Divertor & SOL Physics: EX/4 & TH/3
- Earl Marmar (USA)
Mr Guy Matthews (UK)
10/15/14, 4:40 PM
Our priority for the 2013 JET campaigns was to provide relevant data for the ITER decision on whether to initially install a full tungsten divertor rather than a design with carbon at the strike points. A key element of this was an experiment using a specially modified divertor module which was used to study the characteristics and impact of ELM induced melting of bulk tungsten on JET...
702. Toward an Emerging Understanding of ELM Dynamics and Energy Loss Scaling & Advanced Divertor Analysis of HL-2M
Mr Guoyao Zheng (China)
10/15/14, 5:00 PM
A We report on the latest BOUT++ studies in the past 2 years which: (1) illustrate the consistent collisionality scaling of ELM energy losses with ITPA multi-tokamak database; (2) a new nonlinear criterion for predicting the onset of ELMs. We show that for an ELM crash to occur, the coherence time of the relative phase between potential and pressure perturbations must be long enough to allow...
171. First-Principle Theory-Based Scaling of the SOL Width in Limited Tokamak Plasmas, Experimental Validation, and Implications for the ITER Start-up
Mr Paolo Ricci (Switzerland)
10/15/14, 5:20 PM
The steady-state heat load onto the plasma facing components of tokamak devices depends on the SOL width, which results from a balance between plasma outflowing from the core region, turbulent transport, and losses to the divertor or limiter. Understanding even the simplest SOL configurations, like circular limited plasmas, is a stepping-stone towards more complicated configurations, with...
469. Assessment of Scrape-off Layer Simulations with Drifts against L-Mode Experiments in ASDEX Upgrade and JET
Ms Leena Aho-Mantila (Finland)
10/15/14, 5:40 PM
Recent results of validating scrape-off layer simulations with drifts are summarized, based on detailed comparisons between 2D SOLPS5.0 fluid code solutions and L-mode experiments in the full-metal devices ASDEX Upgrade and JET. The effects of drifts in various divertor power exhaust scenarios are analysed in extensively characterized discharges, in which the levels of deuterium fuelling,...
573. Near-Field Physics of Lower-Hybrid Wave Coupling to Long-Pulse, High Temperature Plasmas in Tore Supra
Mr Marc Goniche (France)
10/15/14, 6:00 PM
Interaction of radio-frequency waves with the edge plasma of tokamaks from which the wave is launched is now well recognized for waves in the Ion Cyclotron Range of Frequency (ICRF) but also in the range of Lower Hybrid Current Drive (LHCD) frequencies. A dynamic Stark spectroscopic measurement was carried out near a Tore Supra LHCD antenna, demonstrating that indeed the electric field...
471. Fuel Retention and Erosion of Metallic Plasma-Facing Materials under the Influence of Plasma Impurities
Mr Arkadi Kreter (Germany)
10/15/14, 6:20 PM
The fuel retention and the lifetime of plasma-facing components are critical factors potentially limiting the availability of a magnetic fusion reactor. It is necessary to test how plasma-facing materials perform with respect to hydrogen retention and erosion under the realistic mixed species plasma conditions including impurities like helium and argon. This contribution summarizes the...