S. Jachmich

Disruption mitigation by massive gas injection in JET

Disruption mitigation is mandatory for ITER in order to reduce forces, to mitigate heat loads during the thermal quench and to avoid runaway electrons (REs). A fast disruption mitigation valve has been installed at JET to study mitigation by massive gas injection. Different gas species and amounts have been investigated with respect to timescales and mitigation efficiency. We discuss the mitigation of halo currents as well as sideways forces during vertical displacement events, the mitigation of heat loads by increased energy dissipation through radiation, the heat loads which could arise by asymmetric radiation and the suppression of REs.

Plasma edge density and lower hybrid current drive in JET (Joint European Torus)

Externally launched lower hybrid (LH) waves do not propagate into the plasma core during operations of JET with radial profiles with relatively high density even at the periphery, approaching the condition necessary for ITER. Modelling results indicate that this problem would be caused by parametric instability (PI)-induced LH spectral broadening, which is expected to occur in the plasma edge and prevents the coupled LH power penetrating the plasma core. However, operation with relatively high electron temperature at the edge is expected to diminish the PI effect and extend the LH current drive effectiveness to reactor-grade high density plasmas, consistent with results obtained in other experiments.

Scaling of plasma turbulence suppression with velocity shear

The scaling of plasma turbulence, turbulent particle flux and cross-phase with shear in the edge of the TEXTOR-94 tokamak is obtained from measurements from fast scanning probes and compared with various existing analytical theories. It is found that the scaling can be expressed as a second order polynomial and that the cross-phase plays a key role in the suppression of particle flux. The variable rate of shear, kept below the value required to produce a low to high particle confinement transition, was obtained by changing, on a shot to shot basis, the voltage applied to an electrode introduced 4 cm into the plasma.

Demonstration of the role of flow shear in improved confinement

This paper summarizes the evidence for the role of shear flow in confinement improvement during electrode biasing experiments in TEXTOR-94: the transport barrier spatially overlaps the shear layer, the temporal causality is clearly established and the magnitude of shear at which the confinement occurs, agrees rather well with theoretical models. These results strengthen the conjecture that stabilization is a viable mechanism for improved confinement in tokamaks.

A 1D fluid model for the measurement of perpendicular flow in strongly magnetized plasmas

We show that it is possible to measure the parallel and the perpendicular flow in a strongly magnetized plasma, using a probe with two current collecting surfaces, inclined with respect to the magnetic field. The method is based on a one-dimensional fluid model, which we use to relate the unperturbed velocity components (the quantities we wish to measure) to the velocity and density perturbations caused by the probe. In this way we are able to establish a link between the electric saturation currents collected by the probe surfaces and the unperturbed velocity. The role of the cross-field transport into a pre-sheath of a collecting probe surface and the boundary condition for the flow velocity at the magnetic pre-sheath entrance are also investigated.

Experimental investigations on the role of flow shear in improved confinement

Edge transport and confinement changes induced by radial electric fields, externally imposed in TEXTOR-94 by means of electrode biasing, were investigated. The edge profiles of the electric field were measured continuously by a specially developed nine-tip Langmuir probe, thus allowing the study of the relative spatial and temporal dynamics of and its radial gradient and possible ensuing transport changes. A particle transport barrier is found to be built up as the electric field gradient increases, thus strengthening the conjecture that stabilization is a viable mechanism for improved confinement in tokamaks.

Strike-point splitting induced by external magnetic perturbations: Observations on JET and MAST and associated modelling

General formula describing both the divertor strike point splitting and width of magnetic islands created by resonant magnetic perturbations (RMPs) in a poloidally diverted tokamak equilibrium is derived. Under the assumption that the RMP is produced by coils at the low-field side such as those used to control edge localized modes (ELMs) it is demonstrated that the width of islands on different magnetic surfaces at the edge and the amount of divertor splitting are related to each other. Explanation is provided of aligned maxima of the perturbation spectra with the safety factor profile – an effect empirically observed in models of many perturbation coil designs.

Integrated scenario with type-III ELMy H-mode edge: extrapolation to ITER

One of the most severe problems for fusion reactors is the power load on the plasma facing components. The challenge is to develop operation scenarios, which combine sufficient energy confinement with benign heat loads to the plasma facing components. The radiative type-III ELMy H-mode seems a possible solution for such an integrated ITER scenario. Nitrogen seeded type-III ELMy H-modes for the standard inductive scenario and the high beta stationary hybrid scenario are investigated with respect to their transient and steady-state power fluxes to the divertor, confinement properties, edge operational space, core operational space, plasma purity and MHD behaviour. A large database of highly radiative type-III ELMy H-modes on JET is used for extrapolations to ITER. On this basis the transient heat load should be acceptable for ITER. It was found that the scaling of the confinement time with respect to the ion gyroradius is close to the gyro-Bohm scaling. Scalings with respect to the plasma collisionality suggest that the confinement will be good enough for an ITER scenario at 17 MA with a power amplification factor (Q) of 10 and might be marginally good enough for a Q = 10 scenario at 15 MA. Those extrapolations are supported by simulations with an integrated core/edge model COREDIV. In addition the hybrid scenario with type-III edge localized modes has been proven to have improved edge conditions without any modification of the central plasma current profile, indicating it is compatible with a high beta operation for a steady-state ITER Q = 5 scenario.

Active control of type-I edge localized modes on JET

The operational domain for active control of type-I edge localized modes (ELMs) with an n = 1 external magnetic perturbation field induced by the ex-vessel error field correction coils on JET has been developed towards more ITER-relevant regimes with high plasma triangularity, up to 0.45, high normalized beta, up to 3.0, plasma current up to 2.0 MA and q95 varied between 3.0 and 4.8. The results of ELM mitigation in high triangularity plasmas show that the frequency of type-I ELMs increased by a factor of 4 during the application of the n = 1 fields, while the energy loss per ELM, ΔW/W, decreased from 6% to below the noise level of the diamagnetic measurement (<2%). No reduction of confinement quality (H98Y) during the ELM mitigation phase has been observed. The minimum n = 1 perturbation field amplitude above which the ELMs were mitigated increased with a lower q95 but always remained below the n = 1 locked mode threshold. The first results of ELM mitigation with n = 2 magnetic perturbations on JET demonstrate that the frequency of ELMs increased from 10 to 35 Hz and a wide operational window of q95 from 4.5 to 3.1 has been found.

Mitigation of type-I ELMs with n?=?2 fields on JET with ITER-like wall

Recently, strong mitigation of Type-I Edge Localized Modes (ELMs) has been observed with application of the n = 2 field in high collisionality (nu^*_e=2.0) H-mode plasma on JET tokamak with ITER-like wall. In this experiment, the EFCC power supply system has been enhanced with a coil current up to 88kAt (twice than before). With an n = 2 field, the large type-I ELMs with frequency of ~ 45 Hz was replaced by the high frequency (few hundreds Hz) small ELMs. No density pump-out was observed during an application of the n = 2 field. The influence of the n = 2 field on the core and the pedestal electron pressure profiles is within the error bar and it can be neglected. During the normal type-I ELM H-mode phase, the maximal surface temperature (Tmax) on the outer divertor plate was overall increasing and associated with large periodical variation due to the type-I ELMs. However, during an application of the n = 2 field, Tmax was saturated and has only small variation in few degrees due to the small mitigated ELMs. Splitting of the outer strike point has been observed during the strong mitigation of the type-I ELMs.