Y. Anquetin
A5042500183- Fusion materials and technologies
- Magnetic confinement fusion research
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Advanced Fiber Laser Technologies
- Laser Material Processing Techniques
- Nuclear Physics and Applications
- Advanced Sensor Technologies Research
- Nuclear reactor physics and engineering
- Advanced Fiber Optic Sensors
Institut Universitaire des Systèmes Thermiques Industriels
2022-2023
Aix-Marseille Université
2022-2023
Centre National de la Recherche Scientifique
2022-2023
Abstract Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under auspices of a single Task Force called ‘Tokamak Exploitation’. The goal to benefit from complementary capabilities each machine in coordinated way and help developing scientific output scalable future largre machines. programme this ensures that ASDEX Upgrade, MAST-U, TCV, WEST JET (since 2022) work together achieve objectives Missions 1 2 Roadmap: i) demonstrate plasma scenarios...
Assessing the performance of ITER design for tungsten (W) divertor Plasma Facing Units (PFUs) in a tokamak environment is high priority issue to ensure efficient plasma operation. This paper reviews most recent results derived from experiments and post-mortem analysis ITER-grade PFUs exposed WEST associated modelling, with focus on understanding heat loading damage evolution. Several shaping options, sharp or chamfered leading edge (LE), unshaped shaped blocks toroidal bevel as foreseen...
Abstract The mission of WEST (tungsten-W Environment in Steady-state Tokamak) is to explore long pulse operation a full tungsten (W) environment for preparing next-step fusion devices (ITER and DEMO) with focus on testing the ITER actively cooled W divertor tokamak conditions. Following successful completion phase 1 (2016-2021), 2 started December 2022 lower made entirely ITER-grade mono-blocks. A boronization prior first plasma attempt allowed smooth startup new divertor. Despite reduced...
The consequences of tungsten (W) damaging processes, such as cracking and melting, on divertor lifetime plasma operation are high priority issues for ITER. A sustained melting experiment was conducted in WEST using a 2 mm deep groove geometry the upstream mono-block (MB) to overexpose sharp leading edge (LE) downstream MB. W-cracking has been evidenced first time with very spatial resolution infrared camera before reached. These cracks develop when monoblock temperature is about 2600°C, thus...
This paper summarizes the emissivity measurements performed on shaped ITER-like plasma facing units (PFU) of WEST lower divertor installed for second phase WEST. Laboratory before their installation in WEST, as well measurement one PFU after exposure to an experimental campaign are shown. The 24 standard show variability from 0.07 0.2 even a serial production. Measurements high heat flux tests (10 MW/m2 cycles) two different facilities modification induced by this load capability test with...
Fusion-based metallic additive manufacturing (AM) features complex material and heat transfer phenomena. These processes dynamics can be monitored using different techniques in order to assess the quality or detect defects. Fiber Bragg Gratings written femtosecond laser pulses (fs-FBGs) inside optical fibers allow temperature multipoint sensing by monitoring reflected wavelength <tex xmlns:mml="http://www.w3.org/1998/Math/MathML"...