Spectroscopic characterisation of TCV divertor towards a detached regime

Chattez avec Graph Search

Posez n’importe quelle question sur les cours, conférences, exercices, recherches, actualités, etc. de l’EPFL ou essayez les exemples de questions ci-dessous.

AVERTISSEMENT : Le chatbot Graph n'est pas programmé pour fournir des réponses explicites ou catégoriques à vos questions. Il transforme plutôt vos questions en demandes API qui sont distribuées aux différents services informatiques officiellement administrés par l'EPFL. Son but est uniquement de collecter et de recommander des références pertinentes à des contenus que vous pouvez explorer pour vous aider à répondre à vos questions.

The Spherical Tokamak for Energy Production (STEP) is a prototype fusion power plant planned to be operational in the 2040s. STEP's interaction with the national grid and its responsiveness to demand hinges largely on the effective control of the energy re ...

One of the main milestones of the EUROfusion roadmap to fusion is the demonstrator reactor DEMO. Like ITER, the EU DEMO will be a large-scale tokamak with superconducting toroidal field (TF) coils to generate a strong magnetic field for plasma confinement. ...

This thesis investigates turbulence self-interaction and self-organization, with a particular focus on their role in triggering internal transport barriers (ITBs). ITBs, which are routinely observed in the core of tokamak experiments, represent an improved ...

The search for resonant mass bumps in invariant-mass distributions remains a cornerstone strategy for uncovering Beyond the Standard Model (BSM) physics at the Large Hadron Collider (LHC). Traditional methods often rely on predefined functional forms and e ...

Nuclear fusion presents a promising clean energy source to mitigate future energy crises, with magnetic confinement fusion well-positioned to provide a baseload scenario to power future reactors. The unmitigated power exhaust of such reactors threatens its ...

The performance of magnetic confinement fusion devices, such as tokamaks, is strongly correlated to the phenomena that occur in the boundary region of the plasma core that faces the wall of the device. The dominant cross-field transport mechanisms from the ...

Rapid inter-discharge simulation and optimization using the RAPTOR code have allowed the development of a reliable and reproducible early heating strategy for an advanced tokamak (AT) scenario on ASDEX Upgrade. Solving for electron heat and current diffusi ...

In order to cope with the decarbonization challenge faced by many countries, fusion is one of the few alternatives to fossil fuels for the production of electricity. Two devices invented in the middle of the previous century have emerged as the most promis ...

Negative triangularity (NT) scenarios in TCV have been compared to positive triangularity (PT) scenarios using the same plasma shapes foreseen for divertor tokamak test tokamak operations. The experiments provided a NT/PT L-mode pair and a PT H-mode with d ...

Local gyrokinetic simulations are used to model turbulent transport for the first time in a representative high-performance plasma discharge projected for the new JT-60SA tokamak. The discharge features a double-null separatrix, 41 MW of combined neutral b ...

MAST-U is equipped with on-axis and off-axis neutral beam injectors (NBI), and these external sources of super-Alfv & eacute;nic deuterium fast-ions provide opportunities for studying a wide range of phenomena relevant to the physics of alpha-particles in ...

Plasma turbulence plays a fundamental role in determining the performances of magnetic confinement fusion devices, such as tokamaks. Advances in computer science, combined with the development of efficient physical models, have significantly improved our u ...

In recent years a strong effort has been made to investigate disruption avoidance schemes in order to aid the development of integrated operational scenarios for ITER. Within the EUROfusion programme the disruptive H-mode density limit (HDL) has been studi ...

Carbon impurity transport is studied in the TCV tokamak using a charge exchange recombination diagnostic. TCVs flexible shaping capabilities were exploited to extend previous impurity transport studies to negative triangularity (delta < 0). A practical way ...

Plasmas with negative triangularity (NT) shape have been recently shown to be able to achieve H-mode levels of confinement in L-mode, avoiding detrimental edge localised modes. Therefore, this plasma geometry is now studied as a possible viable option for ...

The design point that had been chosen for EU DEMO in 2016 is reviewed here and a modification is proposed with a lower aspect ratio. Previously the same aspect ratio, A, was chosen for EU DEMO as in major tokamak experiments including ITER (A = 3.1), and, ...

The vast amount of computational studies on electrical conduction in solid-state electrolytes is not mirrored by comparable efforts addressing thermal conduction, which has been scarcely investigated despite its relevance to thermal management and (over)he ...

Combined high-fusion performance and long-pulse operation is one of the key integration challenges for fusion energy development in magnetic devices. Addressing these challenges requires an integrated vision of physics and engineering aspects with the purp ...

Phase contrast imaging (PCI) is an established and powerful technique for measuring density fluctuations in plasmas and has been successfully applied to several fusion devices. Rooted in a concept first developed for microscopy, PCI belongs to the category ...

The official Spherical Tokamak for Energy Production mission aims to demonstrate the ability to generate net electricity from fusion with the STEP Prototype Power plant. One of the key technological and engineering challenges in fusion power plants is mana ...

Spectroscopic characterisation of TCV divertor towards a detached regime

Chattez avec Graph Search

Fusion alpha power control optimisation using RAPTOR

Development of a High-Current Winding Pack for the Toroidal Field Coils of the EUROfusion Demonstrator Reactor

Gyrokinetic investigation of plasma turbulence self-organization at low magnetic shear in tokamaks

Automatizing the Search for Mass Resonances Using Bumpnet

Experimental study and interpretative modelling of the Power Exhaust in Configurations with Multiple X-Points in TCV

Divertor turbulence characterisation using Gas Puff Imaging in the TCV tokamak

Inter-discharge optimization for fast, reliable access to ASDEX Upgrade advanced tokamak scenario

Global fluid simulations of plasma turbulence in stellarators

Experiments and gyrokinetic simulations of TCV plasmas with negative triangularity in view of DTT operations

Gyrokinetic turbulence modeling of a high performance scenario in JT-60SA

Overview of fast particle experiments in the first MAST Upgrade experimental campaigns

Nonlinear simulation of plasma turbulence using a gyrokinetic moment-based approach

Disruption avoidance and investigation of the H-Mode density limit in ASDEX Upgrade

Study of impurity C transport and plasma rotation in negative triangularity on the TCV tokamak

First-principle based predictions of the effects of negative triangularity on DTT scenarios

Re-design of EU DEMO with a low aspect ratio

Thermal conductivity of Li 3 PS 4 solid electrolytes with ab initio accuracy

Long plasma duration operation analyses with an international multi-machine (tokamaks and stellarators) database

Tangentially viewing phase contrast imaging for turbulence measurements in toroidal fusion devices

Models implemented in the methodological approach to design the initial STEP first wall contour