A5086680210- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Superconducting Materials and Applications
- Diamond and Carbon-based Materials Research
- Ion-surface interactions and analysis
- Particle accelerators and beam dynamics
- Metal and Thin Film Mechanics
- Laser-induced spectroscopy and plasma
- Solar and Space Plasma Dynamics
- Nuclear reactor physics and engineering
- Mass Spectrometry Techniques and Applications
- Plasma Applications and Diagnostics
- Atomic and Molecular Physics
- Advanced Chemical Physics Studies
- Spectroscopy and Laser Applications
- Catalytic Processes in Materials Science
- Dust and Plasma Wave Phenomena
- Photochemistry and Electron Transfer Studies
- Nuclear Physics and Applications
- Muon and positron interactions and applications
- Atmospheric chemistry and aerosols
Universidad Complutense de Madrid
2013-2024
Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas
2013-2023
Unidades Centrales Científico-Técnicas
2011-2023
Max Planck Institute for Plasma Physics
1989-2013
University of California, San Diego
2005-2011
Forschungszentrum Jülich
2011
Fusion for Energy
2010
KTH Royal Institute of Technology
2006
University of California, Santa Barbara
1986-1990
This review of the potential robust plasma facing components (PFCs) with liquid surfaces for applications in future D/T fusion device summarizes critical issues and research being done worldwide confinement facilities, supporting R&D surface interactions. In paper are a set questions related criteria by which we will judge progress readiness PFCs. Part-II (separate paper) cover on technology-oriented aspects including as integrated first walls tritium breeding blankets, retention recovery, safety.
The provision of a particle and power exhaust solution which is compatible with first-wall components edge-plasma conditions key area present-day fusion research mandatory for successful operation ITER DEMO. work package plasma-facing (WP PFC) within the European programme complements laboratory experiments, i.e. in linear plasma devices, electron ion beam loading facilities, studies performed toroidally confined magnetic such as JET, ASDEX Upgrade, WEST etc. connection both groups done via...
The first plasma experiments on the W7AS advanced stellarator were conducted in October 1988, after magnetic surface mapping. characteristics of device are described. During phase operation, 70 GHz ECF was used to generate and heat a 'currentless' which maintained quasi-steady state for typically 0.5 s. Effects configuration confinement measures deal with observed current (bootstrap ECF-driven current) investigated. Preliminary results transport analysis presented compared predictions models.
Sheared flows have been experimentally studied in TJ-II plasmas. In low-density ECH plasmas, sheared can be easily controlled by changing the plasma density, thereby allowing radial origin and evolution of edge velocity shear layer to studied. high density NBI heated plasmas a negative electric field is observed that dominated diamagnetic component. The increases at L–H transition an amount depends on magnetic configuration heating power. Magnetic configurations with without low order...
Laser irradiation at 193 nm of multilayer CH3Br physisorbed on LiF 30 K leads to both photofragmentation and photodesorption molecules. One-photon was observed leading broad velocity distributions for ejected CH3 Br. Fragments as fast those found in gas-phase were seen well collisionally slowed fragments. High energy (2 eV, four times the kinetic energy) Br fragments also due collisions with rebounding CH3. Collisionally molecules seen. A small fraction desorbed via a thermal process,...
Although the use of solid materials as targets divertor plasmas in magnetic fusion research is accepted standard solution for very challenging issue power and particle handling a reactor, generalized feeling that present options chosen ITER will not represent best choice reactor growing up. The problems found tungsten, selection target ITER, laboratory tests hot plasma devices suggest so. Even absence strong neutron irradiation expected issues like surface melting, droplet ejection,...
The first experimental campaign of the TJ-II stellarator has been conducted using electron cyclotron resonance heating (, ) with a pulse length . flexibility device used to study five different configurations varying plasma volume and rotational transform. In this paper, main results are presented and, in particular, influence plasma-wall interaction phenomena on confinement is briefly discussed.
Photolysis of C${\mathrm{H}}_{3}$Br on a brominated Ni(111) surface was observed. Cross-section values are reported for 0.5-, 1-, 2-, 3-, and 10-monolayer coverages. The observed cross sections photofragment times flight indicate that complete quenching the photolysis does not take place, photodynamics is strongly perturbed.
Mechanisms underlying the retention of fuel species in tokamaks with carbon plasma-facing components are presented, together estimates for corresponding tritium ITER. The consequential requirement new and improved schemes to reduce inventory is highlighted results ongoing studies into a range techniques removal rate ITER each case. Finally, an approach involving integration many operational schedule proposed as means extend period operations before major intervention required.
In the last campaign, TJ-II heliac has been operated under lithium-coated walls, representing first stellarator ever working these boundary conditions. Enhanced density control and discharge reproducibility, leading to drastic enlargement of operational window, have obtained. A strong decrease in recycling together with changes shot by fuelling characteristics wall particle inventory recorded. These changes, associated new scenario, had led a long-lasting good control. The conditions were...
Wall conditioning is essential in tokamak and stellarator research to achieve plasma performance reproducibility. This paper presents an overview of recent results, both from experiments present devices modelling, view with superconducting coils, focus on W7-X, JT-60SA ITER. In these devices, the coils stay energised throughout experimental day or week which demands for new techniques that work presence nominal field, addition proven methods such as baking, glow discharge (GDC) low-Z wall...
The inhibition and perturbations of surface photochemistry, due to the coupling excited state surface, are discussed as it pertains CH3 Br adsorbed on nickel. Photofragmentation was observed a brominated Ni(111) with fragmentation process being strongly perturbed at low coverages. attributed charge transfer processes. Direct photofragmentation well specific dissociative electron attachment channel. Cross section values reported for 193 248 nm.
Abstract The use of liquid metals (LMs) as plasma facing components in fusion devices was proposed early 1970 for a field reversed concept and inertial reactors. idea extensively developed during the APEX Project, at turn century, it is subject present biennial International Symposium on Lithium Applications (ISLA), whose fourth meeting took place Granada, Spain end September 2015. While metal flowing concepts were specially addressed USA research projects, embedding capillary porous system...
The 2nd International Symposium on Lithium Applications for Fusion Devices (ISLA-2011) was held 27–29 April 2011 at the Princeton Plasma Physics Laboratory (PPPL) with broad participation from community working aspects of lithium research fusion energy development. This is expanding rapidly in many areas including experiments magnetic confinement devices and a variety test stands, theory modeling developing innovative approaches. Overall, 53 presentations were given representing 26...
The use of lithium (Li) or tin (Sn) as a liquid metal plasma facing component is proposed solution to the high power load issue on divertor region nuclear fusion reactors. possibility these materials depends their compatibility with hydrogen plasmas. With purpose realizing deuterium retention studies, specimens pure Sn (99.999% Sn) and Li–Sn alloy (30 at.% Li) were exposed in ISTTOK edge plasma. Ex situ analysis samples was performed by means ion beam diagnostics. Nuclear reaction (NRA)...
The armor for future nuclear fusion reactors is one of the main areas research due to harsh conditions it will undergo. Thermal fatigue most serious damage, as cause any material fail even if heat and particle loads during reactor operation are always maintained low. In this work we have compared actual tungsten ITER tokamak with a new advanced material: reinforced by fibers (Wf/W). ITER-like W has shown small intergranular cracking at similar ones found in other devices: flux factor FHF =...
The magnitude of radial transport in magnetic confinement devices for controlled nuclear fusion suffers spontaneous bifurcations when specific system parameter values are exceeded. Here we show, the first time, that correlation length plasma potential becomes order machine size during edge bifurcation itself, quite unlike density fluctuations. mechanism governing development this bifurcation, leading to establishment an barrier, is still one main scientific conundrums facing community after...
This paper presents an overview of experimental results and progress made in investigating density control using Li-coating, transport L–H transitions TJ-II. The Li-coating changes drastically the plasma–wall interaction, decreasing recycling, enlarges substantially operational range device delaying appearance radiative collapse that happens for higher densities, which permits confinement properties much denser plasmas to be studied. Moreover, mode transition has only been achieved after...
This paper assesses the three-dimensional (3D) effects of edge magnetic field structure on divertor/scrape-off layer transport, based an inter-machine comparison experimental data and recent progress 3D transport simulation. The are elucidated as a consequence competition between transports parallel () perpendicular to field, in open lines cut by divertor plates, or islands. has strong impacts functions, such determination density regime, impurity screening detachment control. perturbation...