@article{oai:nifs-repository.repo.nii.ac.jp:00011561,
 author = {SHOJI,  Mamoru and KAWAMURA,  Gakushi and ROMAZANOV, Juri and KIRSCHNER, Andreas and MASUZAKI,  Suguru and TOKITANI,  Masayuki and BREZINSEK, Sebastijan},
 issue = {October 2022},
 journal = {Nuclear Materials and Energy},
 month = {Sep},
 note = {0000-0003-0655-7347, 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.},
 title = {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},
 volume = {33},
 year = {2022}
}