Abstract
Beryllium transport modeling was carried out in the trace impurity regime by SOLPS-ITER code for tokamak ITER. It is valuable for developing of diagnostics protection from beryllium deposition. TRIM reflection model and Bogdanskii formula sputtering model were applied. The idea is to show possibility of using this code for beryllium transport. This code has key advantage comparing to other codes, which study beryllium transport, because in it the main plasma and impurities are described self-consistently. Therefore, if beryllium affect the background plasma, only this code can take this effect into account. Test calculations were performed with suppressed sputtering yield by 10 times, to reach trace impurity regime. Main features of behavior of beryllium in the tokamak were studied, however under restriction of static wall conditions. Sources, sinks, fluxes and density distribution were determined. In this test calculation plasma state kept unchanged as expected. Distribution of impinging and absorbed fluxes on the outer divertor plate were established in the position of divertor diagnostics. Main ways for the further improvement are suggested.
Highlights
Finding new sources of energy is one of the most challenging problems these days
The simulations of beryllium transport by SOLPS-ITER code in the ITER chamber were started in order to estimate beryllium flux on diagnostics mirrors
The main source of beryllium is situated on a material wall, and the main sink is deposition on divertor targets
Summary
Finding new sources of energy is one of the most challenging problems these days. Fusion is a relatively reliable way to solve it. ITER is the most advanced project in this area. ITER is a tokamak, and it will be built with beryllium first wall and tungsten divertor [1]. Beryllium will be sputtered and redistributed in the vacuum chamber. Beryllium will deposit on the mirrors of ITER diagnostics. It is important to keep them clean during whole discharge to get correct data from diagnostics. One of the approaches to avoid this influence is so called cleaning discharge [2]. A beryllium flux, which cleaning discharge system can handle with, is strictly limited. There is no possibility to check this technology entirely on another setup, because of unique ITER parameters. The simulations of beryllium transport by SOLPS-ITER code in the ITER chamber were started in order to estimate beryllium flux on diagnostics mirrors
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