Publication

SOLPS simulation of TCV divertor leg length studies

Mirko Wensing
2018
Conference paper

Abstract

This contribution uses TCV experiments with varying divertor configurations to investigate the particle- and heat cross-field transport within the scrape-off layer, which greatly determines the peak heat flux on the plasma-facing components. The proximity of expected peak heat fluxes to the material limits for ITER raises the necessity of obtaining a quantitative understanding of the mechanisms that determine the heat flux profiles on the divertor plates. Target heat flux profiles are often described by a truncated exponential profile with a decay length λ convoluted with a Gaussian of width S, which are interpreted as broadening due to diffusive transport upstream and in the divertor regions, respectively [1]. It is shown that an increase of the poloidal divertor leg length Ldiv (~ factor 3) leads to an unexpected increase of λ , while having little effect on S [2]. The aim of this study is to reproduce the experimental findings quantitatively using the SOLPS code package.

Official source

https://infoscience.epfl.ch/record/264140?ln=en

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Ontological neighbourhood

Physics

Plasma physics: Fusion power

Related concepts (21)

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.

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.

Tokamak

A tokamak (ˈtoʊkəmæk; токамáк) is a device which uses a powerful magnetic field to confine plasma in the shape of a torus. The tokamak is one of several types of magnetic confinement devices being developed to produce controlled thermonuclear fusion power. , it was the leading candidate for a practical fusion reactor. Tokamaks were initially conceptualized in the 1950s by Soviet physicists Igor Tamm and Andrei Sakharov, inspired by a letter by Oleg Lavrentiev. The first working tokamak was attributed to the work of Natan Yavlinsky on the T-1 in 1958.

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