Angular momentum transport studics were conducted for nearly stationary situations of about 50 neutral-beam-heatcd ASDEX discharges undcr a variety of experimental conditions. Comparison of the confinement times of angular momentum and energy reveals close similarities bctwcen thermal and prrpendicuiar momentum transport. Scaling kdWS arc derived for the dependence of the central rotation speed, the momentum confinemcnt time and the radially-averaged momenlum diffusivity from the main experimental parameters of L-mode discharges. A well-devcloprd isotope eKecl, significant power degiddiction and a favourable currcnt scaling are found to be characlrristic features of momentum confinement. Thc L-mode results are compared with the momentum transport behaviour during thc improved confinement phase of H-mode, pellct-fuellcd and counter-NI discharges. For the H-modc, thc confinement improvement is comparable for momentum snd energy. The peakcd density profile scenarios exhibit a considerably more pronounced increase in momentum confinement than in cnergy confinement.

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The results of divertor studies on ASDEX Upgrade, at currents of up to 1.2 MA and heating powers up to 10 M W are described, with emphasis on the ELMy H-mode. The spatial and temporal characteristics of their heat load, and the simulation of ELMs by a time-dependent scrape-off layer code are described. High gas puff rata were found to lead to a large increase in divertor neutral pressure, at modest changes in %, and to a strong reduction in timeaveraged power flow and complete detachment from both target plates in between ELMs. Using pre-programmed puffs of neon and argon, the radiative power losses could be raised to 75% of the heating power, in H-regime discharges, and the regime of enhanced divertor neutral pressure was found also to lead to an improved pumping of recycling impurities. 1.Introduction:ASDEX Upgrade is a mid-size tokamak w i t h non-circular cross-section (major radius R, , = 1.625m, horizontal minor radius a = 0.5 m, elongation b/a = 1.6), purpose-designed as a poloidal divertor device (Figure 1). Further distinguishing features of it are the poloidal field coils placed outside the toroidal ones, and the presence of a saddle coil ("PSL" .. pssive Stabilising loop) inside the vacuum vessel for stabilising the vertical displacement instability. Together, these two features provide a relatively large space between the vacuum vessel and the X-point of the poloidal field lines, although the present divertor configuration, selected to optimise the heat load distribution, places the target plates relatively close to the x-point.

The sawtooth oscillations in tokamak discharges with Ohmic and neutral-beam heating could be suppressed when a large part of the plasma current was driven by lower hybrid waves (IHF/IP ^ 0.5). The stabilization is due to a flattening of the current profile j(r) and an increase of q(Q) above 1. Higher central electron temperatures are obtained with neutral-beam heating if the sawteeth are stabilized. The increase in total energy content in this case was 30% higher than in the presence of sawteeth.PACS numbers: 52.50.Gj, 52.35.Hr, 52.55.FaThe sawtoothlike oscillations usually observed in tokamaks have been considered for a long time as beneficial for stable and clean discharges. The timeaveraged power loss due to the sawtooth instability is small during Ohmic heating (OH) and is still not serious with additional neutral-beam heating. The situation has changed drastically with high-power ioncyclotron heating where giant sawteeth, with modulation of the central electron temperature by up to 50%, have been observed. 1 The resulting clamping of the central energy content could strongly impair core ignition in large fusion experiments. Methods for stabilization of the sawteeth are therefore of greatest interest.Application of lower hybrid (LH) waves may lead to the suppression of sawteeth in OH discharges. 2 * 3 On the ASDEX tokamak we have studied the influence of LH waves on the sawtooth period. Appropriate wave spectra and power requirements for suppression of sawteeth are discussed. Local current-profile measurements allowed clarification of the mechanism of sawtooth stabilization. Application to neutral-beam heating finally demonstrates the possible gain in total energy content in sawtooth-free discharges.The experiments reported here were performed in the divertor tokamak ASDEX (i? = 165 cm, a = 40 M). LH waves were injected with powers of up to F LH = 1 MW and pulse lengths of up to 1.5 s. Details of the LH system and of the plasma behavior with LH heating and current drive are presented elsewhere. 4 " 6