Test program preparations of the ITER toroidal field model coil (TFMC)

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In this work, we compare physics-based dynamic exhaust models with frequency response measurements (FRMs) of the global particle dynamics in the Tokamak à Configuration Variable (TCV). The aim is to understand and model the experimental in-vessel dynamic response of plasma and neutrals to deuterium gas puff modulations with three models of varying fidelity: a 0D three chamber model (TCM); DIV1D, which models the edge plasma in 1D, and SOLEDGE3X for 2D-axisymmetric modeling. We find that the dynamic behavior

The neutral beam injection system is a key part of the TCV machine, which is actively exploited in different experimental campaigns. Development of a new ion-optical system (IOS) for the heating beam with intermediate particle energy (up to ~38 keV) has been performed, having obtained the beam simulation results by the IBSimu code. The validity of IBSimu calculations for the existing design concepts was cross-checked with the experimental data of beam profiles and divergence. The newly developed concept of

Utilizing integrated gate-commutated thyristor (IGCT) devices within resonant converters facilitates the realization of megawatt-scale direct current transformers (DCTs). The clamp circuitry, typically used to restrict the current slew rate at the turn-ON of the IGCT is not strictly needed, thanks to the presence of the resonant tank impedance. Yet, its operation and performance inside the resonant converters have never been investigated and quantified. The well-known hard-switching IGCT clamp working princ

[Neo-classical] Tearing Modes ([N]TMs) control is crucial in high-energy devices like ITER due to the disruptions that may cause potential machine damage. This work presents a real-time [N]TM control strategy for the ITER Plasma Control System (PCS), aiming to predict [N]TMs present and their characteristics, and apply stabilization using Electron Cyclotron Heating (ECH). Key components of the [N]TM control scheme are a predictor with extended co-MRE solver, coupled mode width and frequency dynamics, and a

A Diagnostic Neutral Beam Injector (DNBI) is operated on the TCV Tokamak since 2000. Over the years, the plasma source and the ion optical system have benefited from several upgrades, whereas the power supply system remained almost unchanged. DNBI operation is now compromised by the obsolescence of both the power components and the control infrastructure. To allow for a long term reliable operation, a complete renew of the power supplies set is ongoing. It includes a high-speed current source rated 500 A/10

Negative triangularity (NT) plasmas achieve enhanced confinement without edge localized modes nor the need to exceed the L-H heating power threshold. Removing this H-mode accessibility constraint opens a new region of parameter space: scenarios with low external heating power. Using simple zero dimensional power balance and standard empirical scaling laws for confinement, we analyze the impact of external heating on several different reactor-relevant devices (i.e. SPARC, MANTA, ITER and DEMO). We determine

Despite their wide-scale deployment and ability to make accurate high-frequency voltage measurements, communication network limitations have largely precluded the use of smart meters for real-time monitoring purposes in electric distribution systems. Although smart meter communication networks have limited bandwidth available per meter, they also have the ability to dedicate higher bandwidth to varying subsets of meters. Using this capability to enable real-time monitoring from smart meters, this paper prop

Objective: Develop an algorithm to decompose streamflow electrical conductivity signal into its “harmonics”, i.e. into the specific contribution of different ion species. Level: BS, Masters Description: The electrical conductivity (EC) of an aqueous solution is the capacity to transmit electrical current through the movement of charged ions. Typical major ions in natural waters are: H+, Na+, Ca2+, Mg2+, K+, Cl−, SO2−, NO− and HCO−. For a number of environmental applications, EC can be expr

We have successfully demonstrated the fabrication of self-actuating multilayer NEMS resonators including cantilevers and double clamped beams. Resonant sensors are widely used as precision mass sensors for the detection and quantification of small concentration of analyte molecules in a gaseous solution or bacteria from biological sample which requires extremely high mass sensitivity and responsivity of the resonant sensor. Nanofabrication techniques have enabled the use of ultrathin layers for the fabricat

Integration of nanowire structures in more complex platforms combining microfluidics and multiplexing aspects may complex the electrical readout process. In the present work, fabrication of Aluminium (Al) lines for electrical connections is attempted followed by their integration to nanofabricated Memristive Biosensors that target at the label- free detection of cancer biomarkers. In addition a computational study is carried out investigating the impact of the resistance introduced by the additional Al conn

Typical optimal controls of power systems, such as scheduling of generators, voltage control, losses reduction, have been so far commonly investigated in the domain of high-voltage transmission networks. However, during the past years, the increased connection of distributed energy resources (DERs) in power distribution systems results in frequent violations of operational constraints in these networks and has raised the importance of developing optimal control strategies specifically applied to these syste

Negative triangularity tokamak plasmas are subject of an increased interest both in existing experiments and in studies of core physics as well as power handling relevant to the fusion demonstration power reactor. The ideal MHD stability calculations for the negative triangularity plasma extend the investigation of the TCV tokamak beta limits and edge stability to double null shapes, lower aspect ratio and negative shear. In case of the negative triangularity, the 2nd stability access is closed for ballooni

The TORoidal Plasma EXperiment (TORPEX) is a Simple Magnetized Torus (SMT) where open helical magnetic field lines are obtained from the superposition of a small vertical component on the main toroidal field. The SMT configuration features the main driving mechanisms of plasma instabilities characterising the Scrape-Off Layer (SOL) of larger tokamak devices, making TORPEX a very attractive machine to perform fusion oriented studies of plasma turbulence. A new experimental set-up has been recently developed

The TORoidal Plasma EXperiment (TORPEX) is a basic plasma physics device where a Simple Magnetized Torus configuration (SMT) can be obtained superimposing a small vertical magnetic field component on the main toroidal field, resulting in open magnetic helical field lines. This configuration reproduces some of the main features of a tokamak plasma edge, including density and magnetic field gradient and curvature. In the last years, a complete study of electrostatic fluctuations and turbulence has been comple

We investigate the redistribution of the neutral beam driven current in the presence of small scale turbulence in the ITER steady-state scenario. Gyrokinetic simulations show that anomalous transport of beam ions can be larger than collisional estimates. T ...

This poster is an overview of work carried out on the design of the ITER high-frequency magnetic diagnostic coil (HF sensor). In the first part, the ITER requirements for the HF sensor are presented. In the second part, the ITER reference design of the HF sensor has been assessed and showed some potential weaknesses, which led us to the conclusion that alternative designs could usefully be examined. Several options have been explored, and are presented in the third part: (3.1) direct laser cutting a metalli

Modulation of power amplitude is a widespread to determine the radial absorption profile of externally launched power in fusion plasmas. There are many techniques to analyze the plasma response to such a modulation. The break-in-slope (BIS) analysis can draw an estimated power deposition profile for each power step up. In this paper, the BIS analysis is used to monitor the power deposition location of one or two EC power beams simultaneously in a non-stationary plasma being displaced vertically in the TCV t

Monitoring units for the measurement of high frequencyvoltage transients have been in operation at three different busses of an Italian medium voltage (MV) distribution feeder, mainly composed by overhead lines, in March 2007 – August 2008. The feeder is located in a region characterized by a high ground flash density value (4 flashes/km2/yr); many of the recorded voltage transients may be correlated with the lightning events detected for the same region by the Lightning Location System (LLS) CESISIRF. The

Heat loads on the JET MarkIIHD divertor are measured by IR thermography in high triangularity plasmas with edge conditions of advanced tokamak scenarios (AT). AT scenarios operate at low density (n(e,av) < 5 x 10(19) m(-3) at JET) to maximise the non inductive current drive, leading to high target temperature (20 < T-e < 40 eV), hence high heat loads. Comparisons with a typical baseline inductive scenario (n(e,av) similar or equal to 10 x 10(19) m(-3)), show that for similar input power (similar or equal to

Thin films are very promising for the design of novel and efficient Fault Current Limiter (FCL) made of high-temperature superconductors (HTS). However, their thermal and highly non-linear electromagnetic behavior in the presence of over-critical currents is crucial to their use in future electrical grid. In this paper, we propose a numerical approach to solve magneto-thermal models for geometries of high aspect ratio. The used electromagnetic formulation, inspired in good part from the work of Brambilla et

Test program preparations of the ITER toroidal field model coil (TFMC)

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A multi-model system-identification comparison with the global particle dynamics in TCV

Ion Optics With Oval Apertures for TCV NBI

Comprehensive Modeling and Analysis of the IGCT Clamp Circuit in Resonant Converters

Progress on [N]TM modelling and control in the ITER Plasma Control System design

High Voltage Modulator for the TCV Diagnostic Neutral Beam Injector

On the feasibility of Ohmically heated negative triangularity tokamak power plants

Strategic Electric Distribution Network Sensing via Spectral Bandits

Searching for patterns in the electrical conductivity signal of stream waters

Design and Fabrication of Multilayer Piezoelectric NEMS Resonators

Resistance impact by long connections on electrical behavior of integrated Memristive Biosensors

Optimal voltage control processes in active distribution networks

Stability limits for tokamak plasma with negative triangularity

Study of plasma fluctuations in new closed flux-surface configurations of the TORPEX experiment

First results on the plasma fluctuations of the TORPEX device in the new magnetic field configurations

Numerical modelling of electromagnetic turbulent transport of energetic ions in burning plasmas

Design of the ITER High-Frequency Magnetic Diagnostic Coils

Simultaneous Power Deposition Detection of Two EC Beams with the BIS Analysis in Moving TCV Plasmas

Voltage Transients in a Distribution Network Correlated with Events Identified by a Lightning Location System

Divertor heat load in ITER-like advanced tokamak scenarios on JET

2D Magneto-Thermal Modeling of Coated High-Temperature Superconductors