Publications related to The performance test and analysis of the third and fourth China PF conductor for ITER

Related publications (31)

Long plasma duration operation analyses with an international multi-machine (tokamaks and stellarators) database

Combined high-fusion performance and long-pulse operation is one of the key integration challenges for fusion energy development in magnetic devices. Addressing these challenges requires an integrated vision of physics and engineering aspects with the purp ...

IOP Publishing Ltd2024

Re-design of EU DEMO with a low aspect ratio

Xabier Sarasola Martin

The design point that had been chosen for EU DEMO in 2016 is reviewed here and a modification is proposed with a lower aspect ratio. Previously the same aspect ratio, A, was chosen for EU DEMO as in major tokamak experiments including ITER (A = 3.1), and, ...

Elsevier2024

DTT toroidal field conductor samples test in Sultan: DC and AC characterization

Kamil Sedlák, Mattia Ortino, Hugues Marie Alain Bajas

The superconducting magnet system of the Divertor Tokamak Test (DTT) facility, composed of 18 toroidal field (TF) coils, 6 poloidal field coils and a central solenoid, has been designed and many procurements have been launched. Some manufacturing aspects a ...

Iop Publishing Ltd2024

DEMO toroidal field coil fast discharge unit integration studies

Roberto Guarino

The Fast Discharge Units (FDUs) of the Superconducting (SC) Toroidal Field (TF) coils in the European demonstration fusion power plant DEMO warrant the machine integrity over its full lifetime against severe failure events, such as SC coil quenches or any ...

Elsevier Science Sa2024

ICRH assisted breakdown study on JET

Benoît Labit, Haomin Sun, Thomas Binderup Jensen

Ion cyclotron (IC) wave assisted breakdown has the potential to increase the robustness of plasma initiation during the ITER pre-fusion operation phase. Studies were performed at JET at ITER relevant loop electric field, E-loop ? 0.33 Vm(-1), and a range o ...

IOP Publishing Ltd2023

First characterization of the SPIDER beam AC component with the Beamlet Current Monitor

Basile Marie Jacques Pouradier Duteil

SPIDER is the full scale prototype for the ITER Heating Neutral Beam source, hosted at the Neutral Beam Test Facility in Padova, Italy. The behavior of the beam must be thoroughly investigated to bring the machine's performance in line with ITER's requirem ...

2023

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

Beam homogeneity of caesium seeded SPIDER using a direct beamlet current measurement

Basile Marie Jacques Pouradier Duteil

The ITER Heating Neutral Beam (HNB) source prototype SPIDER (Source for the Production of Ions of Deuterium Extracted from a Radio frequency plasma), hosted at the Neutral Beam Test Facility (NBTF) in Padova, Italy, has recently started operating with evap ...

ELSEVIER SCIENCE SA2023

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

Tests and Qualification of the European 1 MW, 170 GHz CW Gyrotron in an ITER relevant configuration at SPC

Timothy Goodman, Stefano Alberti, Jean-Philippe Hogge, Francisco Sanchez, Jérémy Genoud

After an initial testing period at the Karlsruhe Institute of Technology, the upgraded EU 1 MW, 170 GHz continuous wave (CW) industrial prototype gyrotron (TH1509U) for Electron Cyclotron Resonance Heating and Current Drive (ECRH&CD) in ITER has been trans ...

IEEE2022

Measurements of AC Loss Evolution in ITER TF Conductors

Pierluigi Bruzzone, Kamil Sedlák

AC loss in the Nb3Sn cable-in-conduit conductors (CICC) usually decreases after the conductor undergoes electromagnetic cycling. This can be attributed to the increase of inter-strand resistance due to the detachment of the strand-bonding during cyclic loa ...

IEEE Institute of Electrical and Electronics Engineers2022

Electromechanical investigations and quench experiments on sub-size HTS cables for high field EU-DEMO Central Solenoid

Ortensia Dicuonzo

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

EUROfusion-theory and advanced simulation coordination (E-TASC): programme and the role of high performance computing

Jonathan Graves, Laurent Villard

This paper is a written summary of an overview oral presentation given at the 1st Spanish Fusion High Performance Computer (HPC) Workshop that took place on the 27 November 2020 as an online event. Given that over the next few years ITER24 will move to its ...

2022

The SparSpec algorithm and the application to the detection of spatial periodicities in tokamaks: from a 1D to a 2D analysis

Duccio Testa

A well-known, previously only 1D, algorithm using the Sparse Representation of Signals and an iterative Block Coordinate Descent method (the SparSpec-1D algorithm) has been further developed and tested in a 2D spatial domain to obtain the toroidal and polo ...

2022

Preliminary Design of a High Current R&W TF Coil Conductor for the EU DEMO

Pierluigi Bruzzone, Kamil Sedlák, Federica Demattè

Paschen failures in ITER, W7-X and JT60 superconducting coils at the acceptance tests have shown that it is highly desirable to lower the coil discharge voltage (U-d) of the DEMO Toroidal Field (TF) coils. Another benefit of lowering the U-d might be the r ...

IEEE Institute of Electrical and Electronics Engineers2022

Thermal-hydraulic analysis of alternative cable-in-conduit conductors for the European DEMO hybrid central solenoid

Kamil Sedlák, Xabier Sarasola Martin, Roberto Guarino, Nikolay Bykovskiy

A hybrid design of the Central Solenoid is under study within the conceptual design phase of the European DEMO fusion reactor. It is based on HTS conductors in the innermost high-field layers, and Nb3Sn and NbTi conductors for field values below 15 T. Sinc ...

2022

Impact of mechanical and thermal cycles at different operating conditions on the ITER toroidal field coil conductor performance

Pierluigi Bruzzone, Kamil Sedlák

The impact of electromagnetic (EM) and thermal cyclic loading (referred as warm-up-cool-down-WUCD) on the Nb3Sn cable in conduit conductors for the toroidal field magnets of the ITER tokamak should be carefully assessed for the proper operation of the mach ...

IOP Publishing Ltd2021

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

Pierluigi Bruzzone, Rainer Wesche, Boris Stepanov, Kamil Sedlák, Davide Uglietti, Ortensia Dicuonzo

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 ...

IEEE Institute of Electrical and Electronics Engineers2021

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

Pierluigi Bruzzone, Boris Stepanov, Kamil Sedlák

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

Integration concept of an Electron Cyclotron System in DEMO

Minh Quang Tran, René Chavan

The pre-conceptual layout for an electron cyclotron system (ECS) in DEMO is described. The present DEMO ECS considers only equatorial ports for both plasma heating and neoclassical tearing mode (NTM) control. This differs from ITER, where four launchers in ...

2021