Publication

Test Result of a Full-Size Nb3Sn Conductor Developed for the ITER TF Coils

Publications associées (34)

Graph Chatbot

Chattez avec Graph Search

Posez n’importe quelle question sur les cours, conférences, exercices, recherches, actualités, etc. de l’EPFL ou essayez les exemples de questions ci-dessous.

AVERTISSEMENT : Le chatbot Graph n'est pas programmé pour fournir des réponses explicites ou catégoriques à vos questions. Il transforme plutôt vos questions en demandes API qui sont distribuées aux différents services informatiques officiellement administrés par l'EPFL. Son but est uniquement de collecter et de recommander des références pertinentes à des contenus que vous pouvez explorer pour vous aider à répondre à vos questions.

Connectez-vous pour utiliser Chat avec Graph Search

AC loss and electrical resistance of the RW3 diffusion-bonded joint

Vincenzo D'Auria

For the European DEMO fusion reactor, several options of the Toroidal Field (TF) coil design were proposed. The winding of the TF coil option 1 is based on React&Wind (RW), Nb3Sn, graded conductors in order to optimize the amount of superconductor accordin ...

2023

Impact of Hysteresis Losses in Hybrid (HTS-LTS) Coils for Fusion Applications

Davide Uglietti

Several conductor designs featuring High Temperature Superconducting (HTS) stacked tapes for fusion coils are being proposed. These conductors are planned to operate in time-varying magnetic field and current; thus, the estimation of AC losses is fundament ...

IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC2023

Experimental study of stability, quench propagation and detection methods on 15 kA sub-scale HTS fusion conductors in SULTAN

Pierluigi Bruzzone, Kamil Sedlák, Nikolay Bykovskiy, Ortensia Dicuonzo

High-temperature superconductors (HTSs) enable exclusive operating conditions for fusion magnets, boosting their performance up to 20 T generated magnetic fields in the temperature range from 4 K to 20 K. One of the main technological issues of HTS conduct ...

IOP Publishing Ltd2023

The aim of this thesis is to investigate the mechanical and thermal behaviour of HTS coated conductor cables for EUROfusion DEMO magnets.One of the issue in large HTS magnets is the safety against a quench. A quench is a sudden thermal runway in which the ...

EPFL2022

The DEMO magnet system - Status and future challenges

Pierluigi Bruzzone, Kamil Sedlák, Davide Uglietti, Federica Demattè, Rainer Wesche, Roberto Guarino, Mithlesh Kumar, Vincenzo D'Auria, Ortensia Dicuonzo, Chiara Frittitta

We present the pre-concept design of the European DEMO Magnet System, which has successfully passed the DEMO plant-level gate review in 2020. The main design input parameters originate from the so-called DEMO 2018 baseline, which was produced using the PRO ...

2022

T-cs degradation of ITER TF samples due to fast current discharges

Pierluigi Bruzzone, Kamil Sedlák, Boris Stepanov

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 also with thermal c ...

IOP PUBLISHING LTD2021

Thermal-hydraulic analysis of the upgraded EU-DEMO CS1 coil

The European DEMOnstration Fusion Power Plant (EU-DEMO) is planned to be an intermediate step between ITER experimental reactor and a commercial fusion power plant, which should demonstrate feasibility of grid electricity production at a level of several h ...

SPIE-INT SOC OPTICAL ENGINEERING2019

Frequency Response of Electric and Magnetic Fields of Overhead Conductors With Particular Reference to Axial Electric Field

Complete electric and magnetic field solutions of an overhead conductor above a lossy earth are derived in this letter, and “mode transition” from a low-frequency quasi-transverse electromagnetic (TEM) to a high-frequency transverse Magnetic (TM) mode has ...

2018

Overview of Performance Test of Korean CICCs for ITER TF Magnet

Pierluigi Bruzzone, Boris Stepanov

The Korean Domestic Agency (KODA) for the International Thermonuclear Experimental Reactor (ITER) project has taken the responsibility of the procurement of cable-in-conduit conductors for the ITER toroidal field magnet. While procuring 27 conductor unit l ...

Ieee-Inst Electrical Electronics Engineers Inc2016

, , ,

The series production of Nb3Sn and NbTi cable-inconduit conductors (CICC) for the winding of various coils in the International Thermonuclear Experimental Reactor (ITER) magnet system is being completed in 2015. The tests of the ITER conductor samples are ...

Ieee-Inst Electrical Electronics Engineers Inc2016