H-mode Edge Transport Barrier Research Articles

Ion thermal transport in the H-mode edge transport barrier on DIII-D

The power balance ion heat flux in the pedestal region on DIII-D increases and becomes increasingly anomalous (above conventional neoclassical) in experiments with higher temperature and lower density pedestals where the ion collisionality (νi*) is lowered toward values expected on ITER. Direct measurements of the main-ion temperature are shown to be essential on DIII-D when calculating the ion heat flux due to differences between the temperature of D+ and the more commonly measured C6+ impurity ions approaching the separatrix. Neoclassical transport calculations from NEO and non-linear gyrokinetic calculations using CGYRO are consistent with these observations and show that while neoclassical transport plays an important role, the turbulent ion heat flux due to ion scale electrostatic turbulence is significant and can contribute similar or larger ion heat fluxes at lower collisionality. Beam emission spectroscopy and Doppler backscattering measurements in the steep gradient region of the H-mode pedestal reveal increased broadband, long-wavelength ion scale fluctuations for the low νi* discharges at the radius where the non-linear CGYRO simulations were run. Taken together, increased fluctuations, power balance calculations, and gyrokinetic simulations show that the above neoclassical ion heat fluxes, including the increases at lower νi*, are likely due to weakly suppressed ion scale electrostatic turbulence. These new results are based on world first inferred ion and electron heat fluxes in the pedestal region of deuterium plasmas using direct measurements of the deuterium temperature for power balance across ion collisionalities covering an order of magnitude from high νi* values of 1.3 down to ITER relevant νi* ∼0.1.

Observation of fully detached divertor integrated with improved core confinement for tokamak fusion plasmas

Integration of divertor detachment with a high-performance (βN ∼ 3, βp > 2, H98 ∼ 1.5) core plasma has been demonstrated in DIII-D high-βp (poloidal beta) plasmas associated with a sustained core internal transport barrier (ITB) and an H-mode edge transport barrier (ETB). Such good core-edge integration has been achieved for both neon and nitrogen seeding, for both favorable and unfavorable B-field directions, independently from the impurity puffing locations, though these variations play important roles on divertor characteristics. Compared to the standard H-mode plasmas, the high-βp plasma exhibits a much wider window of detachment compatible with high confinement core. Fully detached divertor plasmas with low plasma temperature (Te < 5 eV), low particle flux, and low heat flux across the entire divertor target plate were obtained by using nitrogen seeding. This detached high-βp plasma is compatible with a newly developed detachment control system which can help optimize the nitrogen gas flow rate. Several features, i.e., the high edge safety factor in the high-βp scenario, impurity injection, closed divertor and reduced heating power requirement due to the high confinement, facilitate the achievement of full divertor detachment at lower density. Instead of degrading global performance, the divertor detachment facilitates the access to an even stronger ITB at large radius with a relatively weak ETB through self-organized synergy between ITB and ETB, leading to sustained high confinement. The strengthening of the large-radius ITB compensates for the ETB degradation associated with divertor detachment. In addition, a weak ETB naturally has smaller edge localized modes (ELMs). In particular, with neon injection, a long-period no-ELM H-mode phase has been achieved simultaneously with high-performance core and partially detached divertor plasmas. These results demonstrate the possibility of integrating excellent core plasma performance with an effective divertor solution, an essential step toward steady-state operation of reactor-grade plasmas.

Transport of tungsten in the H-mode edge transport barrier of ITER

The neoclassical transport of tungsten in the H-mode edge transport barrier (ETB) of ITER is investigated and scaling relations for the transport coefficients are evaluated. The major finding is that the radial convection velocity of tungsten is outward directed for a large proportion of the tested pedestal profiles. This is due to a combination of the high pedestal temperatures and the high separatrix densities making the outward directed temperature screening term the predominant contribution of the collisional convection. The high densities at the separatrix are needed to control the power exhaust and the tungsten sputtering in the divertor and the high pedestal temperatures are expected to be achieved in ITER to meet its fusion performance objectives. The density and temperature profiles, which deliver simultaneously optimum fusion performance, power exhaust and tungsten sputtering control in ITER, also ensure optimum collisional radial transport of tungsten leading to hollow tungsten density profiles in the ETB. In helium H-mode plasmas, which are considered for the initial ITER non-active operation, this very favourable neoclassical transport effect is reduced and only about half of the considered edge plasma profiles yield an outward directed drift.

Observation of different phases during an ELM crash with the help of nitrogen seeding

A new method was applied to indirectly obtain information about the features of the crash of the H-mode edge transport barrier in consequence of an edge localized mode (ELM). The method is based on a combination of fast measurements, without spatial resolution, and relatively slow measurements, with high spatial resolution. The comparison of two different ELM scenarios in the full metal tokamak ASDEX Upgrade—a standard scenario and one with additional nitrogen seeding—revealed a two-fold nature of the ELM crash. In the case with additional nitrogen only a part of the standard crash is observed. This suggests the standard ELM crash consists of two or more consecutive events instead of a single distinct one. Some of these events are observed to be suppressed with changes in plasma parameters. The effect of the impurity seeding on different plasma parameters is documented in detail and compared to measurements conducted in machines with a carbon wall.The radial extent of the phases observed during the ELM crash differs in the kinetic profiles, with one instability extending inside the pedestal top and the other being confined to the pedestal region. This picture can explain the differences in the loss of stored energy and the change in ELM frequency which are observed for the analysed pair of discharges. It also suggests that the ELM crash starts at the pedestal top and only then affects the steep gradient region.

Main chamber sources and edge transport of tungsten in H-mode plasmas at ASDEX Upgrade

In the fully tungsten clad ASDEX Upgrade, the sputtering rates of tungsten have been determined at all relevant plasma facing components using fast spectroscopic measurements with temporal resolution down to 0.5 ms. The sputtering strongly increases during an edge-localized mode (ELM) and the ELMs are often the dominant cause of tungsten sputtering. A modelling approach was employed to calculate the tungsten source at the limiters and the resulting tungsten density at the pedestal top inside the H-mode edge transport barrier (ETB). In the ETB, it is assumed that tungsten transport is collisional, i.e. behaves like other impurities. The collisional transport leads to strong inward drifts and steep density gradients in the ETB, which are flattened during an ELM causing an efflux of tungsten. The collisional transport in the ETB is also calculated for typical ITER conditions and the resulting tungsten density profiles as well as the transport of the helium ash through the ETB are evaluated.

The application of classification methods in a data driven investigation of the JET L–H transition

Understanding the processes which establish the H-mode edge transport barrier (ETB) and the scaling of those processes with the plasma properties local to the plasma edge is of critical importance for optimizing the performance of power-station scale fusion plasmas. In this paper, data from 67 JET pulses were assembled and classified by confinement mode. A neural network classification technique was applied to identify the nature of the dependence of the L–H boundary on plasma parameters local to the plasma edge. Strong dependences on Te, ne, ⟨B⟩ and a weak dependence on q80 were found. In applying the neural network model as a confinement mode identification tool, the correct operating mode was identified for 98.86% of the time slices in a test data set. Using an extended data set the boundary predictions from five theoretical ETB models were evaluated. These models consider a range of different physical processes for the ETB. One model was clearly rejected. While other models proved more favourable, none of the tested models robustly described the JET L–H boundary.

Pedestal width and ELM size identity studies in JET and DIII-D; implications for ITER

The dependence of the H-mode edge transport barrier width on normalized ion gyroradius (ρ* = ρ/a) in discharges with type I ELMs was examined in experiments combining data for the JET and DIII-D tokamaks. The plasma configuration as well as the local normalized pressure (β), collisionality (ν*), Mach number and the ratio of ion and electron temperature at the pedestal top were kept constant, while ρ* was varied by a factor of four. The width of the steep gradient region of the electron temperature (Te) and density (ne) pedestals normalized to machine size showed no or only a weak trend with ρ*. A ρ1/2 or ρ1 dependence of the pedestal width, given by some theoretical predictions, is not supported by the current experiments. This is encouraging for the pedestal scaling towards ITER as it operates at lower ρ* than existing devices. Some differences in pedestal structure and ELM behaviour were, however, found between the devices; in the DIII-D discharges, the ne and Te pedestal were aligned at high ρ* but the ne pedestal shifted outwards in radius relative to Te as ρ* decreases, while on JET the profiles remained aligned while ρ* was scanned by a factor of two. The energy loss at an ELM normalized to the pedestal energy increased from 10% to 40% as ρ* increased by a factor of two in the DIII-D discharges but no such variation was observed in the case of JET. The measured pedestal pressures and widths were found to be consistent with the predictions from modelling based on peeling–ballooning stability theory, and are used to make projections towards ITER

Compatibility of ITER scenarios with an all-W wall

In 2008, ASDEX Upgrade has started its second experimental campaign with full tungsten coverage of the plasma facing components. In the transition from a partially W-coated device (69% tungsten coverage in 2004/2005) to a full tungsten device (since 2007), post campaign analyses show a reduction by an order of magnitude in both the carbon deposition and deuterium retention for the experimental campaigns. Spectroscopic measurements show that the outer divertor is by far the strongest tungsten source region. However, influxes from the outboard limiters are the most important source for the tungsten content in the plasma. The application of ICRH results in large W influxes due to sputtering from light impurities accelerated by electrical fields at the ICRH antennas. In H-mode discharges, ELMs reduce the inward transport of tungsten in the H-mode edge transport barrier. Central heating provided by neutral beams and the upgraded ECRH systems is used to avoid tungsten accumulation in the core of the plasma. Stationary, ITER relevant H-modes (H98 ∼ 1, βN ∼ 1.6–2), with W concentrations below 3 × 10−5, were routinely achieved. High performance H-modes have been obtained before the first boronization, achieving H98 = 1.1–1.2 and βN up to 2.6 as required for advanced scenarios in ITER. Specific ITER studies performed in 2008 include the demonstration of low voltage plasma start-up with ECRH and heating during the current rise to q95 = 3, to achieve a range of plasma inductance of 0.71–0.97. The new results reported here form the basis of further enhancing the operational space of ASDEX Upgrade with the full tungsten wall, preparing for ITER and the ITER-like wall project in JET.

Transport and confinement in the Mega Ampère Spherical Tokamak (MAST) plasma

A combination of recently installed state-of-the-art imaging and profile diagnostics, together with established plasma simulation codes, are providing for the first time on Mega Ampère Spherical Tokamak (MAST) the tools required for studying confinement and transport, from the core through to the plasma edge and scrape-off-layer (SOL). The H-mode edge transport barrier is now routinely turned on and off using a combination of poloidally localized fuelling and fine balancing of the X-points. Theory, supported by experiment, indicates that the edge radial electric field and toroidal flow velocity (thought to play an important role in H-mode access) are largest if gas fuelling is concentrated at the inboard side. H-mode plasmas show predominantly type III ELM characteristics, with confinement HH factor (w.r.t. scaling law IPB98[y, 2]) around ∼1.0. Combining MAST H-mode data with the International Tokamak Physics Activities (ITPA) analyses, results in an L–H power threshold scaling proportional to plasma surface area (rather than PLH ∼ R2). In addition, MAST favours an inverse aspect ratio scaling PLH ∼ ε0.5. Similarly, the introduction of type III ELMing H-mode data to the pedestal energy regression analysis introduces a scaling Wped ∼ ε−2.13 and modifies the exponents on R, BT and κ. Preliminary TRANSP simulations indicate that ion and electron thermal diffusivities in ELMing H-mode approach the ion-neoclassical level in the half-radius region of the plasma with momentum diffusivity a few times lower. Linear flux-tube ITG and ETG microstability calculations using GS2 offer explanations for the near-neoclassical ion diffusivity and significantly anomalous electron diffusivity seen on MAST. To complement the baseline quasi-steady-state H-mode, newly developed advanced regimes are being explored. In particular, ‘broad’ internal transport barriers (ITBs) have been formed using techniques developed at conventional aspect ratio. Electron and ion energy diffusivities are reduced towards the ion-neoclassical level in the ITB region of both co- and counter-injection NBI heated plasmas, with momentum diffusivity up to 10 times lower. Moving out to the edge and SOL, OSM2/EIRENE modelling is being used to extract edge perpendicular particle and heat diffusivities, results being consistent with the ballooning nature of power-flow seen in L-mode and reduction in outboard turbulence seen in ELM-free and inter-ELM H-mode. Modelling of parallel SOL transport requires the inclusion of the mirror force (∼10 times higher in MAST than at the conventional aspect ratio) and B2SOLPS5.0 simulations show the edge electric field to be well modelled by neoclassical theory. Transient edge transport phenomena are being studied in detail using a variety of techniques (e.g. probability density function (PDF) and power spectrum analysis, differencing and rescaling methods). Intermittent transport is associated with a radial efflux at up to a tenth of the sound speed and up to 30 cm from the separatrix. Arguably, the most dramatic edge events seen in the plasma periphery are the ELMs. Recent results using fast, high-resolution visible imaging confirm the hypothesis that ELMs have both poloidal and toroidal structures (n ∼ 10 at q = 4), consistent with recent theories of the non-linear evolution of ballooning modes.

Chapter 6: H-Mode and Pedestal Physics in ASDEX Upgrade

Studies in ASDEX Upgrade of the phenomenology and scaling of the H-mode transition, of edge-localized modes (ELMs), and characterization of the H-mode edge transport barrier carried out in various experimental campaigns between 1996 and 2001 are described. The H-mode transition is recognized by formation of a radial electrical field at the plasma boundary, which in ASDEX Upgrade is detected by an associated increase of the neutral particle charge exchange flux from ripple trapped particles. A scaling for the critical local edge temperature for the H-mode transition threshold is found. Similarity experiments with ASDEX Upgrade and Joint European Torus plasmas for the H-mode transition indicate that the H-mode transition can be obtained at the same values of dimensionless parameters ρ*, ν*, and β at the plasma edge, indicating that the threshold scaling is normally not dominated by atomic physics processes. Energy losses due to ELMs are examined. Different types of ELMs can be obtained, depending on plasma edge temperature and magnetics configuration. An interesting regime is the type II ELMy H-mode for configurations near double null, where the peak heat flux to the target is much reduced compared to large type I ELMs. High-resolution Thomson scattering measurements show that the edge transport barrier width in ASDEX Upgrade shows only weak variations, while the pedestal top electron pressure and pressure gradient strongly depend on the plasma current, or value of Bt/q95.

Steady-state convection and fluctuation-driven particle transport in the H-mode transition.

Large-scale steady-state convection is found to dominate the particle transport just inside the last closed flux surface (LCFS) in Ohmic discharges in the CCT tokamak. Near the limiter radius and in the scrape-off layer, fluctuation-induced transport is prevalent. At the L-H transition, the convection pattern near the LCFS is disrupted and a more poloidally symmetric, near-sonic plasma flow develops. Convective and turbulent particle transport are reduced across the entire edge region, resulting in the formation of the H-mode edge transport barrier.

Modifications in turbulence and edge electric fields at the L–H transition in the DIII-D tokamak

The L to H transition in the DIII-D tokamak [Plasma Physics and Controlled Nuclear Fusion Research, 1986 (IAEA, Vienna, 1987), Vol. I, p. 159] is associated with two clear signatures: edge density fluctuations are abruptly suppressed (in ≊100 μsec), while the edge poloidal rotation velocity vθ increases, implying that the radial electric field Er becomes more negative. Detailed new spectroscopic profile measurements show that the changes in vθ and Er generate a region of sheared electric field and poloidal flow of width ≊3–5 cm. This region develops simultaneously with, and has the same spatial extent as, the edge fluctuation suppression zone as measured using a reflectometer system. Furthermore, the radial extent of the shear and fluctuation suppression zones encompass the location of the H-mode edge transport barrier. These observations are consistent with recent theoretical models of the L–H transition, and a comparison with these theories is presented. Data are also presented on the evolution of edge parameters and density fluctuations after the transition: the shear and fluctuation suppression layers are maintained for the duration of the quiescent H-mode phase, while relative density fluctuation levels decrease and interior plasma confinement gradually improves. Precursors to several different types of edge localized mode (ELMs) are also discussed.