T.C. Blanken

ORCID: 0000-0003-3198-7170
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About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Superconducting Materials and Applications
  • Ionosphere and magnetosphere dynamics
  • Particle accelerators and beam dynamics
  • Nuclear reactor physics and engineering
  • Plasma Diagnostics and Applications
  • Iterative Learning Control Systems
  • Laser-Plasma Interactions and Diagnostics
  • Anomaly Detection Techniques and Applications
  • High-pressure geophysics and materials
  • Cold Fusion and Nuclear Reactions
  • Machine Learning in Healthcare
  • Power Line Inspection Robots
  • earthquake and tectonic studies
  • Fault Detection and Control Systems
  • Distributed systems and fault tolerance
  • Advanced Sensor and Control Systems
  • Nuclear Engineering Thermal-Hydraulics
  • Nuclear Physics and Applications
  • Embedded Systems and FPGA Design
  • Advanced Electrical Measurement Techniques
  • Particle Detector Development and Performance
  • Real-time simulation and control systems
  • Atomic and Subatomic Physics Research

Eindhoven University of Technology
2015-2025

Max Planck Institute for Plasma Physics
2024

Systems Technology (United States)
2017-2019

Dutch Institute for Fundamental Energy Research
2015-2017

Institute for Atomic and Molecular Physics
2015

École Polytechnique Fédérale de Lausanne
2015

Abstract The most efficient and promising operational regime for the International Thermonuclear Experimental Reactor tokamak is high-confinement mode. In this regime, however, periodic relaxations of plasma edge can occur. These edge-localized modes pose a threat to integrity fusion device. Here we reveal strong impact energetic ions on spatio-temporal structure in tokamaks using nonlinear hybrid kinetic–magnetohydrodynamic simulations. A resonant interaction between fast at electromagnetic...

10.1038/s41567-024-02715-6 article EN cc-by Nature Physics 2025-01-01

Abstract The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system address critical issues in preparation for ITER a fusion power plant. For the 2019–20 campaign configurational flexibility has been enhanced with installation of removable divertor gas baffles, diagnostic capabilities an extensive set upgrades new dual frequency gyrotrons. baffles reduce coupling between main chamber allow detailed...

10.1088/1741-4326/ac369b article EN cc-by Nuclear Fusion 2022-03-01

The TCV tokamak is augmenting its unique historical capabilities (strong shaping, strong electron heating) with ion heating, additional heating compatible high densities, and variable divertor geometry, in a multifaceted upgrade program designed to broaden operational range without sacrificing fundamental flexibility. rooted three-pronged approach aimed at ITER support, explorations towards DEMO, research. A 1 MW, tangential neutral beam injector (NBI) was recently installed promptly...

10.1088/1741-4326/aa6412 article EN cc-by Nuclear Fusion 2017-06-23

Abstract The research program of the TCV tokamak ranges from conventional to advanced-tokamak scenarios and alternative divertor configurations, exploratory plasmas driven by theoretical insight, exploiting device’s unique shaping capabilities. Disruption avoidance real-time locked mode prevention or unlocking with electron-cyclotron resonance heating (ECRH) was thoroughly documented, using magnetic radiation triggers. Runaway generation high- Z noble-gas injection runaway dissipation...

10.1088/1741-4326/ab25cb article EN cc-by Nuclear Fusion 2019-05-30

Abstract Experiments on ASDEX Upgrade (AUG) in 2021 and 2022 have addressed a number of critical issues for ITER EU DEMO. A major objective the AUG programme is to shed light underlying physics confinement, stability, plasma exhaust order allow reliable extrapolation results obtained present day machines these reactor-grade devices. Concerning pedestal physics, mitigation edge localised modes (ELMs) using resonant magnetic perturbations (RMPs) was found be consistent with reduction linear...

10.1088/1741-4326/ad249d article EN cc-by Nuclear Fusion 2024-01-31

Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle role plasma fueling shape for onset small ELM regimes. On both devices, regimes with high confinement are achieved if only two conditions fulfilled at same time. Firstly, density separatrix must be large enough (), leading pressure profile flattening separatrix, which stabilizes type-I ELMs. Secondly, magnetic configuration close double null (DN), reduction shear in...

10.1088/1741-4326/ab2211 article EN Nuclear Fusion 2019-05-16

Abstract The ASDEX Upgrade (AUG) programme, jointly run with the EUROfusion MST1 task force, continues to significantly enhance physics base of ITER and DEMO. Here, full tungsten wall is a key asset for extrapolating future devices. high overall heating power, flexible mix comprehensive diagnostic set allows studies ranging from mimicking scrape-off-layer divertor conditions DEMO at density fully non-inductive operation ( q 95 = 5.5, ) low density. Higher installed electron cyclotron...

10.1088/1741-4326/ab18b8 article EN cc-by Nuclear Fusion 2019-04-12

Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat particle loads on wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research ASDEX Upgrade (AUG), MAST TCV. This multi-machine approach within EU-MST, covering wide parameter range, instrumental progress in field, as ITER DEMO core/pedestal SOL parameters are not achievable simultaneously present day devices. A two prong adopted. On one...

10.1088/1741-4326/aa6084 article EN cc-by Nuclear Fusion 2017-06-28

One main programme topic at the ASDEX Upgrade all-metal-wall tokamak is development of a high-density regime with central densities reactor grade level while retaining high-confinement properties. This required appropriate control techniques capable coping pellet tool, powerful means fuelling but one which presented challenges to system for handling related perturbations. Real-time density profile was demonstrated, raising core well above Greenwald edge in order avoid confinement losses....

10.1088/1741-4326/aaa339 article EN cc-by Nuclear Fusion 2017-12-20

Abstract An overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling AUG discharges was established which able to reproduce experimental H-mode plasma profiles based on engineering parameters only. In center, theoretical predictions current redistribution by a dynamo effect were confirmed experimentally. For core transport, stabilizing fast ion distributions turbulent transport shown be important explain isotope and...

10.1088/1741-4326/ac207f article EN cc-by Nuclear Fusion 2021-08-24

The Alfvén instability nonlinearly excited the energetic-particle-driven geodesic acoustic mode on ASDEX-Upgrade tokamak, as demonstrated experimentally. mechanism of excitation and nonlinear evolution is not yet fully understood. In present work, a first-principles simulation using MEGA code investigated properties in both linear growth saturated phases. Here we show that successfully reproduced coexistence these two modes, agreed with experimental results well. Conclusive evidence showed...

10.1038/s41598-024-82577-3 article EN cc-by-nc-nd Scientific Reports 2025-01-07

Abstract On the basis of several recent breakthroughs in fusion research, many activities have been launched around world to develop power plants on fastest possible time scale. In this context, high-fidelity simulations plasma behavior large supercomputers provide one main pathways accelerating progress by guiding crucial design decisions. When it comes determining energy confinement a magnetic device, which is key quantity interest, gyrokinetic turbulence are considered approach choice –...

10.1038/s41467-025-56997-2 article EN cc-by Nature Communications 2025-03-15

The successful performance of a model predictive profile controller is demonstrated in simulations and experiments on the TCV tokamak, employing test environment. Stable high-performance tokamak operation hybrid advanced plasma scenarios requires control over safety factor (q-profile) kinetic parameters such as beta. This demands to establish reliable routines presently operational tokamaks.

10.1088/1741-4326/aa8c48 article EN cc-by Nuclear Fusion 2017-09-13

An overview of the preliminary design ITER plasma control system (PCS) is described here, which focusses on needs for 1st and early operation in hydrogen/helium (H/He) up to a current 15 MA with moderate auxiliary heating power low confinement mode (L-mode). Candidate schemes basic magnetic control, including divertor kinetic electron density gas puffing pellet injection, were developed. Commissioning systems included as well support functions stray field topology real-time boundary...

10.1088/1741-4326/aa8177 article EN Nuclear Fusion 2017-07-23

Plasma density control for next generation tokamaks, such as ITER, is challenging because of multiple reasons. The response the usual gas valve actuators in future, larger fusion devices, might be too slow feedback control. Both pellet fuelling and use feedforward-based may help to solve this problem. Also, tight limits arise during ramp-up, due operational related divertor detachment radiative collapses. As number shots available controller tuning will limited paper, iterative learning...

10.1088/1741-4326/aa95ce article EN cc-by Nuclear Fusion 2017-10-25

The control of 2/1 neoclassical tearing modes (NTMs) with electron cyclotron (EC) waves has been studied both experimentally and numerically on TCV. Dynamic evolutions NTMs along time-varying deposition locations the beam have in detail. prevention by means preemptive EC (i.e. is switched before mode onset) also explored. A small sinusoidal sweeping full amplitude 0.07 (normalized to minor radius) added two experiments facilitate comparison between NTM stabilization prevention. It shown that...

10.1088/1741-4326/ab1e1e article EN Nuclear Fusion 2019-04-30

Abstract In tokamaks, a leading platform for fusion energy, periodic filamentary plasma eruptions known as edge-localized modes occur in plasmas with high-energy confinement and steep pressure profiles at the edge. These could damage tokamak wall but can be suppressed using small three-dimensional magnetic perturbations. Here we demonstrate that these perturbations change topology just inside gradient region of We identify signatures island, their observation is linked to suppression modes....

10.1038/s41567-024-02666-y article EN cc-by Nature Physics 2024-10-28

A key feature of the new digital plasma control system installed on TCV (Tokamak à Configuration Variable) tokamak is its possibility to rapidly design, test and deploy real-time algorithms.It accommodates hundreds diagnostic inputs actuator outputs, offers design advanced algorithms with better knowledge state coherently all actuators, including poloidal field coils, gas valves, gyrotron powers launcher angles electron cyclotron heating current drive together triggering signals.It...

10.1088/1741-4326/aa6120 article EN Nuclear Fusion 2017-03-17

In ITER and DEMO, various control objectives related to plasma must be simultaneously achieved by the system (PCS), in both normal operation as well off-normal conditions. The PCS act on events deviations from target scenario, since certain sequences (chains) of can precede disruptions. It is important that these decisions are made while maintaining a coherent prioritization between real-time tasks ensure high-performance operation.

10.1088/1741-4326/aaf451 article EN cc-by Nuclear Fusion 2018-11-27
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