Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device. (October 2022)

• Record Type: Journal Article
• Authors: Shoji, M.; Kawamura, G.; Romazanov, J.; Kirschner, A.; Masuzaki, S.; Tokitani, M.; Brezinsek, S.
• Is Part Of: Nuclear materials and energy. Volume 33(2022)
• Publication Date: 2022-10
• Subjects: ERO2.0 -- Tungsten migration -- Plasma-wall interaction -- EMC3-EIRENE -- LHD; LHD The Large Helical Device; Nuclear energy -- Periodicals; Nuclear fuels -- Periodicals; Nuclear reactors -- Materials -- Periodicals; Radioactive substances -- Periodicals; 621.4833
• DOI: 10.1016/j.nme.2022.101257
• Languages: English
• ISSNs: 2352-1791

Abstract

Highlights: Migration of tungsten sputtered from a tungsten-coated divertor plate was investigated. The simulation reasonably explained the observed localization of tungsten migration. The simulation reproduced observed tungsten deposition in the private side. The simulated tungsten density on the plasma wetted areas disagreed with observation. Abstract: Tungsten migration in the open divertor region in the Large Helical Device is analyzed for validating the three-dimensional plasma-wall interaction simulation code ERO2.0. The ERO2.0 simulation reproduced the measurement of localized tungsten migration from a tungsten-coated divertor plate installed in the inboard side of the torus. The simulation also explained the measurement of the high tungsten areal density in the private side on a carbon divertor plate, next to the tungsten-coated divertor plate, by the tungsten prompt redeposition in plasma discharges for a low magnetic field strength in a counterclockwise toroidal direction. However, the simulation disagreed with the measurement of low tungsten areal density on the plasma-wetted areas on the carbon divertor plates, which indicated that the actual erosion rate of the redeposited tungsten should be much higher than that used in the ERO2.0 code.