Results 21 to 30 of about 2,743 (148)

Synthetic plasma edge diagnostics for EMC3-EIRENE, highlighted for Wendelstein 7-X [PDF]

Review of Scientific Instruments, 2016
Interpretation of spectroscopic measurements in the edge region of high-temperature plasmas can be a challenge since line of sight integration effects make direct interpretation in terms of quantitative, local emission strengths often impossible. The EMC3-EIRENE code—a 3D fluid edge plasma and kinetic neutral gas transport code—is a suitable tool for ...
H. Frerichs, F. Effenberg, O. Schmitz, C. Biedermann, Y. Feng, M. Jakubowski, R. König, M. Krychowiak, J. Lore, H. Niemann, T. S. Pedersen, L. Stephey, G. A. Wurden   +12 more
openaire   +3 more sources

Toroidally symmetric/asymmetric effect on the divertor flux due to neon/nitrogen seeding in LHD

Nuclear Materials and Energy, 2017
Toroidal distributions of divertor particle flux during neon (Ne) and nitrogen (N2) seeded discharges were investigated in the Large Helical Device (LHD).
H. Tanaka, G. Kawamura, S. Masuzaki, M. Kobayashi, T. Akiyama, B.J. Peterson, K. Mukai, R. Sano, S.Y. Dai, R. Sakamoto, T. Morisaki, N. Ohno   +11 more
doaj   +1 more source

Three-dimensional structure of radiative cooling in impurity seeded plasmas in the Large Helical Device

Nuclear Materials and Energy, 2022
Three-dimensionally localization of radiative cooling due to nitrogen (N2) seeding for divertor detachment was detected experimentally. Since the localization along some magnetic field lines induces toroidal asymmetry of heat load reduction on divertor ...
K. Mukai, G. Kawamura, S. Masuzaki, Y. Hayashi, H. Tanaka, B.J. Peterson, T. Oishi, C. Suzuki, M. Kobayashi, K. Munechika   +9 more
doaj   +1 more source

Estimations of edge plasma and impurity performance on HL-2M with EMC3-EIRENE modelling

Physica Scripta, 2021
Abstract The three-dimensional edge transport code EMC3-EIRENE has been employed to investigate the edge plasma behavior and carbon impurity transport in the HuanLiuqi-2M (HL-2M) tokamak. It is found that the outboard divertor target has a narrower flux deposition width and therefore undergoes more intense peak ...
Z Liang, S Y Dai, Y Feng, D Z Wang
openaire   +2 more sources

Simulation of impurity transport in the peripheral plasma due to the emission of dust in long pulse discharges on the Large Helical Device

Nuclear Materials and Energy, 2017
Two different plasma termination processes by dust emission were observed in long pulse discharges in the Large Helical Device. One is a plasma termination caused by large amounts of carbon dust released from a lower divertor region.
M. Shoji, G. Kawamura, R. Smirnov, A. Pigarov, Y. Tanaka, S. Masuzaki, Y. Uesugi   +6 more
doaj   +1 more source

Integrated modelling: Coupling of surface evolution and plasma-impurity transport

Nuclear Materials and Energy, 2020
During the interaction of the scrape off layer (SOL) plasma with the first wall the evolution of both wall and plasma are tightly coupled: The erosion of the first wall leads to an impurity concentration in the plasma which affects the particle and power
K. Schmid, F. Effenberg, A. Dinklage, L. Rudischhauser, Y. Gao, M. Mayer, S. Brezinsek, J. Geiger, G. Fuchert, V. Miklos, H. Smith, Y. Turkin, K. Rahbarnia, T. Stange, K. Ipp, J. Brunner, U. Neuner, A. Pavone, U. Hoefel, H. Ipp   +19 more
doaj   +1 more source

EMC3-Eirene simulations of the spatial dependence of the tungsten divertor retention in ASDEX Upgrade [PDF]

Plasma Physics and Controlled Fusion, 2011
The Edge Monte Carlo 3D (EMC3)-Eirene code package is applied to simulate the deuterium plasma and neutral particle as well as the tungsten impurity transport in ASDEX Upgrade. Good agreement is found for the deuterium bulk plasma for an L-mode discharge both in the upstream and downstream profiles.
Lunt, T., Feng, Y., Krieger, K., Neu, R., Müller, H. W., Wolfrum, E., Willensdorfer, M., Wischmeier, M., ASDEX Upgrade Team   +8 more
openaire   +3 more sources

Impact of impurities on the effective charge state distribution in the limiter plasmas of Wendelstein 7-X

Nuclear Materials and Energy, 2019
Carbon and oxygen have been identified as the two major impurities in the first limiter operational phase of the stellarator Wendelstein 7-X. We evaluate basic differences between these impurities regarding the effective charge state in the boundary ...
J. Cosfeld, M. Rack, D. Reiter, P. Drews, Y. Feng, D. Zhang   +5 more
doaj   +1 more source

2D and 3D studies of the X-divertor configuration in the future upper divertor of ASDEX upgrade

Nuclear Materials and Energy, 2019
ASDEX Upgrade is planning the installation of a pair of in-vessel coils in order to study alternative divertor configurations, like an X-divertor (XD) or a Snowflake (SF) in a machine with a high heating power compared to its size.
T. Lunt, O. Pan, A. Herrmann, M. Teschke, M. Dunne, Y. Feng, M. Wischmeier   +6 more
doaj   +1 more source

Impurity transport simulation in the peripheral plasma in the large helical device with tungsten closed helical divertor

Nuclear Materials and Energy, 2018
Long pulse plasma discharges in the Large Helical Device have been often interrupted by iron dust emission induced by electric arcing on the surface of the vacuum vessel.
M. Shoji, G. Kawamura, S. Masuzaki, T. Morisaki   +3 more
doaj   +1 more source