A5034789276- Magnetic confinement fusion research
- Fusion materials and technologies
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Anomaly Detection Techniques and Applications
- Currency Recognition and Detection
- Infrared Target Detection Methodologies
- Ionosphere and magnetosphere dynamics
- Atomic and Subatomic Physics Research
- Spectroscopy and Laser Applications
- Seismology and Earthquake Studies
- Generative Adversarial Networks and Image Synthesis
- Combustion and flame dynamics
- Image Retrieval and Classification Techniques
- Optical Systems and Laser Technology
- Sensor Technology and Measurement Systems
- Video Coding and Compression Technologies
- Metal and Thin Film Mechanics
- Welding Techniques and Residual Stresses
- Image and Video Quality Assessment
CEA Cadarache
2014-2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2014-2024
Institut de Recherche sur la Fusion par Confinement Magnétique
2021
National University of Engineering
1970
The new JET ITER-like wall (made of beryllium and tungsten) is more fragile than the former carbon fiber composite requires active protection to prevent excessive heat loads on plasma facing components (PFC). Analog CCD cameras operating in near infrared wavelength are used measure surface temperature PFCs. Region interest (ROI) analysis performed real time maximum measured each ROI sent vessel thermal map. system started October 2011 has already successfully led a safe landing when hot...
In this paper, a method was developed to estimate in-situ the emissivity of W-coated graphite divertor tiles in WEST tokamak. This is based on double heating and take advantages temperature increase after successive plasma experiments due inertial behavior facing components. Photonic calculations have been used disentangle emitted reflected parts measured radiances from infrared system. The uncertainty as well robustness investigated thanks wide IR thermocouple coverage divertor. results...
Abstract A multi-stage process that detects, tracks and classifies thermal events automatically using imaging of the inside fusion reactors is presented. The relies on Cascade R-CNN algorithm for detection classification SORT tracking. trained a dataset 325 distributed in seven classes, manually annotated from 20 infrared movies WEST tokamak. This created user-friendly annotation tools, based simple thresholding. performance evaluated modified indicators emphasize importance hottest zones...
During operation of present fusion devices, the plasma facing components (PFCs) are exposed to high heat fluxes. Understanding and preventing overheating these during long pulse discharges is a crucial safety issue for future devices like ITER. Infrared digital cameras interfaced with complex optical systems have become routine diagnostic measure surface temperatures in many magnetic devices. Due complexity observed scenes large amount data produced, use computational performance hardware...
During the 2019 C4 experimental campaign of WEST (W Environment in Steady-state Tokamak) (France), infrared diagnostic produced more than seven terabytes uncompressed video data. Constraints on computer infrastructure required for storage, backup, and especially offline access to videos made use a compression algorithm mandatory. This paper proposes an innovative method compress with controlled temperature precision. is based averaging that maximizes potential standard lossless codecs such...
With the development of heterogeneous camera networks working at different wavelengths and frame rates covering a large surface vacuum vessel, visual observation variety plasma thermal phenomena (e.g., hot spots, ELMs, MARFE, arcs, dusts, etc.) becomes possible. In domain machine protection, phenomenological diagnostic is key-element towards plasma/thermal event dangerousness assessment during real time operation. It also primary importance to automate extraction storage information for...
The ITER actively cooled tokamak is the next-generation fusion device that will allow study of burning plasma over hundreds seconds. plasma-facing component (PFC) real-time protection be mandatory to minimize operational risks as water leaks and critical heat flux lead degradation PFCs. systems routinely used on Tore Supra (TS) or JET are based infrared (IR) imaging controlling monitoring power load PFCs through surface temperature measurements. Thanks TS expertise in long-pulse operation,...
Abstract In this paper, we promote intelligent plasma facing component video monitoring for both real‐time purposes (machine protection issues) and post event analysis (plasma‐wall interaction understanding). We propose a vision‐based system able to automatically detect classify into different pre‐defined categories thermal phenomena such as localized hot spots or transient events (e.g. electrical arcing) from infrared imaging data of PFCs. This original computer vision is made by endowing...
The ITER tokamak is the next generation fusion device which will allow studying burning plasma obtained by a Deuterium-Tritium (D-T) reaction during hundreds of seconds. vacuum vessel real-time protection be mandatory operation to avoid water leaks and critical facing components degradation. system based on wide angle viewing (WAVS) composed with 18 visible (VIS) infrared (IR) cameras covering 80 % one major imaging systems ITER. Compared routinely used current tokamaks (VIS and/or IR), new...
In nuclear fusion devices, such as Tore Supra, the plasma facing components (PFC) are in carbon. Such exposed to very high heat flux and surface temperature measurement is mandatory for safety of device also efficient scenario development. Besides this essential evaluate these fluxes a better knowledge physics plasma-wall interaction, it required monitor fatigue PFCs. Infrared system (IR) used manage measure real time. For carbon PFCs, emissivity known (ɛ ∼ 0.8), therefore contribution...
The Wendelstein 7-X stellarator is a large nuclear fusion device based at Max-Planck-Institut für Plasmaphysik in Greifswald Germany. main plasma heating system for steady state operation W7-X electron cyclotron resonance (ECRH). During operation, part of plama facing components will be directly heated by the non-absorbed power 1 MW rf beams ECRH. In order to avoid damages such made graphite tiles during first operational phase, near infra-red video has been developed as protective...
Magnetic confinement fusion reactors are complex devices where a large amount of energy is required to make the reactions happen. In such experimental conditions, plasma facing components (PFC) subjected high heat fluxes. current Tokamaks like Tore Supra, infrared thermographic diagnostics based on image analysis and feedback control used measure monitor heating PFC during operation. The system consists in detecting increase IR luminance signal beyond fixed temperature thresholds for set...
The bonding of plasma-facing component (PFC) tiles and their possible defects need to be monitored evaluate the safety during long pulse plasma operations prevent critical failure, which is very important for ITER next-step fusion devices. defect evolutions two toroidal pumped limiter (TPL) are investigated by analysing infrared images obtained Tore Supra experiments from 2006 2010 (about 10 000 discharges). evolution characterized surface temperature reached in stationary discharge...
Abstract The protection of the inner walls magnetic confinement fusion research reactors is a crucial issue, particularly in this context where plasma scenarios are explored to reach high power performance, thus leading temperature facing components (PFCs), possibly close their technological limitation. aim protect PFCs from damage during experimental campaigns, whilst enabling expansion operational domain toward long duration and performances. With nearly 35 years operation Tore Supra now...