Pierre Gavouyere-Lasserre

ORCID: 0000-0001-9572-7197
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About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Superconducting Materials and Applications
  • Particle accelerators and beam dynamics
  • Particle Accelerators and Free-Electron Lasers
  • Fusion materials and technologies

Fusion for Energy
2020-2022

Fusion for Energy is delivering 5 out of 6 ITER superconducting poloidal field coils (PF coils), which are composed stacks to 8 double-layered circular - double pancakes (DPs). The range from 17m 24m in diameter and the wound conductor has a NbTi core inside stainless steel squared jacked. Due size PF2-4 coils, they have been manufactured on site, very close assembly hall. This article highlights manufacturing processes, learning curve, main challenges learned lessons during winding...

10.1109/tasc.2024.3362758 article EN IEEE Transactions on Applied Superconductivity 2024-02-06

The plasma confinement of the International Tokamak Experimental Rector (ITER) is provided by magnetic field generated 18 toroidal (TF) coils while 6 poloidal (PF) and central solenoid have function to drive, shape pre-heat plasma. Fusion for Energy (F4E), European Domestic Agency ITER, responsible supply 10 TF 5 PF ITER project. Organization (IO) team instead design such as well coordination activities different Agencies (DAs) producing components, their assembly into Tokamak. utilize NbTi...

10.1109/tasc.2020.2979397 article EN IEEE Transactions on Applied Superconductivity 2020-03-31

Fusion for Energy (F4E), the European Domestic Agency International Thermonuclear Experimental Reactor (ITER), is responsible supply of 5 out 6 Poloidal Field (PF) Coils: PF2-PF6. One coil, PF1, being manufactured by Russian Federation (RFDA). While 10 m diameter PF6 was Institute Plasma Physics Chinese Academy Sciences (ASIPP) and tested in cold test facility at Cadarache under a collaboration agreement with F4E; coils PF2-PF5 are currently on site, close to Tokamak building, their size...

10.1109/tasc.2022.3149227 article EN IEEE Transactions on Applied Superconductivity 2022-02-07

The plasma confinement of the International Tokamak Experimental Rector (ITER) is provided by magnetic field generated 18 toroidal (TF) coils while 6 poloidal (PF) and central solenoid modules have function to drive, shape pre-heat plasma. Fusion for Energy (F4E), European Domestic Agency ITER, responsible supply 10 TF 5 PF ITER project. utilize NbTi Cable-in-Conduit-Conductor (CICC) different diameters between 8 24 meters a weight up 400 tons. So far two EU coils, PF5 PF6, been completed....

10.1109/tasc.2022.3171191 article EN IEEE Transactions on Applied Superconductivity 2022-05-10
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