Simulation of the flow-reversal effect in dual-channel CICC for ITER
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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 ...
In the International Thermonuclear Experimental Reactor (ITER) toroidal field model coil (TFMC) the experimental evaluation of the superconducting critical properties will only be possible by heating the helium upstream of the inner joint. In this coil onl ...
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 JET experimental campaign has focused on studies in support of the ITER physics basis. An overview of the results obtained is given for the reference ELMy H mode and advanced scenarios, which in JET are based on internal transport barriers. JET studies ...
The reduction of static heat load in superconducting magnet systems is of great importance because of reduction of refrigeration power and operational costs. The major elements that determine the heat load are the current leads. The use of high temperature ...
Two short length samples have been prepared and tested in SULTAN to benchmark the performance of high current density, advanced Nb3Sn strands in the large cable-in-conduit conductors (CICC) for ITER. The cable pattern and jacket layout were identical to th ...
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 ...
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 ...
Within the framework of the European Fusion Programme a FSJS has been designed and manufactured by European Industry using PF coil NbTi superconductor manufactured and supplied by the Russian Federation as part of the R&D for the PF Conductor Insert (PFCI) ...