A5070328504- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Gyrotron and Vacuum Electronics Research
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Electromagnetic Launch and Propulsion Technology
- Diamond and Carbon-based Materials Research
- Induction Heating and Inverter Technology
- Metal and Thin Film Mechanics
- Nuclear and radioactivity studies
- Semiconductor materials and devices
- Laser-Plasma Interactions and Diagnostics
- Graphite, nuclear technology, radiation studies
- Nuclear Materials and Properties
- Pulsed Power Technology Applications
- Muon and positron interactions and applications
- Plasma Diagnostics and Applications
- Magneto-Optical Properties and Applications
- Renewable energy and sustainable power systems
- Particle Accelerators and Free-Electron Lasers
- Adaptive optics and wavefront sensing
- Ammonia Synthesis and Nitrogen Reduction
- Gas Dynamics and Kinetic Theory
Karlsruhe Institute of Technology
2011-2024
Applied Materials (Germany)
2014-2022
National Agency for New Technologies, Energy and Sustainable Economic Development
2022
University of Padua
2022
Applied Materials (United States)
2017-2019
FZI Research Center for Information Technology
2005-2010
École Polytechnique Fédérale de Lausanne
2008
Fusion for Energy
2008
The European DEMO is a pulsed device with pulse length of 2 hours. functions devoted to the heating and current drive system are: plasma breakdown, ramp-up flat-top where fusion reactions occur, control during phase, finally ramp-down. EU-DEMO project was in Pre-Concept Design Phase 2014-2020, meaning that some cases, design values precise requirements from physics point view were not yet frozen. A total 130 MW considered for all phases plasma: flat top, 30 required neoclassical tearing...
The ITER electron cyclotron (EC) upper port antenna (or launcher) is nearing completion of the detailed design stage and final build-to-print will soon start. main objective this launcher to drive current locally stabilize neoclassical tearing modes (NTMs) (depositing ECCD inside island that forms on either q = 3/2 or 2 rational magnetic flux surfaces) control sawtooth instability (deposit near 1 surface). should be capable steering focused beam deposition location resonant surface over...
This article describes the DEMO cryostat, vacuum vessel, and tokamak building as well system configurations to integrate main in-vessel components auxiliary systems developed during Pre-Conceptual Design Phase. The vessel is primary component for radiation shielding containment of tritium other radioactive material. Various required operate plasma are integrated in its ports. together with external magnetic coils located inside even larger cryostat that has function provide a enable...
The EU DEMO Tokamak is foreseen to be equipped with an electron cyclotron (EC) system for plasma heating, magnetohydrodynamic (MHD) control, and thermal instability suppression. Up six launchers will installed into equatorial ports the aim inject a maximum of 130 MW millimeter wave power at frequencies 136/170/204 GHz toward dedicated positions plasma. This article presents current layout typical EC launcher components within available space reservation areas in level baseline model. Beside...
Abstract The European DEMO (EU-DEMO) reactor studies within EUROfusion aim to develop a fusion power plant concept. large tokamak device needs an auxiliary heating which, at the present stage, is provided by Electron Cyclotron (EC) system with up 130 MW foreseen reach different regions of plasma for heating, suppression instabilities and possibility support ramp-up ramp-down phases. conceptual design based on 2 coaxial-cavity gyrotron sources, transmission line (TL) using both circular...
The front steering (FS) launcher is one of two concepts that have been considered for the ITER electron cyclotron heating upper by European Union. During development a detailed conceptual design, team involved with FS project listed all critical issues associated installing an in port, and then work was concentrated on providing solution to each design issues. A similar procedure performed alternative option (remote launcher). These actions helped International Team evaluate systems choose...
Computational results of the nuclear analyses for ECRH launcher integrated into ITER upper port are presented. The purpose was to provide proof design that requirements specified in project can be met. aim achieved on basis 3D neutronics radiation transport calculations using Monte Carlo code MCNP. In course an adequate shielding configuration against neutron and gamma developed keeping necessary empty space mm-waves propagation accordance with physics guidelines. Different variants extended...
For high power transmission in ECRH systems, window materials have to combine ultra low mm-wave loss (tanδ < 10−4) with an outstanding resistance against crack formation. Specially challenging are the CVD diamond ''torus'' windows which form primary tritium confinement system of Upper Launcher for plasma stabilization at ITER and be designed as a compact structure allowing 2 MW beams 170 GHz. Special emphasis is given development remote steering (RS) launcher, contrast alternative front (FS)...
The electron cyclotron (EC) system of ITER for the initial configuration is designed to provide 20MW RF power into plasma during 3600s and a duty cycle up 25% heating (co counter) non-inductive current drive, also used control MHD instabilities. EC being procured by 5 domestic agencies plus Organization (IO). F4E has largest fraction procurements, which includes 8 high voltage supplies (HVPS), 6 gyrotrons, ex-vessel waveguides (includes isolation valves diamond windows) all launchers, 4...
The ITER torus diamond window unit is part of the electron cyclotron (EC) upper launcher (UL) used to direct high power microwave beams generated by gyrotrons into plasma for heating and current drive (H&CD) applications. UL consists an assembly ex-vessel waveguides (WGs) in-vessel port plug (PP). units form vacuum confinement boundaries between volume transmission lines (TLs) which guide 1 1.5 MW at 170 GHz from launcher. There are eight attached WGs, one each WG. design strategy have a...