Publications de Kamil Sedlák | EPFL Graph Search

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A low-AC loss Rare-earth barium copper oxide (REBCO) cable, based on the VIPER cable technology has been developed by commonwealth fusion systems for use in high-field, compact tokamaks. The new cable is composed of partitioned and transposed copper ‘petal ...

Particle accelerators foresee the use of Nb3Sn in the next generation of dipole magnets. A common design strategy is to grade the coil, i.e., to optimize the quantity of superconductor in the turns with respect to the magnetic field intensity. As a consequ ...

The pre-conceptual design phase of the EU DEMO magnet system relies on mechanical, electromagnetic and thermal-hydraulic analyses of different conductor designs for the Toroidal Field (TF) coils, the Poloidal Field (PF) coils and the Central Solenoid (CS) ...

The need of full transposition of the current carrying elements (strands) in large cables is frequently retained as top design criterion for conductors operating in pulsed mode. However, when the transposition error, i.e., the inductance difference among t ...

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 activities undertaken ...

EDIPO 2 (the upgraded EDIPO test facility) will provide a unique testbed for superconducting cables for fusion magnets,accelerators, and other applications. Compared to the previous magnet assembly, the magnetic field is enhanced from 12.35 T to 15 T, the ...

The European Dipole (EDIPO) test facility is undergoing a major upgrade of its magnet assembly, which will provide ground for testing both fusion and high-energy physics superconducting samples at variable temperature and with a background field of 15 T. I ...

A promising way to realize controlled nuclear fusion involves the use of magnetic fields to control and confine the hot plasma configuration. This approach requires superconductor magnets operating above 15 T for the next generation of fusion devices. Due ...

The present work is performed within the framework of the EUROfusion DEMO project. Previously, it was demonstrated that for a maintained magnetic flux the use of HTS conductors at highest magnetic field in a layer-wound CS coil would allow the reduction of ...

Quench protection is a critical issue for magnet using high-temperature superconducting (HTS) materials such as REBCO. For cable-in-conduit conductor (CICC) with twisted REBCO tapes, which is considered for high-current HTS conductor for fusion magnet, the ...

The Swiss Plasma Center (SPC) has developed a layout of Toroidal Field (TF) coil for EUROfusion DEMO tokamak, based on the reference tokamak baseline of 2015. Each TF coil winding pack is wound with graded Nb3Sn conductors and consists of 12 single layers, ...

The coupling currents loss for fusion conductors is frequently assessed applying a sinusoidal field sweep of fixed, small amplitude and variable frequency. From the initial slope of the loss curve, the coupling loss time constant is derived and applied in ...

The European DEMOnstration Fusion Power Plant (EU-DEMO) is being designed as an intermediary stage between the ITER experimental reactor and future commercial fusion power plants. The EU-DEMO is based on the tokamak concept with a fully superconducting mag ...

The Divertor Tokamak Test (DTT) facility is a challenging high-field and compact tokamak, currently under construction at the Frascati ENEA Research Center. Its purpose is to significantly contribute to the exploration, design and assessment of systems int ...

The Cold Mass Support (CMS) is a basic structural component of the feeder system of the EU DEMO tokamak. The function of this structural element is not only to provide support to the containment duct - wiring the cryogenic lines, electrical bus bars and in ...

In this study, we present a technical and economic assessment of high-current HTS bus bars for primary use in fusion reactors. Our objective is to verify the technical feasibility of such conductors and, for this purpose, we carry out a conceptual design o ...

High Temperature Superconductors (HTS) are promising materials for future fusion magnets. One of HTS conductors' main issues is the quench protection: the quench develops much slower than in LTS, delaying the quench detection by voltage monitoring and caus ...

The Central Solenoid (CS) is at the core of the EU DEMO tokamak, and has a strong impact on the tokamak design and the overall machine size. By ramping its current, the CS generates a change of magnetic flux, which initiates the plasma, and induces and con ...

The EUROfusion DEMO is being designed as the fusion machine to be built after ITER. During the preconceptual phase, several design options are investigated by theoretical analyses as well as tests on newly developed conductor prototypes. One design option ...

In a typical Nb3Sn cable for fusion applications, the knowledge of the strain state of Nb3Sn filaments is important to predict and interpret the conductor performance in operation. Amongst the relevant strain sources, the predominant is the thermal strain ...

Kamil Sedlák

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Development of a high current density, high temperature superconducting cable for pulsed magnets

Diffusion-Bonding Between Strands and Modeling of Splices of Nb3Sn Rutherford Cables

Parametric study and optimization of the cryo-magnetic system for EU DEMO at the pre-conceptual design phase

Performance Comparison of Cables With Partial Transposition

Performance review of the joints for the ITER poloidal field coils

Progress on the Design of the 15 T Magnet of the EDIPO Test Facility

Preliminary design of the pressure relief system of the EDIPO 2 helium vessel

Performance of the First 80-kA HTS CICC for High-Field Application in Future Fusion Reactors

Hybrid HTS-Nb3Sn-NbTi DEMO CS coil design optimized for maximum magnetic flux generation

Quench Simulation of REBCO Cable-in-Conduit Conductor With Twisted Stacked-Tape Cable

Inter-Layer Joint of Nb3Sn React&Wind Cables for Fusion Magnets

A new test method of AC loss assessment for fusion conductors

Quench analysis of the DEMO CS1 coil

Characterization of the Full-Size Superconducting ASG Joint Designed for the DTT Toroidal Field Coils

Preliminary design of the cold mass supports for the EU DEMO feeders

Technical and economic feasibility study of high-current HTS bus bars for fusion reactors

Upgrade and Commissioning of the SULTAN Facility to Host Quench Experiments on HTS High Current Conductors

Parametric Studies of the EU DEMO Central Solenoid

AC Loss Measurement of the DEMO TF React&Wind Conductor Prototype No. 2

Experimental Assessment of the Thermal Strain Distribution in Nb3Sn React & Wind Conductor Prototype for European DEMO