P.C. de Vries
A5012782943- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Virus-based gene therapy research
- Physics of Superconductivity and Magnetism
- Mesenchymal stem cell research
- Immune Cell Function and Interaction
- Pluripotent Stem Cells Research
- Gyrotron and Vacuum Electronics Research
- Solar and Space Plasma Dynamics
- Hematopoietic Stem Cell Transplantation
- Nuclear Engineering Thermal-Hydraulics
- Migraine and Headache Studies
- Computational Fluid Dynamics and Aerodynamics
- High-Energy Particle Collisions Research
- Silicon Carbide Semiconductor Technologies
- Cytokine Signaling Pathways and Interactions
- Mast cells and histamine
- Viral Infectious Diseases and Gene Expression in Insects
ITER
2015-2024
Institut Méditerranéen d’Océanologie
2019
Institute for Atomic and Molecular Physics
1999-2014
Dutch Institute for Fundamental Energy Research
2012-2014
Japan External Trade Organization
2014
Culham Centre for Fusion Energy
2004-2013
Culham Science Centre
2004-2013
University of California, Davis
2010-2013
Forschungszentrum Jülich
1997-2012
Plasma (Russia)
2011
Type-I edge-localized modes (ELMs) have been mitigated at the JET tokamak using a static external $n=1$ perturbation field generated by four error correction coils located far from plasma. During application of ELM frequency increased factor 4 and amplitude ${\mathrm{D}}_{\ensuremath{\alpha}}$ signal decreased. The energy loss per normalized to total stored energy, $\ensuremath{\Delta}W/W$, dropped values below 2%. Transport analyses shows no or only moderate (up 20%) degradation confinement...
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.
Abstract The objectives of NSTX-U research are to reinforce the advantages STs while addressing challenges. To extend confinement physics low- A , high beta plasmas lower collisionality levels, understanding transport mechanisms that set performance and pedestal profiles is being advanced through gyrokinetic simulations, reduced model development, comparison NSTX experiment, as well improved simulation RF heating. develop stable non-inductive scenarios needed for steady-state operation,...
Experiments were carried out in the JET tokamak to determine critical ion temperature inverse gradient length (R/LTi=R|nablaTi|/Ti) for onset of modes and stiffness Ti profiles with respect deviations from value. Threshold have been compared linear nonlinear predictions gyrokinetic code GS2. Plasmas higher values toroidal rotation show a significant increase R/LTi, which is found be mainly due decrease level. This finding has implications on extrapolation future machines present day results...
Abstract WEST is an MA class superconducting, actively cooled, full tungsten (W) tokamak, designed to operate in long pulses up 1000 s. In support of ITER operation and DEMO conceptual activities, key missions are: (i) qualification high heat flux plasma-facing components integrating both technological physics aspects relevant particle exhaust conditions, particularly for the monoblocks foreseen divertor; (ii) integrated steady-state at confinement, with a focus on power issues. During phase...
Pluripotent hematopoietic stem cells (PHSC) are very rare whose functional capabilities can only be analyzed indirectly. For a better understanding and possible manipulation of mechanisms that regulate self-renewal commitment to differentiation PHSC, it is necessary purify these develop assays for their growth in vitro. In the present study, rapid simple, widely applicable procedure highly day 14 spleen colony-forming (day CFU-S) described. Low density bone marrow (rho less than or equal...
The newly installed electron cyclotron emission imaging diagnostic on ASDEX Upgrade provides measurements of the 2D temperature dynamics with high spatial and temporal resolution. An overview technical experimental properties system is presented. These are illustrated by edge localized mode reversed shear Alfvén eigenmode, showing both advantage having a two-dimensional (2D) measurement, as well some limitations measurements. Furthermore, application singular value decomposition powerful...
In the recent JET experimental campaigns with new ITER-like wall (JET-ILW), major progress has been achieved in characterization and operation of H-mode regime metallic environments: (i) plasma breakdown at first attempt X-point L-mode recovered a few days operation; (ii) stationary stable type-I ELMy H-modes βN ∼ 1.4 have low high triangularity shape plasmas are showing that their operational domain H = 1 is significantly reduced JET-ILW mainly because need to inject large amount gas (above...
Key plasma physics and real-time control elements needed for robustly stable operation of high fusion power discharges in ITER have been demonstrated recent research worldwide.Recent analysis has identified the current density profile as main drive disruptive instabilities simulating ITER's baseline scenario with low external torque.Ongoing development model-based active magnetohydrodynamic is improving stability multiple scenarios.Significant advances made toward physicsbased prediction...
Abstract In magnetic fusion devices, error field (EF) sources, spurious perturbations, need to be identified and corrected for safe stable (disruption-free) tokamak operation. Within Work Package Tokamak Exploitation RT04, a series of studies have been carried out test the portability novel non-disruptive method, designed tested in DIII-D (Paz-Soldan et al 2022 Nucl. Fusion 62 126007), perform an assessment model-based EF control strategies towards their applicability ITER. this paper,...
In 2003, the performance of 'hybrid' regime was successfully validated in JET experiments up to βN = 2.8 at low toroidal field (1.7 T), with plasma triangularity and normalized Larmor radius (ρ*) corresponding identical ASDEX Upgrade discharges. Stationary conditions have been achieved fusion figure merit ( ) reaching 0.42 q95 3.9. The discharges show similar MHD, edge current profile behaviour, when compared Upgrade. addition, extended hybrid scenario operation higher 2.4 T lower ρ* towards...
The disruption rate (the percentage of discharges that disrupt) in JET was found to drop steadily over the years. Recent campaigns (2005–2007) show a yearly averaged only 6% while from 1991 1995 this often higher than 20%. Besides rate, so-called disruptivity, or likelihood depending on plasma parameters, has been determined. disruptivity plasmas be significantly close three main operational boundaries for tokamaks; low- q , high density and β-limit. frequency at which operated density-limit...
To consolidate International Thermonuclear Experimental Reactor (ITER) design choices and prepare for its operation, Joint European Torus (JET) has implemented ITER's plasma facing materials, namely, Be the main wall W in divertor. In addition, protection systems, diagnostics, vertical stability control were upgraded heating capability of neutral beams was increased to over 30 MW. First results confirm expected benefits limitations all metal components (PFCs) but also yield understanding...
Abstract The amplitude of locked instabilities, likely magnetic islands, seen as precursors to disruptions has been studied using data from the JET, ASDEX Upgrade and COMPASS tokamaks. It was found that thermal quench, often initiates disruption, is triggered when reached a distinct level. This information can be used determine thresholds for simple disruption prediction schemes. measured in part depends on distance perturbation measurement coils. Hence threshold mode location (i.e. rational...
The inboard limiters for ITER were initially designed on the assumption that parallel heat flux density in scrape-off layer (SOL) could be approximated by a single exponential with decay length λq. This was found not to adequate 2012, when infra-red (IR) thermography measurements inner column during JET limiter discharges clearly revealed presence of narrow channel adjacent last closed surface. near-SOL occurs λq ∼ few mm, much shorter than main SOL λq, and can raise at apex factor up ∼4...
This paper revisits a number of key aspects plasma initiation, aiming to clarify concepts, provide definitions and improve understanding, in view ITER First Plasma operation. It shows that size matters breakdown initiation differ larger devices. The large thick conductive vessel slows down the prefill process, development toroidal electric field affects dynamics poloidal magnetic at breakdown. vacuum requires more than 1 s for gas spread over vessel. field, applied ionize gas, by about...