A5080367833- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Laser-Plasma Interactions and Diagnostics
- Network Traffic and Congestion Control
- Advanced Condensed Matter Physics
- Distributed systems and fault tolerance
- Glass properties and applications
- Mobile Agent-Based Network Management
- Surface Roughness and Optical Measurements
- Nuclear Materials and Properties
- Laser-induced spectroscopy and plasma
- Muon and positron interactions and applications
- High-pressure geophysics and materials
- Atomic and Molecular Physics
- Solid State Laser Technologies
- Nuclear and radioactivity studies
- Magneto-Optical Properties and Applications
- Gas Dynamics and Kinetic Theory
- Optical Systems and Laser Technology
- Advanced Research in Science and Engineering
Forschungszentrum Jülich
2011-2023
An initial concept for the plasma diagnostic and control (D&C) system has been developed as part of European studies towards development a demonstration tokamak fusion reactor (DEMO). The main objective is to develop feasible, integrated design DEMO D&C that can provide reliable high performance (electricity output) over extended periods operation. While power maximized when operating near operational limits tokamak, reliability operation typically improves choosing parameters significantly...
Abstract The paper reports the first demonstration of in situ laser-induced desorption — quadrupole mass spectrometry (LID-QMS) application on a large scale fusion device performed summer 2023. LID-QMS allows direct measurements fuel inventory plasma facing components without retrieving them from device. diagnostic desorbs retained gases by heating 3 mm diameter spot wall using 1 ms long laser pulse and detects QMS. Thus, it can measure gas content at any position accessible to laser....
Mirrors will be used as first plasma-viewing elements in optical and laser-based diagnostics ITER. Deterioration of the mirror performance due to e.g. sputtering surface by plasma particles or deposition impurities hamper entire affected diagnostic thus affect ITER operation. The Specialists Working Group on First (FM SWG) Topical Diagnostics International Tokamak Physics Activity (ITPA) plays an important role finding solutions for mirrors.
The efficient and reliable control monitoring of the quality optical properties mirrors is an open problem in laboratory plasmas. Until now, measurement reflectance first was based on methods that require additional light calibration sources. We propose a new technique ratio red- blue-shifted emission signals reflected hydrogen atoms which enables situ spectral metallic low-density Ar-H or Ar-D coefficients were measured for C, Al, Ag, Fe, Pd, Ti, Sn, Rh, Mo, W installed linear magnetized...
The reflectometry diagnostic proposed for DEMO aims to measure the radial edge density profile and provide data feedback control of plasma position shape. Microwave (MW) measurements are foreseen at 16 poloidal locations (gaps) require plasma-facing antennas waveguides (WGs) route microwaves through upper port (UP) hall. current integration proposal is based on Diagnostics Slim Cassette (DSC) concept, a full, 25-cm thick sector dedicated house WGs. This paper translates main findings from...
A conservative engineering model of the impurity deposition on diagnostic mirrors is proposed. The applied to analyze numerically effect protecting structures (ducts) with and without baffles in conditions ITER main chamber. It was found that gross rate ducts baffles, if they are long enough, can be made by an order magnitude smaller than equivalent length baffles. This prediction tested experimentally. calculated efficiency flux attenuation depends strongly assumption: variation between...
The diagnostics slim cassette (DSC) is a concept currently proposed for DEMO to host the microwave reflectometry diagnostic in dedicated poloidal section, feedback control of plasma position and shape, also providing radial edge density profile at several angles. This DSC, which expected house up 100 antennas waveguides, be integrated with breeding blanket (BB) segments. Moreover, it being designed remote handling compatibility mind facilitate 'fast' exchange by maintenance (RM) when needed,...
Core particle fueling, an essential task in the European demonstration fusion power plant EU-DEMO, relies on adequate pellet injection. However, pellets are fragile objects, and their delivery efficiency can hardly be assumed to unity. Exploring kinetic control of EU-DEMO1 scenario indicates that such missed-out do cause a considerable problem for keeping burning plasma. Missed-out severe drop plasma density turn results potential drastic loss burn power. Efforts under way at ASDEX Upgrade...
Mirrors inside the ITER torus vacuum are used in many of port based diagnostic systems. As example, core Charge Exchange Recombination Spectroscopy (core CXRS) concept is on a mirror labyrinth 7 consecutive in-vessel mirrors. For this system, ex-vessel alignment up to three mirrors might be needed. Because unique and demanding environment plugs, especially first meter from plasma, existing designs adjustable holders cannot without modification. The wish allow re-alignment during maintenance...
Optical mirrors inside the ITER torus vacuum are required by many of port-based diagnostic systems. As an example, core charge exchange recombination spectroscopy (core CXRS) concept is based on a mirror labyrinth seven consecutive in-vessel (exposed to vacuum) mirrors. For this system, alignment up three during assembly might be needed. Because unique and demanding environment in port plugs, particularly first meter from plasma, existing designs adjustable holders cannot used without...