ

IPB98(y,2) scaling experiment

[C. Challis, Ex/9-3 Friday]

High δ experiments with C-wall atypical. Possible role of neutrals. [E.De la Luna, EX/P5-29]

Weak confinement degradation with power

  • Power scan performed in type I

ELMy H-mode with low level gas injection shows weaker confinement degradation with power than expected from the IPB98(y,2) scaling

  • Rapid increase in β with

heating power due to:

– Increase in core temperature consistent with transport modelling including fast ion effects [J. Garcia, TH/5-2 Thursday] – Increase in density peaking correlated with collisionality – Increase in pedestal pressure consistent with peeling- ballooning modelling [C. Maggi, EX/3-3 Wednesday]

slide-37
SLIDE 37
  • F. Romanelli

37 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-38
SLIDE 38
  • F. Romanelli

38 FEC 2014 Saint Petersburg 13-18 October 2014

Integrated performance with N-seeding and divertor compatibility ¡

  • Semi-detached divertor
  • peration in both legs
  • No feed-back required
  • Stationary conditions

~7s=26✕τE ¡ ¡ ¡ITER

  • H98~ 0.85

1.0

  • βN~1.6

1.8

  • fGW~ 0.85

0.85

  • Zeff~ 1.6

1.6

  • ΔWELM/Wped~4% 1%
  • Similar scenario to be

developed with Ar or Ne for DT campaign

[C. Giroud, EX/P5-25]

slide-39
SLIDE 39
  • F. Romanelli

39 FEC 2014 Saint Petersburg 13-18 October 2014

  • Semi-detached divertor
  • peration in both legs
  • No feed-back required
  • Stationary conditions

~7s=26✕τE ¡ ¡ ¡ITER

  • H98~ 0.85

1.0

  • βN~1.6

1.8

  • fGW~ 0.85

0.85

  • Zeff~ 1.6

1.6

  • ΔWELM/Wped~4% 1%
  • Similar scenario to be

developed with Ar or Ne for DT campaign

Integrated performance including divertor compatibility require further development High radiation DEMO-relevant discharges presently limited on JET to frad=75% (see C. Lowry EX/7-2 Friday)

[C. Giroud, EX/P5-25]

Integrated performance with N-seeding and divertor compatibility ¡

slide-40
SLIDE 40
  • F. Romanelli

40 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-41
SLIDE 41
  • F. Romanelli

41 FEC 2014 Saint Petersburg 13-18 October 2014

Progress to maximum performance

  • Maximum performance in JET

is still being optimised but suffers from:

  • Lack of power to reach

moderate / high β at full current

  • Power handling limits that

require divertor sweeping – away from the position of maximum exhaust

  • Minimum gas (or ELM

frequency) to control W accumulation

[I. Nunes, EX/9-2 Friday]

slide-42
SLIDE 42
  • F. Romanelli

42 FEC 2014 Saint Petersburg 13-18 October 2014

Progress to maximum performance

  • Maximum performance in JET

is still being optimised but suffers from:

  • Lack of power to reach

moderate / high β at full current

  • Power handling limits that

require divertor sweeping – away from the position of maximum exhaust

  • Minimum gas (or ELM

frequency) to control W accumulation

[I. Nunes, EX/9-2 Friday]

Further optimisation will be a primary goal in 2015 and is driving upgrades planned for the 2014/15 shutdown:

  • Re-instate ITER-like Antenna to increase central heating for

W control

  • Relocate High Frequency Pellet Injector to facilitate ELM

pacing (also DEMO-relevant [P. Lang, SOFT 2014])

slide-43
SLIDE 43
  • F. Romanelli

43 FEC 2014 Saint Petersburg 13-18 October 2014 4 2 30 15 10 5 15 7.5 3 1.5 10 5 Ip (MA) Gas dosing rate (1x1022/s) Line integrated density (1x1019 m-3) D-D neutron rate (1x1016/s) Stored energy (MJ) Pulse 87412 (baseline) 7 9 11 Time (s)

n/nGW = 0.72 Zeff = 1.3 n/nGW = 0.70 Zeff = 1.5-1.6

Pulse 86614 (hybrid) PNBI (MW) PICRH (MW)

– Hybrid: 2.5MA/2.9T (q95=3.7): Transient good confinement phase of ~1 s Limited by MHD and divertor compatibility (low gas fuelling rate). – Baseline: 3.5MA/3.3T (q95=3): Stationary plasmas. Limited by very high gas dosing rates (to minimise risk of disruption) and temperature limit on divertor.

Progress to maximum performance

slide-44
SLIDE 44
  • F. Romanelli

44 FEC 2014 Saint Petersburg 13-18 October 2014 Hybrid Baseline 2014 DT extrapolation 2014 DT extrapolation Ip (MA) 2.5 3.5 3.5 (4) 4.5 Bt (Tesla) 2.9 3.85 3.4 3.85 q95 3.8 3.65 2.9 2.9 PNBI (MW) 24 34 27 34 PICRH (MW) 4 5 4 5 Wdia (MJ) 7.5 12 8 12 Duration (s) 1 5 2-3 5 Limitation MHD TF I2t Tsurf of divertor TF I2t Pfus (MW) (7) 15* (4) 13** *: Extrapolated from JET-C data ** 8MW for H98=0.8

Progress to maximum performance

Projection do not include alpha power and isotope effect on confinement. Compatibility with divertor operation still to be achieved for long pulse operation.

slide-45
SLIDE 45
  • F. Romanelli

45 FEC 2014 Saint Petersburg 13-18 October 2014 Hybrid Baseline 2014 DT extrapolation 2014 DT extrapolation Ip (MA) 2.5 3.5 3.5 (4) 4.5 Bt (Tesla) 2.9 3.85 3.4 3.85 q95 3.8 3.65 2.9 2.9 PNBI (MW) 24 34 27 34 PICRH (MW) 4 5 4 5 Wdia (MJ) 7.5 12 8 12 Duration (s) 1 5 2-3 5 Limitation MHD TF I2t Tsurf of divertor TF I2t Pfus (MW) (7) 15* (4) 13** *: Extrapolated from JET-C data ** 8MW for H98=0.8

Progress to maximum performance

Projection do not include alpha power and isotope effect on confinement. Compatibility with divertor operation still to be achieved for long pulse operation.

Plasma operation with the ITER-like Wall:

  • Is ~ready for T-T operation in 2017 (retention, isotope

scaling, RF studies)

  • Needs further development of ITER scenarios at high

performance in 2015

slide-46
SLIDE 46
  • F. Romanelli

46 FEC 2014 Saint Petersburg 13-18 October 2014

Outline

  • JET programme in support of ITER
  • Operation of JET with the ITER-like wall (ILW)
  • Tungsten Melt Experiment
  • Material Migration & Retention
  • Disruptions and Runaway Electrons
  • H-mode physics in an all-metal environment
  • H-mode optimization with the ILW
  • Stationary N-seeded discharges
  • Progress to maximum fusion performance
  • Conclusions and perspectives
slide-47
SLIDE 47
  • F. Romanelli

47 FEC 2014 Saint Petersburg 13-18 October 2014

There are two possible scenarios for the future use of JET:

  • *Details of the Alternative Scenario are not yet agreed

JET Forward Programme

slide-48
SLIDE 48
  • F. Romanelli

48 FEC 2014 Saint Petersburg 13-18 October 2014

  • Operation with shallow W melting have been demonstrated
  • n JET. Agreement with MEMOS predictions.
  • Retention/migration path reproduced by WallDYN. More than

3000 full DT shot on ITER to reach maximum T inventory.

  • High-confinement H-mode have been re-established at

2.5MA by optimizing the magnetic configuration.

  • Divertor compatible regimes established with N-seeding.

Confinement optimization in progress.

  • The preparation of the DT campaign in 2017 has started and

the demonstration of high (equivalent) fusion gain discharges will be the main objective of the 2015-16 JET programme.

Conclusions

slide-49
SLIDE 49
  • F. Romanelli

49 FEC 2014 Saint Petersburg 13-18 October 2014

  • L. ¡Aho-­‑ManRla ¡Assessment ¡of ¡Scrape-­‑off ¡Layer ¡SimulaRons ¡with

¡ DriXs ¡against ¡L-­‑mode ¡Experiments ¡in ¡ASDEX ¡Upgrade ¡and ¡ JET ¡ I ¡Bolshakova ¡Experimental ¡EvaluaRon ¡of ¡Stable ¡Long-­‑Term ¡ OperaRon ¡of ¡Semiconductor ¡MagneRc ¡Sensors ¡in ¡ITER-­‑ Relevant ¡Environment ¡

  • C. ¡Bourdelle ¡L ¡to ¡H ¡mode ¡transiRon: ¡Parametric ¡dependencies ¡
  • f ¡the ¡temperature ¡threshold ¡

W.A. ¡Cooper ¡Equilibrium ¡and ¡Fast ¡ParRcle ¡Confinement ¡in ¡3D ¡ tokamaks ¡with ¡toroidal ¡rotaRon ¡ ¡

  • E. ¡Delabi ¡e ¡Overview ¡and ¡InterpretaRon ¡of ¡L-­‑H ¡Threshold ¡

Experiments ¡on ¡JET ¡with ¡the ¡ITER-­‑like ¡Wall ¡

  • D. ¡Douai ¡Experimental ¡and ¡modelling ¡results ¡on ¡wall ¡

condiRoning ¡for ¡ITER ¡operaRon ¡

  • A. ¡Garcia-­‑Carrasco ¡Comprehensive ¡First ¡Mirror ¡Test ¡for ¡ITER ¡at ¡

JET ¡with ¡ITER-­‑Like ¡Wall ¡

  • S. ¡Gerasimov ¡JET ¡and ¡COMPASS ¡Asymmetrical ¡DisrupRons ¡
  • M. ¡Groth ¡Steps ¡in ¡validaRng ¡scrape-­‑off ¡layer ¡simulaRons ¡of ¡

detached ¡plasmas ¡in ¡the ¡JET ¡ITER-­‑like ¡wall ¡configuraRon ¡ GMD ¡Hogeweij ¡InterpretaRon ¡of ¡W ¡evoluRon ¡in ¡JET ¡and ¡AUG ¡ and ¡implicaRons ¡for ¡ITER ¡ GTA ¡Huijsmans ¡Non-­‑linear ¡MHD ¡SimulaRons ¡for ¡ITER ¡

  • P. ¡Jacquet ¡MaximizaRon ¡of ¡ICRF ¡power ¡by ¡SOL ¡density ¡tailoring ¡

with ¡local ¡gas ¡injecRon ¡ A ¡Jarvinen ¡Comparison ¡of ¡H-­‑mode ¡plasmas ¡in ¡JET-­‑ILW ¡and ¡JET-­‑C ¡ with ¡and ¡without ¡impurity ¡seeding ¡

  • F. ¡Jenko ¡Can ¡gyrokineRcs ¡really ¡describe ¡transport ¡in ¡L-­‑mode ¡core ¡

plasmas? ¡ A.B. ¡Kukushkin ¡TheoreRcal ¡Model ¡of ¡ITER ¡High ¡ResoluRon ¡H-­‑alpha ¡ Spectroscopy ¡for ¡a ¡Strong ¡Divertor ¡Stray ¡Light ¡and ¡ValidaRon ¡ Against ¡JET-­‑ILW ¡Experiments ¡

  • M. ¡Lennholm ¡Real-­‑Time ¡Control ¡of ¡ELM ¡and ¡Sawtooth ¡Frequencies: ¡

SimilariRes ¡and ¡Differences ¡

  • V. ¡Leonov ¡SimulaRon ¡of ¡the ¡Pre-­‑Thermal ¡Quench ¡Stage ¡of ¡

DisrupRons ¡during ¡Massive ¡Gas ¡InjecRon ¡and ¡ProjecRons ¡for ¡ ITER ¡

  • T. ¡Loarer ¡Plasma ¡isotopic ¡change ¡over ¡experiments ¡in ¡JET ¡under ¡

Carbon ¡and ¡ITER-­‑Like ¡Wall ¡condiRons ¡ J.R. ¡MarRn-­‑Solis ¡FormaRon ¡and ¡terminaRon ¡of ¡runaway ¡beams ¡in ¡ tokamak ¡disrupRons ¡and ¡implicaRons ¡for ¡ITER ¡

  • S. ¡Moradi ¡Core ¡micro-­‑instability ¡analysis ¡of ¡JET ¡hybrid ¡and ¡baseline ¡

discharges ¡with ¡carbon ¡wall ¡

  • V. ¡Plyusnin ¡Parameters ¡of ¡Runaway ¡Electrons ¡in ¡JET ¡
  • M. ¡Rubel ¡An ¡Overview ¡of ¡Erosion-­‑DeposiRon ¡Pamern ¡in ¡JET ¡with ¡

ILW ¡ A.C.C. ¡Sips ¡Progress ¡in ¡Preparing ¡Scenarios ¡for ¡ITER ¡OperaRon ¡

  • S. ¡VarouRs ¡SimulaRon ¡of ¡neutral ¡gas ¡flow ¡in ¡the ¡JET ¡subdivertor ¡and ¡

comparison ¡with ¡experimental ¡results ¡

  • T. ¡Wauters ¡ICRF ¡Discharge ¡ProducRon ¡for ¡Ion ¡Cyclotron ¡Wall ¡

CondiRoning ¡on ¡JET ¡

  • R. ¡Zagorski ¡Integrated ¡core-­‑SOL-­‑divertor ¡modelling ¡for ¡ITER ¡

including ¡impurity: ¡effect ¡of ¡W ¡on ¡fusion ¡performance ¡in ¡H-­‑ mode ¡and ¡hybrid ¡scenario ¡

Other JET contributions at this conference

slide-50
SLIDE 50
  • F. Romanelli

50 FEC 2014 Saint Petersburg 13-18 October 2014

ITER baseline New data at q95~3

Plasma Energy Confinement

Optimisation, including placing the divertor strike point so as to maximise pumping, allows access to the ITER targets of H98=1 and βN=1.8