Free-Boundary Simulations of ITER Advanced Scenarios
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.
The transport of particles in magnetically confined plasmas is of great importance for the development of fusion energy. It will determine techniques for fuelling, for controlling impurity concentrations and for the removal of the alpha particles produced ...
The condition of the latest version of the ELMy H-mode database has been re-examined. It is shown that there is bias in the ordinary least squares regression for some of the variables. To address these shortcomings three different techniques are employed: ...
The Poloidal Field (PF) coils of the International Thermonuclear Experimental Reactor (ITER) are designed using of NbTi cable-in-conduit conductors carrying a current up to 45 kA. Each PF coil consists of several modules Wound in double pancakes. Joints co ...
Advanced tokamak regimes obtained in ASDEX Upgrade, DIII-D, FF-U, JET, JT-60U, TCV and Tore Supra experiments are assessed both in terms of their fusion performance and capability for ultimately reaching steady-state using data from the international inter ...
A semi-Lagrangian code for the solution of the electrostatic drift-kinetic equations in straight cylinder configuration is presented. The code, CYGNE, is part of a project with the long term aim of studying microturbulence in fusion devices. The code has b ...
Within the framework of the R&D studies for the International Thermonuclear Experimental Reactor (ITER) project, the first full size NbTi conductor sample was fabricated industrially and tested in the SULTAN facility (Villigen, Switzerland). This sample (P ...
The ITER toroidal field model coil (TFMC) has been tested in the TOSKA facility of FzK. The racetrack coil, which uses a circular Nb3Sn cable-in-conduit conductor, is equipped with external resistive heaters for the evaluation of the current sharing temper ...
The large physical size of the JET tokamak, its heating systems and diagnostics, and its capability to operate with full deuterium-tritium (D-T) plasmas, including high-power tritium neutral beam injection (NBI), give it unique possibilities in fast partic ...
Industry benefits in a number of different ways from the research and technology activities of the European Fusion Programme, overseen by the European Commission. These benefits range from: winning contracts to supply equipment and services to fusion labor ...
The ITER toroidal field model coil (TFMC) was designed, constructed and tested by the European Home Team in the framework of the ITER research and development program of the Engineering Design Activities (EDA). The project was performed under the leadershi ...
