Development of ITER 15 MA ELMy H-mode inductive scenario

Kessel, C.; Campbell, D.J.; Gribov, Y.; Saibene, G.; Ambrosino, G.; Budny, R.; Casper, T. A.; Cavinato, M.; Fujieda, H.; Hawryluk, R. J.; Horton, L. D.; Kavin, А.; Kharyrutdinov, R.; Koechl, F.; Leuer, J.A.; Loarte, A.; Lomas, P. J.; Luce, T. C.; Lukash, V.E.; Mattei, M.; Nunes, I.; Parail, V.; Polevoi, A.; Portone, A.; Sartori, R.; Sips, A. C. C.; Thomas, Paul R.; Welander, A.S.; Wesley, J.C.

doi:10.1088/0029-5515/49/8/085034

Cited by 69 publications

(114 citation statements)

References 21 publications

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“…While much R&D has been done, continued refinement of ITER inductive, hybrid, and steady-state DT scenarios is 021804- 3 Sips et al…”

Section: B High Priority Research Issues For Iter Scenariosmentioning

confidence: 99%

“…These are determined by comparing the change in the poloidal magnetic flux at the plasma boundary for ohmic and heated rampups. Utilizing simulations of the ITER baseline current rampup, 3 which required 115 Wb for an ohmic rampup (excludes external inductive), these translate into 11 and 17-23 Wb, respectively. DIII-D reports 24,27 indicate a savings level of $20% over ohmic rampups.…”

Section: B Iter Current Rampup and Rampdown Phasesmentioning

confidence: 99%

“…Plasmas 22, 021804 (2015) frequencies), while for hydrogen operation, without 3 He, ICRF can only be used at B t > 3.4 T in ITER. Resonant Magnetic Perturbation (RMP) coils and ELM pellet pacing should be commissioned for the mitigation of heat loads to the divertor, but they may also be required for the control of W accumulation in H-mode plasmas.…”

Section: -13mentioning

confidence: 99%

“…Key parts of the ITER scenarios are determined by the capability of the proposed poloidal field (PF) coil set. 3 They include the plasma breakdown at low loop voltage, the current rise phase, the performance during the flat top phase, and a ramp down of the plasma. The ITER discharge evolution has been verified in dedicated (joint) experiments.…”

mentioning

confidence: 99%

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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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“…While much R&D has been done, continued refinement of ITER inductive, hybrid, and steady-state DT scenarios is 021804- 3 Sips et al…”

Section: B High Priority Research Issues For Iter Scenariosmentioning

confidence: 99%

Section: B Iter Current Rampup and Rampdown Phasesmentioning

confidence: 99%

Section: -13mentioning

confidence: 99%

mentioning

confidence: 99%

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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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“…Scenario 2 flat-top time has recently been analysed in detail for different pedestal temperatures and Ejima parameters [26]. In this study here, the reference heating mix was compared with pure ECCD for the volt-second consumption.…”

Section: Scenariomentioning

confidence: 99%

On the heating mix of ITER

Wagner¹,

Bécoulet²,

Budny³

et al. 2010

Plasma Phys. Control. Fusion

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This paper considers the heating mix of ITER for the two main scenarios. Presently, 73 MW of absorbed power are foreseen in the mix 20/33/20 for ECH, NBI and ICH. Given a sufficient edge stability, Q = 10-the goal of scenario 2-can be reached with 40 MW power irrespective of the heating method but depends sensitively inter alia on the H-mode pedestal temperature, the density profile shape and on the characteristics of impurity transport. ICH preferentially heats the ions and would contribute specifically with Q < 1.5. The success of the Q = 5 steady-state scenario 4 with reduced current requires discharges with improved confinement necessitating weakly or strongly reversed shear, f bs > 0.5, and strong off-axis current drive (CD). The findings presented here are based on revised CD efficiencies γ for ECCD and a detailed benchmark of several CD codes. With ECCD alone, the goals of scenario 4 can hardly be reached. Efficient off-axis CD is only possible with NBI. With beams, inductive discharges with f ni > 0.8 can be maintained for 3000 s. The conclusion of this study is that the present heating mix of ITER is appropriate. It provides the necessary actuators to induce in a flexible way the best possible scenarios. The development risks of NBI at 1 MeV can be reduced by operation at 0.85 MeV.

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Calculation of Internal Inductance and Poloidal Beta Using Solovev’s Assumption in a Circular Cross Section Tokamak

Rahimi-Rad

Ghoranneviss

2012

J Fusion Energ

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Development of ITER 15 MA ELMy H-mode inductive scenario

Cited by 69 publications

References 21 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

On the heating mix of ITER

Calculation of Internal Inductance and Poloidal Beta Using Solovev’s Assumption in a Circular Cross Section Tokamak

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