A5090594150- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Spacecraft and Cryogenic Technologies
- Nuclear Physics and Applications
- European and International Law Studies
- Heat Transfer and Boiling Studies
- Caribbean and African Literature and Culture
- Cerebrovascular and Carotid Artery Diseases
- Boron Compounds in Chemistry
- Heat Transfer and Optimization
- Nuclear reactor physics and engineering
- Asphalt Pavement Performance Evaluation
- Aging, Elder Care, and Social Issues
- Muon and positron interactions and applications
- International Law and Aviation
- Renal and Vascular Pathologies
- Sensor Technology and Measurement Systems
- Engineering and Materials Science Studies
- HVDC Systems and Fault Protection
Université Paris-Saclay
2024
Électricité de France (France)
2023
ITER
2013-2023
CEA Cadarache
2010
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2010
University of Alberta
1972
The ITER central solenoid (CS) is a highly stressed magnet that must provide 30 000 plasma cycles under the prescribed maximum operating conditions. To verify performance of CS conductor in conditions close to those for CS, insert was built USA-Japan collaboration. tested aperture CSMC facility Naka, Japan, during first half 2015. A magnetic field up 13 T and transport current 60 kA provided wide range parameters characterize conductor. has been direct reverse charges, which allowed strain...
While the ITER magnet system assembly is progressing, models are being developed to predict performances of coils in support preparation commissioning and operation. In particular, AC losses generated during a plasma scenario need be estimated as input thermo-hydraulic performance simulations. The largest operation expected CS PF coils. This paper discusses results simulations these representative pulse. These calculations also take into account electromagnetic screening provided by passive...
AC loss is a major heat load in the pulsed, superconducting ITER coils, and thus design driver for cryo-system superconductor. Given importance of loss, extensive characterization components from strands, cables, long “coil-like” conductors (so called insert-coils) to completed were conducted over past years. Recently first Central Solenoid (CS) modules factory tested including tests representative operational conditions. The modelling critical preparation Tokamak operation commissioning....
During the years of ITER conductors qualification and production, samples from all domestic agencies were tested. Some these tests focused on characterizing AC losses properties conductors. The data produced originate various facilities (PSI, University Twente, CERN), using different experimental reduction protocols, for a large number samples. result is thus considerable database results with wide spread in properties. need reduced set parameters describing now becoming urgent order to...
The ITER Central Solenoid (CS) will be realized by assembling a stack of six modules. Each module is solenoid consisting 40 pancakes wound with Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn Cable in Conduit Conductor (CICC). tests the second (CSM#2) were performed at General Atomics (GA) facility Poway (US). During test campaign, CS Module submitted to dumps transport current from different initial values (10, 15, 20, 25, 30, 35,...
The ITER Central Solenoid (CS), the backbone of magnet system, is composed 6 modules, each made 40 pancakes, for a total conductor length about 36 km. More than 4 km pipes, 30 bypass or control valves, heat exchangers and cold circulator are part cryogenic distribution used to maintain nominal operating conditions (flow temperature). During plasma scenario, several loss sources – such as AC losses, from supports structures, joule heating at joints can affect stability. A reliable analysis...
The ITER Central Solenoid (CS) will be manufactured by assembling a stack of six modules, which are under fabrication the US organization and its subcontractors. tests first CS Module have been performed at premises General Atomics (GA) facility in Poway (US), order to check compliance requirements. Among other tests, magnet was submitted exponential dumps transport current from different initial values (10, 15, 20, 22.5, 25, 35, 40 kA) down 0 kA. These aimed conducting DC breaker...
The poloidal field (PF) coils and correction (CCs) constitute one of the four hydraulic loops ITER magnet system. They are cooled in parallel by same heat exchanger. PF consist 6 different pulsed while CCs include 18 divided into 3 sets: bottom, side top. made dual-channel NbTi conductors whereas single-channel conductors. SuperMagnet suite codes can combine 1-D cooling with supercritical helium flow 2-D diffusion across a full-scale quasi 3-D model. We analyzed in-coil conductor performance...
While the ITER Magnet system is being assembled at Cadarache (France), models are developed on basis of conductors test results. The purpose to prepare performances extrapolation magnet commissioning and operation. In particular, AC losses generated in during a plasma scenario should be estimated order predict potential operating margins reductions prevent quenches. there case TF inner leg, where field variations both transverse parallel axis conductor, PF/CS current variation. This paper...
The Central Solenoid (CS) is a key element of the ITER Magnet system, including six identical coils, called modules, assembled together to form 4 m outer diameter, 13 high solenoid. It superconducting magnet, using 45 kA Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn conductor internally cooled by circulation supercritical helium at 4.5 K with peak field up T. enclosed inside structure providing vertical pre-compression and...
The ITER Central Solenoid is under fabrication by the U.S. organization and its subcontractors. will supply seven modules to IO, six of which be assembled in a stack that forms Solenoid. first were built GA at their facility, went into high voltage testing, including Paschen testing vacuum, then they tested 4.5 K up 40 kA demonstrate compliance coil with requirements. In this article, we present Test Plan results central solenoid (CS) module's performance, especially full current. We...
<para xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> In the framework of EU participation to JT-60SA project, a “pseudo-3D” thermo hydraulic tool was developed in order address reliably choice between multiple design options on TF coils design. </para>
Previous quench studies performed for the International Thermonuclear Experimental Reactor (ITER) Toroidal Field (TF) Coils have led to identify two extreme families of quench: first "severe" quenches over long initial lengths in high magnetic field, and second smooth short low field region. Detailed analyses results on propagation detectability one TF Cable In Conduit Conductor (CICC) with a lower velocity are presented here. The influence energy is shown computations either Fast Discharge...
Quantum and radiological science technology performed a toroidal field (TF) insert coil (TFIC) test in 2016-2017, which was newly developed 2014 with the ITER TF conductor, central solenoid model facility. According to program, TFIC underwent more than 1000 cycles of energization 68 kA under 10.8 T background field, represents lifetime electromagnetic loads coils. Then, five warm-up 290 K cool-down temperature lower 5 were also performed. Through campaign, transition current sharing (Tcs)...
As part of the design verification ITER magnet system and in preparation commissioning activities, heat deposition on cold structures has been computed order to generate input loads for subsequent thermo-hydraulic analyses, which are essential assessment temperature margins superconducting cables. The Finite Element model a 40 degree sector presented previous works (F. Cau et al., 2016) updated, including Poloidal Field (PF) coils clamps Correction Coils (CC) supports. A new inductive plasma...
During ITER plasma operation, large thermal loads are generated in the stainless steel Toroidal Field (TF) coil casing. To minimize impact on temperature of TF Cable Conduit Conductor (CICC), these heat intercepted by case cooling channels which implemented at interface to winding pack. One design options for consists a pipe inserted rectangular groove is machined casing and filled charged resin high conductivity. A higher number pipes arranged facing wall case, thus providing better...
The paper presents a numerical study on electrodynamic be-havior of the inter-pancake twin-box joints Poloidal Field (PF) coils ITER Magnet System. This work was carried out with THELMA code, developed at University Bo-logna. model adapted to describe both superconducting wires and resistive saddle joint in set reference configurations representative exper-imental tests performed sample SULTAN fa-cility Villigen, Switzerland. applied ana-lyze DC resistance measurements AC loss vs frequency...
Thorough analyses of electromagnetic transients in superconducting coils for fusion magnets are necessary to compute the losses arising time-varying operating conditions and correctly design cryogenic system. The challenge these analyses, when using numerical methods, is related high number degrees freedom required discretize large-scale wound with cable conduit conductors (CICCs), which include hundreds composite strands. This study focused on central solenoid (CS) ITER magnet system,...
The ITER magnet system consists of 4 sub-systems: 3 sets 6 Correction Coils (CC), a Central Solenoid (CS), Poloidal Field coils (PF) and 18 Toroidal (TFC). Coil aims to correct particular asymmetries reduce error magnetic fields responsible for locked modes which can induce plasma disruptions. During the scenario, thermal shield radiation, eddy current losses in structures, conduction from TFC casing AC NbTi superconductor will decrease temperature margin CC conductor.
The ITER Central Solenoid (CS) modules are under fabrication by the US organization and its subcontractors. will supply seven to Organization (IO), six of which be assembled in a stack that forms Solenoid, last one being spare. first module, namely CSM 1 was manufactured General Atomics (GA) went through Factory Acceptance Tests (FAT) including high voltage testing, Paschen testing then cold test at 4.5 K up 40.0 kA order demonstrate compliance with coil performance requirements. paper...