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Scenario development for DT operation at JET Scenario development for DT operation at JET

Scenario development for DT operation at JET - PowerPoint Presentation

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Scenario development for DT operation at JET - PPT Presentation

Presented by Luca Garzotti Acknowledgements L Garzotti 1 C Challis 1 R Dumont 2 D Frigione 3 J Graves 4 E Lerche 5 J Mailloux 1 M Mantsinen 67 F Rimini 1 F Casson ID: 914128

garzotti 2018 fec scenario 2018 garzotti scenario fec october gandhinagar india luca high 27th hybrid 22nd baseline power fusion

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Slide1

Scenario development for DT operation at JET

Presented by Luca Garzotti

Slide2

Acknowledgements

L. Garzotti

1

, C. Challis

1, R. Dumont2, D. Frigione3, J. Graves4, E Lerche5, J. Mailloux1, M. Mantsinen6,7, F. Rimini1, F. Casson1, A. Czarnecka8, J. Eriksson9, R. Felton1, L. Frassinetti10, D. Gallart6, J. Garcia2, C. Giroud1, E. Joffrin2, H.-T. Kim11, N. Krawczyk8, M. Lennholm11, P. Lomas1, C. Lowry11, L. Meneses12, I. Nunes12, M. Romanelli1, S. Sharapov1, S. Silburn1, A. Sips11, E. Stefániková9, M. Tsalas13, D. Valcarcel1, M. Valovič1 and JET contributors*1UKAEA, Culham, UK – 2CEA, Cadarache, France – 3ENEA, Frascati, Italy – 4EPFL, Lausanne, Switzerland – 5ERM, Bruxelles, Belgium – 6BSC, Barcelona, Spain – 7ICREA, Barcelona, Spain – 8IFPILM, Warsaw, Poland – 9Uppsala University, Uppsala, Sweden –10KTH, Stockholm, Sweden - 11JET PMU, Culham, UK – 12IST, Lisbon, Portugal –13DIFFER, Eindhoven, The Netherlands.*See the author list of “X. Litaudon et al. 2017 Nucl. Fusion 57 102001

Luca Garzotti | FEC 2018 | 22

nd

– 27

th

October 2018 | Gandhinagar, India |

2

Slide3

Outline

Motivation

Scenarios developed

Key results

Extension to stationary conditionsConclusionsLuca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 3

Slide4

Motivation

The JET exploitation plan foresees D-T operations in 2020 (DTE2).

Focus will be on demonstrating stationary high-performance plasmas lasting for several confinement times and conduct experiments demonstrating unequivocally alpha-particle physics.

Establish a reliable scenario capable of producing 5·10

16 neutrons/s for 5 s in D plasmas. (~15 MW of fusion power maintained over 5s in D-T).Intense activity of scenario development ongoing in D and T. Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 4Combined heating power will be 32 MW NBI and 8 MW ICRH

Slide5

Scenarios developed

Scenarios for performances:

β

N

~1.8, q95~3. Push the operation towards the high current and field limits with a relaxed current profile. Baseline.βN~2-3, q95~4. Exploit the advantages of operating at high βN with a shaped current profile and q0>1. Hybrid.both lines of research aim at achieving a stationary scenario of the duration of 5 s featuring H98>0.9, Wth≈10-12MJ in the domain achievable on JET most relevant to ITER in terms of combined ρ* and ν*Scenario for alpha-particle physics (ITB scenario): high plasma performance for 1-2 s to generate a significant population of α-particles.avoid ICRH in D-T to rule out TAEs destabilized by RF fast particles. maximize α-particle drive in conditions of elevated q0.minimize the damping provided by fast beam ions.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 5

Slide6

Performance so far

Baseline and hybrid plasma reach a maximum yield of ~3·10

16

neutrons/s.

Hybrid scenario is more effective in converting stored energy into fusion power. (More peaked density and temperature, higher reactivity for a given stored energy).Baseline scenario neutrons:~60% thermonuclear.Hybrid scenario neutrons:~30% thermonuclear.ITB scenario neutrons:40% thermonuclear.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 6TRANSP analysis

Slide7

Baseline and hybrid scenarios

Luca Garzotti | FEC 2018 | 22

nd

– 27

th October 2018 | Gandhinagar, India | 7H98~1.3, βN~2.5 and a neutron yield of 2.9 1016 neutrons/s for ~1s.High βN domain extended to B~2.8T for first time since ILW installed.

H

98

~1.1 and a neutron yield of ~3 10

16

neutrons/s were obtained for >5 energy confinement times (~1.5 s).

Combination of gas and ELM pacing D pellets injection.

Baseline

Hybrid

Slide8

Possible explanation for baseline high performance

Luca Garzotti | FEC 2018 | 22

nd

– 27

th October 2018 | Gandhinagar, India | 80 √ψN 10 √ψN 1Hyun-Tae Kim et al. Nucl. Fusion 2018Hyun-Tae Kim et al. EX/P1-5Pellet & gas fuelledFuelled by gas only

Slide9

Proposed explanation for hybrid high performance

Feedback loop between high

β

p

and improved pedestal stability.Further turbulence stabilisation from high β and fast particles can feed into the loop.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 9Challis C. et al. Nucl. Fusion 2015Saarelma S. et al. PPCF 2018Garcia J. et al. PoP 2018GENE GK simulations

Slide10

ITB scenario for alpha particle studies

Concentrated on alpha particle driven TAEs.

After-glow scenario (TFTR).

2.5 MA/3.4 T.

High plasma performance for 1-2 s.ICRH-induced TAE observed after the NBI switch off, with delay consistent with the beam fast ion slowing-down time.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 10Dumont R. et al. Nucl. Fusion 2018Sharapov S. et al. EX/P1-28

Slide11

ITB formation

q profile exhibits an extended region of low positive shear favourable for the triggering of an internal transport barrier (ITB).

Clear ITBs obtained for the first time since the installation of the ILW in JET.

Luca Garzotti | FEC 2018 | 22

nd – 27th October 2018 | Gandhinagar, India | 11√ψNqMailloux J. et al. EPS conference 201765432101

Slide12

DT extrapolation

Luca Garzotti | FEC 2018 | 22

nd

– 27

th October 2018 | Gandhinagar, India | 12D-T fusion power calculated assuming 50-50 D-T, same power for D and T beams.Best hybrid and baseline pulses extrapolated to high current and additional power.Self consistent core/pedestal modelling in semi-empirical simulations (Bohm/gyro-Bohm).Isotope effects taken into account in physics based simulations (TGLF, QuaLiKiZ).Uncertainty due to different currents and bootstrap current models.Garcia J. et al. TH/3-1

19

15

11

7

3

P

FUS

(MW)

20 30 40 50

P

IN

(MW)

CRONOS-TGFL & JINTRAC-QUALIKIZ: filled symbols

JINTRAC-BGB: open symbols

CRONOS-CDBM: Stars

Hybrid

Baseline

ITB

Slide13

Further development

Baseline scenario will be pushed towards higher current and field.

Detailed extrapolation path will depend on many factors, such as:

Optimum

βN,Choice of ICRH heating scheme (H vs 3He minority),Optimum current and q95.Hybrid scenario will also be extended to higher field, q95 and βN:strong emphasis placed on improving the MHD stability of the discharge to extend the MHD free phase to 5 s.Further challenges common to all scenarios will be addressed. Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 13

Slide14

Disruptions prevention and avoidance

High average

disruptivity

affects in particular the baseline scenario.

Techniques are being developed for better disruption prediction and avoidance.Improved termination strategies aiming at controlling impurity accumulation in the current ramp-down phase.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 14Sozzi C. et al. EX/P1-22Gerasimov S. et al. EX/P1-24de la Luna E. et al. EX/2-1Generative Topographic Mapping clustering of disruptive and non disruptive plasmas

Slide15

Divertor power load control

Strike-point sweeping

.

High power operations (P

IN=30 MW for 5 s) are compatible with 3.5 cm sweeping. (Hybrid).Modelling suggests 40 MW with wider sweeping should be tolerable.Ne seeding.Reduces the heating of the divertor tile.Non-negligible penalty on the fusion yield.Sweeping favourite optionLuca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 15Silburn S. et al. Phys. Scripta 2018

Slide16

Impurity accumulation avoidance

On-axis ICRH (fundamental H minority heating) reduces impurity accumulation.

More peaked electron temperature profile → enhanced turbulence drive → flatter density profile → reduced neoclassical impurity convection.

More peaked ion temperature profile (predicted by physics based modelling) → enhanced neoclassical impurity screening.

Other RF schemes foreseen for DT (e.g. 3He minority heating or 3-ion schemes) will be investigated for impurity control.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 16Lerche E. et al. Nucl. Fusion 2016Casson F. et al. TH/3-2~Ti

Slide17

Real time control improves robustness

Simultaneous real-time control of

f

ELM

and βN developed for steady conditions with sweeping.βN control and q-profile tailoring made possible to maintain βN~2.4 for ~3.5 s at B=2.14T with no detrimental MHD activity (critical for hybrid scenario).MHD free phase not yet extended to 5 s.Further optimization needed.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 17ELM frequency ref. and meas. [Hz]

4 5 6 7 8 9 10 11

Time (s)

Total gas injection rate [el/s]

β

N

ref.

and

meas

.

NBI power [MW]

JET pulse 92191

Lennholm M. et al. ITPA-IOS meeting 2017

Slide18

Conclusions

Good progress made towards the development of scenarios suitable for JET D-T.

~2.2·10

16

D-D neutrons/s over 5 s. Will be improved when 32 MW of NBI at 120 keV and 8 MW of ICRH power will be reliably available. The scenario developed for the study of α-particle effects, has demonstrated the potential of creating a plasma with α-particle pressure high enough to destabilize TAEs in the afterglow scenario.All scenarios will be replicated in T to investigate the impact of possible isotope effects.Real time control schemes to control plasma physics and machine operational parameters such as βN, ELM frequency, plasma isotope composition and divertor temperature will be used to improve the robustness of the scenarios. The encouraging results obtained so far confirm the prospect of a successful D-T campaign on JET in 2020 with an ITER-like wall and an extended set of diagnostics.Luca Garzotti | FEC 2018 | 22nd – 27th October 2018 | Gandhinagar, India | 18