Enhancement of plasma burn-through simulation and validation in JET

Kim, Hyun-Tae; Fundamenski, W.; Sips, A. C. C.; Contributors, Efda‐Jet

doi:10.1088/0029-5515/52/10/103016

Cited by 42 publications

(120 citation statements)

References 30 publications

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“…18 The DYON code is a plasma burn-through simulator developed at JET. 21 The simulation results have been compared and validated with experimental data from the JET campaigns with the ITER-like wall. The DYON code has been used to perform a predictive simulation for ITER.…”

Section: A Plasma Formationmentioning

confidence: 99%

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Sips

Giruzzi²,

Ide

et al. 2014

Physics of Plasmas

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The development of operating scenarios is one of the key issues in the research for ITER which aims to achieve a fusion gain (Q) of ∼10, while producing 500 MW of fusion power for ≥300 s. The ITER Research plan proposes a success oriented schedule starting in hydrogen and helium, to be followed by a nuclear operation phase with a rapid development towards Q ∼ 10 in deuterium/tritium. The Integrated Operation Scenarios Topical Group of the International Tokamak Physics Activity initiates joint activities among worldwide institutions and experiments to prepare ITER operation. Plasma formation studies report robust plasma breakdown in devices with metal walls over a wide range of conditions, while other experiments use an inclined EC launch angle at plasma formation to mimic the conditions in ITER. Simulations of the plasma burn-through predict that at least 4 MW of Electron Cyclotron heating (EC) assist would be required in ITER. For H-modes at q95 ∼ 3, many experiments have demonstrated operation with scaled parameters for the ITER baseline scenario at ne/nGW ∼ 0.85. Most experiments, however, obtain stable discharges at H98(y,2) ∼ 1.0 only for βN = 2.0–2.2. For the rampup in ITER, early X-point formation is recommended, allowing auxiliary heating to reduce the flux consumption. A range of plasma inductance (li(3)) can be obtained from 0.65 to 1.0, with the lowest values obtained in H-mode operation. For the rampdown, the plasma should stay diverted maintaining H-mode together with a reduction of the elongation from 1.85 to 1.4. Simulations show that the proposed rampup and rampdown schemes developed since 2007 are compatible with the present ITER design for the poloidal field coils. At 13–15 MA and densities down to ne/nGW ∼ 0.5, long pulse operation (>1000 s) in ITER is possible at Q ∼ 5, useful to provide neutron fluence for Test Blanket Module assessments. ITER scenario preparation in hydrogen and helium requires high input power (>50 MW). H-mode operation in helium may be possible at input powers above 35 MW at a toroidal field of 2.65 T, for studying H-modes and ELM mitigation. In hydrogen, H-mode operation is expected to be marginal, even at 2.65 T with 60 MW of input power. Simulation code benchmark studies using hybrid and steady state scenario parameters have proved to be a very challenging and lengthy task of testing suites of codes, consisting of tens of sophisticated modules. Nevertheless, the general basis of the modelling appears sound, with substantial consistency among codes developed by different groups. For a hybrid scenario at 12 MA, the code simulations give a range for Q = 6.5–8.3, using 30 MW neutral beam injection and 20 MW ICRH. For non-inductive operation at 7–9 MA, the simulation results show more variation. At high edge pedestal pressure (Tped ∼ 7 keV), the codes predict Q = 3.3–3.8 using 33 MW NB, 20 MW EC, and 20 MW ion cyclotron to demonstrate the feasibility of steady-state operation with the day-1 heating systems in ITER. Simulations using a lower edge pedestal temperature (∼3 keV) but improved core confinement obtain Q = 5–6.5, when ECCD is concentrated at mid-radius and ∼20 MW off-axis current drive (ECCD or LHCD) is added. Several issues remain to be studied, including plasmas with dominant electron heating, mitigation of transient heat loads integrated in scenario demonstrations and (burn) control simulations in ITER scenarios.

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Section: A Plasma Formationmentioning

confidence: 99%

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Sips

Giruzzi²,

Ide

et al. 2014

Physics of Plasmas

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show abstract

“…According to this, oxygen sputtering is also modelled for the carbon wall JET with a constant sputtering yield, 1. The details of the chemical sputtering model used are given in [10]. The DYON simulation results using the wallsputtering model for the carbon wall have shown good agreement with the experimental data of JET with the carbon wall as presented in [10].…”

Section: Review Of Wall-sputtering Models For Carbon Wallmentioning

confidence: 53%

“…The details of the chemical sputtering model used are given in [10]. The DYON simulation results using the wallsputtering model for the carbon wall have shown good agreement with the experimental data of JET with the carbon wall as presented in [10]. However, it should be noted that the chemical sputtering model used was a simplified model, without considering some issues such as chemical sputtering by neutrals, physical sputtering, and a-CH film formation on the wall surface.…”

Section: Review Of Wall-sputtering Models For Carbon Wallmentioning

confidence: 64%

“…It should be noted that for the carbon wall simulations the DYON simulation results with the decay model showed better agreement with the JET data. [10]. Figure 10(b).…”

Section: Deuterium Recycling Coefficientmentioning

confidence: 99%

“…radiation and ionization power loss P rad+iz , equilibration power loss P equi , and convective transport power loss P e conv . In the case of a pure deuterium plasma assumed in this section, they are calculated as shown below [6] [10].…”

Section: Criterion For Deuterium Burn-throughmentioning

confidence: 99%

See 2 more Smart Citations

Physics of plasma burn-through and DYON simulations for the JET ITER-like wall

Kim¹,

Sips²,

Contributors³

2013

Nucl. Fusion

Self Cite

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Abstract. This paper presents the DYON simulations of the plasma burn-through phase at Joint European Torus (JET) with the ITER-like wall. The main purpose of the study is to validate the simulations with the ITER-like wall, made of beryllium. Without impurities, the burn-through process of a pure deuterium plasma is described using DYON simulations, and the criterion for deuterium burn-through is derived analytically. The plasma burn-through with impurities are simulated using wallsputtering models in the DYON code, which are modified for the ITER-like wall. The wall-sputtering models and the validation against JET data are presented. The impact of the assumed plasma parameters in DYON simulations are discussed by means of parameter scans. As a result, the operation space of prefill gas pressure and toroidal electric field for plasma burn-through in JET is compared to the Townsend avalanche criterion.Physics of plasma burn-through and DYON simulations for the JET ITER-like wall 2

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0-D modeling of SST-1 plasma break-down & start-up using ECRH assisted pre-ionization

Kumar

Pradhan

2016

Fusion Engineering and Design

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Enhancement of plasma burn-through simulation and validation in JET

Cited by 42 publications

References 30 publications

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Progress in preparing scenarios for operation of the International Thermonuclear Experimental Reactor

Physics of plasma burn-through and DYON simulations for the JET ITER-like wall

0-D modeling of SST-1 plasma break-down & start-up using ECRH assisted pre-ionization

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