A. Vostner
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View article: Coupling and Hysteresis Loss Measurements on the ITER CS Module #4
Coupling and Hysteresis Loss Measurements on the ITER CS Module #4 Open
The fourth CS Module (CSM#4) of the ITER Central Solenoid was tested in November/December 2022 at the premises of General Atomics, Poway, US. During the measurement campaign, the CSM#4 was submitted to dumps of the transport current from d…
Research and development of copper joint for ITER In-Vessel Coils Open
The ITER In-Vessel Coils (IVCs) are crucial components of the Tokamak fusion reactor. They are located within the vacuum vessel (VV) behind the blanket shield modules and are responsible for compensating for fast perturbations of the plasm…
View article: Performance review of the joints for the ITER poloidal field coils
Performance review of the joints for the ITER poloidal field coils Open
For large scale magnets wound with cable-in-conduit conductors, the safe operation of the joints is of paramount importance to guarantee adequate reliability and stability margin of the whole magnet. For this reason, during the R&D activit…
View article: Multiphysics Model of Quench for the ITER Central Solenoid
Multiphysics Model of Quench for the ITER Central Solenoid Open
The ITER Central Solenoid (CS), the backbone of the ITER magnet system, is composed of 6 modules, each made of 40 pancakes, for a total conductor length of about 36 km. More than 4 km of pipes, about 30 bypass or control valves, the heat e…
View article: <i>T</i> <sub>cs</sub> degradation of ITER TF samples due to fast current discharges
<i>T</i> <sub>cs</sub> degradation of ITER TF samples due to fast current discharges Open
Direct current tests performed in the past on the conductor samples of the toroidal field (TF) ITER coils revealed degradation of current sharing temperature, T cs . The degradation progresses with repetitive electromagnetic loading, and a…
Overview of verification tests on AC loss, contact resistance and mechanical properties of ITER conductors with transverse loading up to 30 000 cycles Open
The ITER magnet system uses cable-in-conduit conductor (CICC) technology with individual strands twisted in several stages resulting in a rope-type cable, which is inserted into a stainless steel conduit. The combination of high current (u…
View article: Statistical analysis of the Nb<sub>3</sub>Sn strand production for the ITER toroidal field coils
Statistical analysis of the Nb<sub>3</sub>Sn strand production for the ITER toroidal field coils Open
The ITER toroidal field (TF) strand procurement initiated the largest Nb3Sn superconducting strand production hitherto. The industrial-scale production started in Japan in 2008 and finished in summer 2015. Six ITER partners (so-called Dome…
Investigation of RF Nb-Ti PF 1&6 Coils Conductor Performances in the SULTAN Test Facility Open
This paper summarizes the work on the manufacturing and testing of conductor samples for ITER poloidal field 1&6 coils. The work was carried out by the IO and multiple institutions in the EU, Switzerland and Russia. Five samples were manuf…