Impact of mechanical and thermal cycles at different operating conditions on the ITER toroidal field coil conductor performance
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.
An improved joint layout layout is proposed for the electrical connections of the large Nb3Sn cable-in-conduit conductors for the Central Solenoid and Toroidal Field coils of ITER, International Thermonuclear Experimental Reactor. The driving design criter ...
A section of the ITER (International Thermonuclear Experimental Reactor) conductor, left from the winding of the Central Solenoid Model Coil, was tested for stability under pulsed transverse field in the SULTAN facility, at background field up to 11 T and ...
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 ...
Divertor detachment is currently assumed to be a fundamental pre-requisite for the successful operation of future fusion reactors. Only by partially detaching the divertor in the regions of highest power flux density can high performance tokamak operation ...
The use of high temperature superconductor (HTS) materials in future fusion machines could increase the efficiency drastically, but strong boundary conditions exist. To outline the prospects, challenges and problems, first the benefit of using HTS material ...
SULTAN, the world wide unique, high field, large bore test facility. has been built as European contribution to the development program for ITER, The facility has primarily been devoted to the qualification of full-size cable-in-conduit-conductors (CICC) f ...
Within the R&D program on the International Thermonuclear Experimental Reactor (ITER) Poloidal Field (PF) coils, a full size conductor sample was tested in the SULTAN facility (CRPP Villigen, Switzerland). This sample is composed of two straight ITER-like ...
Prototype conductors for the ITER magnets have been tested extensively in the SULTAN facility at CRPP in the last decade. The in-depth characterization of the high current carrying conductors provided a valuable feedback in the design, with performance opt ...
The preparative experimental and analysis work as well as the code development for testing the ITER (International Thermonuclear Experimental Reactor) TFMC, one of the large projects of the ITER research and development programme, is described. The expecte ...
The experiments of Cable-in conduit conductor (CICC) short samples with high proportion of segregated copper strands have been carried out in SULTAN facility last September. These experiments aimed to investigate transient stability and AC losses of CICC c ...
