Infrared measurements of the heat flux spreading under variable divertor geometries in TCV
Graph Chatbot
Chat with Graph Search
Ask any question about EPFL courses, lectures, exercises, research, news, etc. or try the example questions below.
DISCLAIMER: The Graph Chatbot is not programmed to provide explicit or categorical answers to your questions. Rather, it transforms your questions into API requests that are distributed across the various IT services officially administered by EPFL. Its purpose is solely to collect and recommend relevant references to content that you can explore to help you answer your questions.
Although ohmic H-modes have long been produced on the TCV tokamak and the effects of ELMs at the divertor targets studied in some detail [1], no attempt has yet been made to model the scrape-off layer (SOL) in these plasmas. This contribution describes det ...
Heat loads on the JET MarkIIHD divertor are measured by IR thermography in high triangularity plasmas with edge conditions of advanced tokamak scenarios (AT). AT scenarios operate at low density (n(e,av) < 5 x 10(19) m(-3) at JET) to maximise the non induc ...
The substitution of CFC refrigerants in refrigeration systems, heat pumps and organic Rankine cycles, requests a good knowledge of the heat transfer and pressure drop properties of substitute fluids. A contribution to this international effort is proposed ...
Magnetic diagnostics for the new generation fusion reactor “ITER” are required to be extremely reliable since they provide measurements essential for reactor operation and protection, plasma control and for measurement of several parameters fundamental to ...
The development of controlled thermonuclear fusion, a quasi-unlimited energy source suitable for large scale electricity production, is one of the main goals of plasma physics research. Among the directions explored to date, the use of toroidal devices cal ...
An overview is given of the wide range of activities contained within recent R&D being performed within Europe on In-vessel materials for structural, heat sink and plasma facing purposes for ITER. The effect of creep-fatigue interaction on the fatigue life ...
Experimental observations and some preliminary results from B2-Eirene code modelling of divertor detachment in the TCV tokamak are reported, with emphasis on the aspects of this detachment related to divertor geometry. The contribution is restricted to deu ...
This paper describes experiments performed on JET over the past two years dedicated to characterizing ELM-averaged power exhaust (based on time-averaged divertor power deposition profiles), with an emphasis on unfuelled, Type-I ELMy H-mode. Radial energy t ...
The transient pulses of heat and particles arriving at the divertor target plates as a consequence of upstream ELM activity have been characterised at JET using an array of target embedded Langmuir probes in the MkIIGB-SRP divertor. High temporal and spati ...
An analysis of the effect of magnetic geometry on heat flux in a wide range of single null diverted discharge configurations with 1.5 < κ(95) < 2.2, 0.2 < δ(95) < 0.45 suggests that elongation is beneficial for confinement. If heat diffusivitie ...