A5019917556- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Advanced materials and composites
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Laser-Plasma Interactions and Diagnostics
- Solar and Space Plasma Dynamics
- Nuclear Physics and Applications
- Laser-induced spectroscopy and plasma
- Atomic and Molecular Physics
- Metal and Thin Film Mechanics
- Advanced ceramic materials synthesis
- Intermetallics and Advanced Alloy Properties
- Nuclear physics research studies
- Metallurgical Processes and Thermodynamics
- Spacecraft and Cryogenic Technologies
- Ion-surface interactions and analysis
- Diamond and Carbon-based Materials Research
- Vacuum and Plasma Arcs
- Astro and Planetary Science
- X-ray Spectroscopy and Fluorescence Analysis
Max Planck Institute for Plasma Physics
2016-2025
Technical University of Munich
2016-2025
University of Rome Tor Vergata
2024
University of Wisconsin–Madison
2022
Max Planck Society
2012-2021
Royal Military Academy
2020
Max Planck Innovation
1985-2017
Forschungszentrum Jülich
2007-2017
Institute for Particle and Nuclear Physics
2016
HUN-REN Wigner Research Centre for Physics
2016
Progress, since the ITER Physics Basis publication (ITER Editors et al 1999 Nucl. Fusion 39 2137–2664), in understanding processes that will determine properties of plasma edge and its interaction with material elements is described. Experimental areas where significant progress has taken place are energy transport scrape-off layer (SOL) particular anomalous scaling, particle SOL plays a major role diverted plasmas main-chamber elements, localized mode (ELM) deposition on mechanism for ELM...
This paper reports the successful installation of JET ITER-like wall and realization its technical objectives. It also presents an overview planned experimental programme which has been optimized to exploit new other enhancements in 2011/12.
Tungsten (W) has moved into the focus of fusion research being a main candidate for plasma facing components (PFCs) ITER and future reactor. A ingredient understanding influence W as impurity its impact on is spatially resolved spectroscopic diagnosis W. The experimental investigations at ASDEX Upgrade most intense emissions ions (about I-like W21+ to Mn-like W49+) in VUV soft x-ray region covering electron temperature range from about 0.5–5.0 keV. relative shape fractional abundances...
JET underwent a transformation from full carbon-dominated tokamak to fully metallic device with beryllium in the main chamber and tungsten divertor. This material combination is foreseen for activated phase of ITER. The ITER-Like Wall (ILW) experiment at shall demonstrate plasma compatibility walls reduction fuel retention. We report on set experiments (Ip = 2.0 MA, Bt 2.0–2.4 T, δ 0.2–0.4) different confinement conditions global gas balance analysis demonstrating strong long-term retention...
The preferred plasma-facing material in present-day and future magnetic confinement thermonuclear fusion devices is tungsten. This mainly chosen because of its high threshold energy for sputtering by hydrogen isotopes as well low retention tritium within the material. From an engineering point view, however, tungsten a challenging to work with it inherently hard brittle metal. In this respect, established fabrication technologies based materials are limiting factor directly affecting design...
The tungsten programme in ASDEX Upgrade is pursued towards a full high-Z device. spectroscopic diagnostic of W has been extended and refined the cooling factor re-evaluated. coated surfaces now represent fraction 65% all plasma facing components (24.8 m2). only two major that are not yet strikepoint region lower divertor as well limiters at low field side. While extending surfaces, concentration discharge behaviour have changed gradually pointing to critical issues when operating with wall:...
The cooling factor of W is evaluated using state the art data for line radiation and an ionization balance which has been benchmarked with experiment. For calculation radiation, level-resolved calculations were performed Cowan code to obtain electronic structure excitation cross sections (plane-wave Born approximation). processed by a collisional radiative model electron density dependent emissions. These then combined power derived from recombination rates bremsstrahlung total factor....
In ASDEX Upgrade, experimental efforts aim to establish pace making and mitigation of type-I edge localized modes (ELMs) in high confinement mode (H-mode) discharges. Injection small size cryogenic deuterium pellets (∼(1.4 mm)2 × 0.2 mm ≈ 2.5 1019 D) at rates up 83 Hz imposed persisting ELM control without significant fuelling, enabling for investigations well inside the regime. The approach turned out meet all required operational features. was realized with driving frequency ranging from 1...
A new thermography system with high time resolution was put into operation at ASDEX-Upgrade and is routinely used to determine the energy flux onto lower diverter plates. The measurements allow power deposition be characterized during dynamic events such as ELMs disruptions, well asymmetry of inboard/outboard load. balance set up even single discharges losses are found fairly equal input.
Local edge parameters on the ASDEX Upgrade tokamak are investigated at L-mode to H-mode transition, during phases with various types of edge-localized modes (ELMs), and density limit. A scaling law for boundary electron temperature, , is found which describes threshold deuterium-puffed discharges favourable ion -drift direction. The region stable operation bounded by type I ELMs near ideal ballooning limit a minimum temperature necessary avoid thermal instability plasma edge. Stationary III...
Work is in progress to completely replace, 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent ITER design. The ITER-like wall (ILW) will be created combination beryllium (Be), tungsten (W), W-coated and Be-coated inconel tiles, material depending on local anticipated heat flux geometry. It part an integrated package enhancements whose aim develop understanding issues techniques required operate inductive advanced scenarios as close possible...
High-efficiency refuelling of ELMy H-mode tokamak discharges with solid deuterium pellets injected from the magnetic high-field side is demonstrated. Compared to standard low-field injection, fuelling efficiency was enhanced by a factor 4, pellet penetration more than 2 times. This experimental result can be qualitatively explained force pushing diamagnetic plasma cloud towards lower field, causing rapid particle loss for shallow but enhancing and injection.
Feedback control of the divertor power load by means nitrogen seeding has been developed into a routine operational tool in all-tungsten clad ASDEX Upgrade tokamak. For heating powers above about 12 MW, its use become inevitable to protect tungsten coating under boronized conditions. The is accompanied improved energy confinement due higher core plasma temperatures, which more than compensates negative effect dilution on neutron rate. This paper describes technical details feedback...
Recent research in scrape-off layer (SOL) and divertor physics is reviewed; new existing data from a variety of experiments have been used to make cross-experiment comparisons with implications for further ITER. Studies the region near separatrix addressed relationship profiles turbulence as well scaling parallel power flow. Enhanced low-field side radial transport implicated driving flows inboard side. The medium-n nature edge localized modes (ELMs) has elucidated measurements determined...
This paper reports the impact on confinement and power load of high-shape 2.5 MA ELMy H-mode scenario at JET a change from all carbon plasma-facing components to an metal wall. In preparation this change, systematic studies reduction as result fuelling in combination with nitrogen seeding were carried out JET-C are compared their counterpart metallic An unexpected significant is reported decrease pedestal but partially recovered injection nitrogen.
DEMO is the name for first stage prototype fusion reactor considered to be next step after ITER towards realizing fusion.For realization of energy especially materials questions pose a significant challenge already today.Heat, particle and neutron loads are problem material lifetime when extrapolating DEMO.For many issues faced advanced solution under discussion or development.In particular components such as wall divertor can benefit from introducing new approaches composites alloys into...
Operation of DEMO in comparison to ITER will be significantly more demanding, as various additional limitations physical and technical nature have respected. In particular a set extremely restrictive boundary conditions on divertor operation during between ELMs It is high importance describe these order consider them early possible the ongoing development concept design. This paper extrapolates existing physics basis power particle exhaust DEMO.