Publication

SOLPS-ITER simulations of the TCV divertor upgrade

Basil Duval, Holger Reimerdes, Christian Gabriel Theiler, Artur Perek, Marco Wischmeier, Davide Galassi, Kevin Henricus Annemarie Verhaegh, Mirko Wensing
2019
Journal Articles

Abstract

The effect of the upcoming TCV divertor upgrade on the distribution of neutrals and the onset of detachment is studied using 2D transport code simulations. The divertor upgrade is centered around the installation of a gas baffle to form a divertor chamber of variable closure. SOLPS- ITER simulations predict that the baffle geometry selected to be installed in TCV in 2019 increases the divertor neutral density by a factor ∼5 and the neutral compression by one order of magnitude in typical TCV single null, Ohmic heated scenarios (330 kW). The compression increases further with the addition of auxiliary heating systems (1.2 MW). Simulations show that volumetric power losses in the divertor increase giving access to deeper detachment for given upstream densities and heating power. Predictions for observations by various TCV diagnostics, including baratrons, divertor spectrometer and visible camera systems, are presented to guide the experimental verification of the efficiency of the divertor baffles.

Official source

https://infoscience.epfl.ch/entities/publication/a1c2103b-7530-40da-ae81-fcb9c7866bb2

About this result

This page is automatically generated and may contain information that is not correct, complete, up-to-date, or relevant to your search query. The same applies to every other page on this website. Please make sure to verify the information with EPFL's official sources.

Graph Chat

Chat with Graph Search

Ask any question about EPFL courses, lectures, exercises, research, news, etc. or try the example questions below.

DISCLAIMER: The Graph Chatbot is not programmed to provide explicit or categorical answers to your questions. Rather, it transforms your questions into API requests that are distributed across the various IT services officially administered by EPFL. Its purpose is solely to collect and recommend relevant references to content that you can explore to help you answer your questions.

Basil Duval, Holger Reimerdes, Christian Gabriel Theiler, Artur Perek, Marco Wischmeier, Davide Galassi, Kevin Henricus Annemarie Verhaegh, Mirko Wensing
2019
Journal Articles

Abstract

Official source

https://infoscience.epfl.ch/entities/publication/a1c2103b-7530-40da-ae81-fcb9c7866bb2

About this result

Related concepts (32)

Magnetic confinement fusion

Magnetic confinement fusion is an approach to generate thermonuclear fusion power that uses magnetic fields to confine fusion fuel in the form of a plasma. Magnetic confinement is one of two major branches of fusion energy research, along with inertial confinement fusion. The magnetic approach began in the 1940s and absorbed the majority of subsequent development. Fusion reactions combine light atomic nuclei such as hydrogen to form heavier ones such as helium, producing energy.

Electric heating

Electric heating is a process in which electrical energy is converted directly to heat energy. Common applications include space heating, cooking, water heating and industrial processes. An electric heater is an electrical device that converts an electric current into heat. The heating element inside every electric heater is an electrical resistor, and works on the principle of Joule heating: an electric current passing through a resistor will convert that electrical energy into heat energy.

Plasma-facing material

In nuclear fusion power research, the plasma-facing material (or materials) (PFM) is any material used to construct the plasma-facing components (PFC), those components exposed to the plasma within which nuclear fusion occurs, and particularly the material used for the lining the first wall or divertor region of the reactor vessel. Plasma-facing materials for fusion reactor designs must support the overall steps for energy generation, these include: Generating heat through fusion, Capturing heat in the first wall, Transferring heat at a faster rate than capturing heat.

Related publications (31)

SOLPS-ITER simulations of the TCV divertor upgrade

Chat with Graph Search

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

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

Scenario optimization for the tokamak ramp-down phase in RAPTOR: A. Analysis and model validation on ASDEX Upgrade