A5015814334- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Iterative Learning Control Systems
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Atomic and Subatomic Physics Research
- Aerodynamics and Fluid Dynamics Research
- Nuclear Materials and Properties
- Engineering Applied Research
- Radiative Heat Transfer Studies
- Silicon Carbide Semiconductor Technologies
- Real-time simulation and control systems
- Advanced Data Storage Technologies
- Surface Roughness and Optical Measurements
- Radiation Detection and Scintillator Technologies
- Turbomachinery Performance and Optimization
- Combustion and flame dynamics
- Particle Detector Development and Performance
- Network Security and Intrusion Detection
- Mechanical Engineering and Vibrations Research
- Refrigeration and Air Conditioning Technologies
General Atomics (United States)
2020-2024
DIII-D National Fusion Facility
2022
Fusion (United States)
2022
ITER
2018-2020
École Polytechnique Fédérale de Lausanne
2017-2019
Super Stars Literacy
2015-2016
University of Delhi
2011
Indian Institute of Technology Kanpur
1983
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...
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...
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...
Abstract Through predictive modeling validated by a series of experiments on DIII-D, the vertical stability low β diverted plasmas with strong negative triangularity (NT) ( <?CDATA $\delta\sim-0.6$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mi>δ</mml:mi> <mml:mo>∼</mml:mo> <mml:mo>−</mml:mo> <mml:mn>0.6</mml:mn> </mml:math> ) is assessed. As result their unique magnetic geometry, NT feature larger Shafranov shifts and more elongated inner flux surfaces...
Abstract DIII-D physics research addresses critical challenges for the operation of ITER and next generation fusion energy devices. This is done through a focus on innovations to provide solutions high performance long pulse operation, coupled with fundamental plasma understanding model validation, drive scenario development by integrating core boundary plasmas. Substantial increases in off-axis current efficiency from an innovative top launch system EC power, pressure broadening Alfven...
Deposition and fuel retention profiles in low power hydrogen L-mode plasmas neon (Ne) seeded ITER DT burning have been investigated. Two different Ne plasma backgrounds with varying sub-divertor neutral pressures but the same impurity concentration are considered, representing high recycling partially detached divertor solutions. The 2D SOLPS numerical grid does not extend all way to wall surfaces so that an extrapolation of background is required performed using a second simulation stage...
Abstract ERO2.0 is a recently developed Monte‐Carlo code for modelling global erosion and redeposition in fusion devices. We report here on the code's application to ITER studying of beryllium (Be) first wall armour under burning plasma steady state diverted conditions. An important goal study provide synthetic signals design two key diagnostics: main chamber visible spectroscopy laser in‐vessel viewing systems. The simulations are performed using toroidally symmetric backgrounds obtained by...
A novel plasma position and shape controller has been developed for the highly flexible shaping poloidal-field coil set of TCV tokamak, to aid in precise control advanced configurations such as negative-triangularity plasmas, snowflake super-X divertors, doublets. This work follows relies on deployment a new, sub-ms, real-time magnetic equilibrium-reconstruction algorithm. The formulation ensures flexibility through an ordering controlled variables from most easily least controlled, while...
Abstract Real-time magnetic control has been developed to deliver precise of multiple plasma shape parameters for advanced divertor configurations, including double-null, Super-X, X-point target and X-divertor the first time on MAST Upgrade (MAST-U) spherical tokamak. Successful real-time equilibrium different variables accomplished in 2022–2023 MAST-U experimental campaign configurations. Application boundary reconstruction algorithm, LEMUR, is described compared with off-line diagnostic...
Abstract Recent results from MAST Upgrade are presented, emphasising understanding the capabilities of this new device and deepening key physics issues for operation ITER design future fusion power plants. The impact MHD instabilities on fast ion confinement have been studied, including first observation losses correlated with Compressional Global Alfvén Eigenmodes. High-performance plasma scenarios developed by tailoring early current ramp phase to avoid internal reconnection events,...
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...
Abstract Detachment control based on ion saturation current I sat measurements from Langmuir probes (LPs) is implemented in the KSTAR tokamak and shown to be capable of following dynamic constant target trajectories with good accuracy, H-mode, by moderating flow rate nitrogen or deuterium. controllers normalize order form attachment fraction ( A frac ) as their parameter. The implementation differs previous work that it continuously calculates a model for attached uses denominator , whereas...
The beryllium (Be) first wall energy deposition and melt damage profiles resulting from the current quench phase of an unmitigated, 5 MA/1.8 T upward vertical displacement event for ITER are investigated. Time dependent 2D magnetic flux calculated with DINA code used as input SMITER 3D field line tracing software. maps wetted area perpendicular heat show that majority occurs on upper panels #8 #9. simulations predict surfaces FWPs #9 at end ∼450 ms quench. surface generated by in MEMOS-U...
A control-oriented approach, based on real-time equilibrium reconstruction, has been developed to monitor power fluxes ITER plasma-facing components (PFC). The model describes the deposited heat flux as a poloidal function with two main input parameters: exhausted across plasma boundary and scrape-off layer width. module containing weighting factors accounts for real PFC 3D geometry. These are obtained using new sophisticated GUI interface, SMITER, hosting magnetic field line tracing code...
Magnetic diagnostics in tokamaks are key to plasma equilibrium control (plasma current, shape, and position) amelioration of instabilities. Thus, real-time identification the anomalous sensor is mandatory. A new system based on autoencoder (AE) neural networks (NNs) for anomaly detection magnetics signals, including both flux loops magnetic probes, has been successfully implemented (PCS) DIII-D tokamak. The AE NN trained over 4000 discharges, with an optimized latent space representation...
Abstract The DIII-D tokamak has elucidated crucial physics and developed projectable solutions for ITER fusion power plants in the key areas of core performance, boundary heat particle transport, integrated scenario operation, with closing core-edge integration knowledge gap being overarching mission. New experimental validation high-fidelity, multi-channel, non-linear gyrokinetic turbulent transport models provides strong confidence it will achieve Q ⩾ 10 operation. Experiments identify...
Abstract A new controller has been developed with help of the flexible divertor poloidal-field coil set DIII-D tokamak, to aid in precise control flux expansion scrape-off layer. The single-input multiple-output architecture ensures flexibility through a complementary orthogonal actuator direction guarantee minimum effect on existing controlled variables, e.g. radial and vertical position X-point. non-linear free-boundary simulation code (GSevolve) is used for simulating closed-loop response...
The novel plasma position and shape controller of the TCV tokamak aids in precise control complex configurations such as snowflake (SF) divertors. ability design to simultaneously position, shape, divertor leg X-points is extended various SF configurations. unique feature ordering controlled variables from most easily least controlled, while respecting hardware limits on poloidal-field coil currents, exploited particular provide reliable equilibria with closely spaced X-points, approaching...