T. S. Pedersen

Plans for the first plasma operation of Wendelstein 7-X

Wendelstein 7-X (W7-X) is currently under commissioning in preparation for its initial plasma operation phase, operation phase 1.1 (OP1.1). This first phase serves primarily to provide an integral commissioning of all major systems needed for plasma operation, as well as systems, such as diagnostics, that need plasma operation to verify their foreseen functions. In OP1.1, W7-X will have a reduced set of in-vessel components. In particular, five graphite limiter stripes replace the later foreseen divertor. This paper describes the expected machine capabilities in OP1.1, as well as a selection of physics topics that can be addressed in OP1.1, despite the simplified configuration and the reduced machine capabilities. Physics topics include the verification and adjustment of the magnetic topology, the testing of the foreseen plasma start-up scenarios and the feed-forward control of plasma density and temperature evolution, as well as more advanced topics such as scrape-off layer (SOL) studies at short connection lengths and transport studies. Plasma operation in OP1.1 will primarily be performed in helium, with a hydrogen plasma phase at the end.

Setup and initial results from the magnetic flux surface diagnostics at Wendelstein 7-X

Wendelstein 7-X is an optimized stellarator with superconducting magnetic field coils that just started plasma operation at the Max-Planck-Institut fur Plasmaphysik (IPP) Greifswald. Utilizing the electron beam technique the first vacuum flux surface measurements were performed during the commissioning of the magnet system. For the magnetic configurations investigated so far the existence of closed and nested flux surfaces has been validated. All features of the configuration designed for the initial plasma operation phase, including a predicted island chain, were confirmed. No evidence on significant magnetic field errors was found. Furthermore, the effect of the elastic deformation of the non-planar coils was confirmed by the measurements.

Access to edge scenarios for testing a scraper element in early operation phases of Wendelstein 7-X

The edge topology of magnetic fusion devices is decisive for the control of the plasma exhaust. In Wendelstein 7-X, the island divertor concept will be used, for which the edge topology can change significantly as the internal currents in a plasma discharge evolve towards steady-state. Consequently, the device has been optimized to minimize such internal currents, in particular the bootstrap current [1]. Nonetheless, there are predicted pulse scenarios where effects of the remaining internal currents could potentially lead to overload of plasma-facing components. These internal currents are predicted to evolve on long time scales (tens of seconds) so their effects on the edge topology and the divertor heat loads may not be experimentally accessible in the first years of W7-X operation, where only relatively short pulses are possible. However, we show here that for at least one important long-pulse divertor operation issue, relevant physics experiments can be performed already in short-pulse operation, through judicious adjustment of the edge topology by the use of the existing coil sets. The specific issue studied here is a potential overload of the divertor element edges. This overload might be mitigated by the installation of an extra set of plasma-facing components, so-called scraper elements, as suggested in earlier publications. It is shown here that by a targeted control of edge topology, the effectiveness of such scraper elements can be tested already with uncooled test-scraper elements in short-pulse operation. This will allow an early and well-informed decision on whether long-pulse-capable (actively cooled) scraper elements should be built and installed.

A high-power spatial filter for Thomson scattering stray light reduction

The Thomson scattering diagnostic on the High Beta Tokamak-Extended Pulse (HBT-EP) is routinely used to measure electron temperature and density during plasma discharges. Avalanche photodiodes in a five-channel interference filter polychromator measure scattered light from a 6 ns, 800 mJ, 1064 nm Nd:YAG laser pulse. A low cost, high-power spatial filter was designed, tested, and added to the laser beamline in order to reduce stray laser light to levels which are acceptable for accurate Rayleigh calibration. A detailed analysis of the spatial filter design and performance is given. The spatial filter can be easily implemented in an existing Thomson scattering system without the need to disturb the vacuum chamber or significantly change the beamline. Although apertures in the spatial filter suffer substantial damage from the focused beam, with proper design they can last long enough to permit absolute calibration.

Status of the diagnostics development for the first operation phase of the stellarator Wendelstein 7-X

An overview of the diagnostics which are essential for the first operational phase of Wendelstein 7-X and the set of diagnostics expected to be ready for operation at this time are presented. The ongoing investigations of how to cope with high levels of stray Electron Cyclotron Resonance Heating (ECRH) radiation in the ultraviolet (UV)/visible/infrared (IR) optical diagnostics are described.

Recent status of A Positron-Electron Experiment (APEX)

A project is underway to generate an electron-positron plasma by using the NEPOMUC positron source at the FRM-II facility combined with a multicell-type Penning trap (PAX) and a superconducting dipole magnetic field trap (APEX). In the APEX project, proof-of principle experiments are proposed for the development of efficient injection methods of positrons by using a small dipole magnetic field trap with a permanent magnet. Plans for the APEX project and its recent status are reported.

Key results from the first plasma operation phase and outlook for future performance in Wendelstein 7-X

The first physics operation phase on the stellarator experiment Wendelstein 7-X was successfully completed in March 2016 after about 10 weeks of operation. Experiments in this phase were conducted with five graphite limiters as the primary plasma-facing components. Overall, the results were beyond the expectations published shortly before the start of operation [Sunn Pedersen et al., Nucl. Fusion 55, 126001 (2015)] both with respect to parameters reached and with respect to physics themes addressed. We report here on some of the most important plasma experiments that were conducted. The importance of electric fields on global confinement will be discussed, and the obtained results will be compared and contrasted with results from other devices, quantified in terms of the fusion triple product. Expected values for the triple product in future operation phases will also be described and put into a broader fusion perspective.

Synthetic plasma edge diagnostics for EMC3-EIRENE, highlighted for Wendelstein 7-X

Interpretation of spectroscopic measurements in the edge region of high-temperature plasmas can be a challenge since line of sight integration effects make direct interpretation in terms of quantitative, local emission strengths often impossible. The EMC3-EIRENE code-a 3D fluid edge plasma and kinetic neutral gas transport code-is a suitable tool for full 3D reconstruction of such signals. A versatile synthetic diagnostic module has been developed recently which allows the realistic 3D setup of various plasma edge diagnostics to be captured. We highlight these capabilities with two examples for Wendelstein 7-X (W7-X): a visible camera for the analysis of recycling, and a coherent-imaging system for velocity measurements.

W7-X commissioning: Progress and lessons learned for future devices

Commissioning of the stellarator Wendelstein 7-X (W7-X) at the Max-Planck-Institute for Plasma Physics in Greifswald, Germany, started in April 2014, simultaneously with final assembly work. First, individual components and their local control systems were put into operation. The subsequent cryostat evacuation was then the first large system commissioning. Before the final room temperature vacuum of ≈10-4 mbar was reached, the electrical insulation of the superconducting coil system had been successfully tested with voltages up to 2.5 kV under Paschen conditions. Partly in parallel, all power supplies, the trim and most of the control coils, CoDaC, and the diagnostic as well as ECRH - as far as possible without plasma - were put into operation. Next major achievements were the magnet system cool-down to 3.8 K, and the first operation of individual coil groups. Evacuation of the plasma vessel has been delayed due to leaks at vacuum pump manifold flanges which are currently being repaired. The large system commissioning steps and problems encountered as well as remedies are described, and an outlook for remaining work to be done until the first plasma is given.

Influence of the resonant magnetic perturbations on transport in the Large Helical Device

The purpose of this study is the investigation of the non-linear plasma response of transport due to stochastic effects. On the Large Helical Device, perturbation coils create a resonant magnetic perturbation (RMP) with the m/n?=?1/1 and 2/1 Fourier components. Depending on the plasma conditions, the perturbation either enhances or heals the natural m/n?=?1/1 magnetic island. For the case of an amplified island the enhanced heat and particle transport across the island causes a rather significant reduction in the confinement. For a healed island, there is a small decrease in beta with increasing perturbation current. These changes coincide with an increasing width of the open stochastic volume at the plasma edge near the x-point. Systematic experiments are performed, changing the amplitude of the perturbation linearly with IRMP in the range from 0 to 2.7?kA. Two scenarios are investigated: first, the discharge is ramped up with an external perturbation already superimposed on the main magnetic field. Second, the external perturbation is applied to the plasma already ignited (similar to experiments with RMPs in tokamaks). As will be shown, there is a clear difference in the size of the 1/1 island and the dependence of ne and Te on the perturbation when comparing these two scenarios. A hysteresis is observed up to a certain amplitude of the external perturbation. The particle transport and confinement are affected substantially in the discharges with a pre-existing magnetic perturbation. Interestingly, a global reduction in Te and ne is observed above a certain value of perturbation current in both cases. However, for the same island width, the plasma reacts differently to the applied perturbation depending on the direction of the ramp. For ramp-downs, we observe steeper electron density and temperature gradients, which leads to better plasma performance.