Integrated modelling of steady-state scenarios and heating and current drive mixes for ITER

Murakami, M.; Park, J.M.; Giruzzi, G.; García, J.; Bonoli, P. T.; Budny, R.; Doyle, E. J.; Fukuyama, A.; Hayashi, Nobuhiko; Honda, M.; Hubbard, A.; Ide, S.; Imbeaux, F.; Jaeger, E. F.; Luce, T. C.; Na, Y.-S.; Oikawa, T.; Osborne, T. H.; Parail, V.; Polevoi, A.; Prater, R.; Sips, A. C. C.; Snipes, J.; John, H.E. St.; Snyder, P. B.; Voitsekhovitch, I.; Itpa,

doi:10.1088/0029-5515/51/10/103006

Cited by 50 publications

(50 citation statements)

References 32 publications

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“…It was found that the overall results from different codes using the stiff theory-based (GLF23) model agree well. 6 There are still some discrepancies in the fusion products and, as mentioned before, differences in the computed loss mechanism (such as radiation). Global and local current balance is important for steady state scenarios.…”

Section: -16mentioning

confidence: 95%

“…Simulations have been performed limited to the evolution of current and temperatures (i.e., with non-evolving density, rotation and impurity profiles). This benchmark exercise was extended to steady-state scenarios, 6 one characterised by high pedestal and weak shear, and a second study with ITB. The results of the benchmarks for the hybrid and steady-state scenarios are summarized here.…”

Section: Benchmarking Hybrid and Steady-state Simulationsmentioning

confidence: 99%

“…Since it is not possible to reproduce all the physics parameters of ITER plasmas simultaneously in present experiments, simulations are used to project to ITER regimes using theory based physics models that are being tested against present tokamak experiments. [4][5][6] These efforts include energy, particle, current, and momentum transport and self-consistent ideal magneto-hydrodynamic (MHD) equilibrium and stability calculations, together with heating and current drive (H&CD) source models in timedependent discharge simulations. In order to provide a more consistent prediction for ITER, a common set of parameters for the scenarios and a comparison (benchmarking) of the various codes has been coordinated by the IOS-TG.…”

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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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Section: -16mentioning

confidence: 95%

Section: Benchmarking Hybrid and Steady-state Simulationsmentioning

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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“…The coupling between the core transport solver and the external components usually occurs at memory level in view of the frequent calls that the core solver has to make to its modules while integrating the transport equations in time. A non-exhaustive list of these codes are ONETWO [1,2], TRANSP/PTRANSP [3], TOP-ICS [4], ASTRA [5], CRONOS [6], CORSICA [7], FAS-TRAN [8], FACETS [9].…”

Section: Transport-based Frameworkmentioning

confidence: 99%

Integrated Modeling of Tokamak Experiments with OMFIT

Meneghini

Lao

2013

Plasma and Fusion Research

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One Modeling Framework for Integrated Tasks (OMFIT) is a framework that allows data to be easily exchanged among different codes by providing a unifying data structure. The main idea at the base of OMFIT is to treat files, data and scripts as a uniform collection of objects organized into a tree structure, which provides a consistent way to access and manipulate such collection of heterogeneous objects, independent of their origin. Within the OMFIT tree, data can be copied/referred from one node to another and tasks can call each other allowing for complex compound task to be built. A top-level Graphical User Interface (GUI) allowing users to manage tree objects, carry out simulations and analyze the data either interactively or in batch. OMFIT supports many scientific data formats and when a file is loaded into the framework, its data populates the tree structure, automatically endowing it with many potential uses. Furthermore, seamless integration with experimental management systems allows direct manipulation of their data. In OMFIT modeling tasks are organized into modules, which can be easily combined to create arbitrarily-large multi-physics simulations. Modules inter-dependencies are seamlessly defined by variables referencing tree locations among them. Creation of new modules and customization of existing ones is encouraged by graphical tools for their management and an online repository. High level Application Programmer Interfaces (APIs) enable users to execute their codes on remote servers and creation application-specific GUIs. Finally, within OMFIT it is possible to visualize experimental and modeling data for both quick analysis and publication purposes. Examples of application to the DIII-D tokamak are presented.

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“…Previous work on steady-state exploration in ITER with internal transport barriers includes integrated benchmark of transport codes by Kessel et al 13 and Murakami et al, 18 steady state scenarios by Garcia et al 16,19 (who also extensively discuss the role of reverse shear) and Giruzzi et al 20 In this work, we examine the formation of ITBs in L-mode and their sustainment in the flattop phase with the day-one heating mix. We discuss, in particular, how the electron cyclotron (EC) launcher configuration affects the magnetic geometry and the dynamics of ITBs.…”

Section: Introductionmentioning

confidence: 99%

Formation and sustainment of internal transport barriers in the International Thermonuclear Experimental Reactor with the baseline heating mix

Poli

Kessel

2013

Physics of Plasmas

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Plasmas with internal transport barriers (ITBs) are a potential and attractive route to steady-state operation in ITER. These plasmas exhibit radially localized regions of improved confinement with steep pressure gradients in the plasma core, which drive large bootstrap current and generate hollow current profiles and negative magnetic shear. This work examines the formation and sustainment of ITBs in ITER with electron cyclotron heating and current drive. The time-dependent transport simulations indicate that, with a trade-off of the power delivered to the equatorial and to the upper launcher, the sustainment of steady-state ITBs can be demonstrated in ITER with the baseline heating configuration. V C 2013 AIP Publishing LLC. [http://dx.

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Integrated modelling of steady-state scenarios and heating and current drive mixes for ITER

Cited by 50 publications

References 32 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

Integrated Modeling of Tokamak Experiments with OMFIT

Formation and sustainment of internal transport barriers in the International Thermonuclear Experimental Reactor with the baseline heating mix

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