Results 81 to 90 of about 984 (168)

Numerical modeling of impurity powder injection in W7-X

Nuclear Materials and Energy
In this work, we present numerical simulation results of powder injection in W7-X using the EMC3-EIRENE and DIS codes. First, we model powder injection experiments performed in W7-X with the Probe Mounted Powder Injector.
F. Nespoli, Y. Feng, G. Kawamura, M. Shoji, R. Lunsford, D. Hathiramani, J. Koopmann, A. Nagy, F. Effenberg, N.A. Pablant, C. Killer, D. Zhang, M. Kubkowska, S. Jablonski, G. Kocsis, B. Buttenschön, D. Nicolai   +16 more
doaj   +1 more source

Modeling of impurity seeding and transport for W7-X island divertor scenarios with EMC3-EIRENE

, 2017
http://fusionsites.ciemat.es/cwgm16/files/2017/01/effenberg_16thCWGM_Madrid2017 ...
Effenberg, Florian, Feng, Y., Schmitz, O., Frerichs, H., Blackwell, B., Barbui, T., Geiger, J., Bozhenkov, S., Jakubowski, M., König, R., Krychowiak, M., Niemann, H., Sunn Pedersen, T., Stephey, L., Suzuki, Y., Wurden, G.A.   +15 more
openaire   +2 more sources

Impurity leakage mechanisms in the Wendelstein 7-X island divertor under friction-dominated conditions

Nuclear Fusion
The EMC3-Eirene code was used to study the main impurity leakage mechanism for the island divertor in the standard magnetic field configuration. It was found that under experimentally accessible plasma scenarios in the last experimental campaign, the ...
V.R. Winters, F. Reimold, Y. Feng, V. Perseo, M. Beurskens, S. Bozhenkov, K.J. Brunner, G. Fuchert, R. Koenig, J. Knauer, M. Krychowiak, E. Pasch, E. Scott, D. Zhang, the W7-X Team   +14 more
doaj   +1 more source

A universal target plate design scheme for stellarators: theoretical basis and its application to heat load control

Nuclear Fusion
This study introduces a novel divertor target design scheme for stellarators, grounded in mathematical treatments and tailored to control of toroidal heat load distributions.
B. Liu, G. Kawamura, S.Y. Dai, Y. Xu, Y. Suzuki, A. Shimizu, H. Frerichs, Y. Feng   +7 more
doaj   +1 more source

Near- and far scrape-off layer transport studies in detached, small-ELM ASDEX Upgrade discharges by means of EMC3-EIRENE [PDF]

, 2020
T. Lunt, H. Frerichs, M. Bernert, D. Brida, D. Carralero, M. Cavedon, P. David, A. Drenik, M. Faitsch, Y. Feng, M. Griener, A. Herrmann, B. Kurzan, O. Pan, U. Plank, D. Silvagni, M. Willensdorfer, M. Wischmeier, E. Wolfrum   +18 more
openalex   +1 more source

Full-torus impurity transport simulation in boron powder injection experiments in the Large Helical Device

Nuclear Materials and Energy
The toroidal distribution of boron deposition on plasma-facing components (PFCs) in boron powder injection using an impurity power dropper (IPD) was investigated by full-torus simulation and observations in a systematic plasma density-scan experiment ...
M. Shoji, G. Kawamura, R. Smirnov, J. Romazanov, A. Kirschner, Y. Tanaka, S. Masuzaki, T. Kawate, F. Nespoli, R. Lunsford, E.P. Gilson, S. Brezinsek, N.A. Pablant   +12 more
doaj   +1 more source

EMC3-EIRENE modelling of tungsten behavior under resonant magnetic perturbations on EAST: Effects of tungsten sputtering and impurity screening

, 2020
Shuyu Dai, Hongming Zhang, Bo Lyu, Youwen Sun, M. Jia, Y. Feng, Z. X. Wang, Dezhen Wang   +7 more
openalex   +1 more source

Correlation between radiated power and target heat flux in the island divertor of W7-X

Nuclear Fusion
Radiative losses from the plasma represent a key component of global power balance in a magnetic confinement fusion device. Measurements of the plasma radiation and its spatial distribution are essential for physical studies and to ensure safe machine ...
G. Partesotti, F. Reimold, G.A. Wurden, N. Maaziz, A. Tsikouras, B.J. Peterson, F. Federici, K.A. Siever, A. Puig Sitjes, M. Jakubowski, Y. Gao, T. Nishizawa, K. Mukai, the W7-X Team   +13 more
doaj   +1 more source

Extension of Calculation Grid for LHD Edge and Divertor Plasmas [PDF]

departmental bulletin ...
114189, 114190, 114191, 114192, 114193, 114194, Feng, Y., Kawamura, G., Kobayashi, M., Masuzaki, S., Morisaki, T., Tomita, Y.   +11 more
core  

Model prediction of impurity retention in stochastic magnetic boundary and comparison with edge carbon emission in LHD [PDF]

, 2009
Chowdhuri, M. B., Feng, Y., Funaba, H., Goto, M., Kobayashi, M., Komori, A., LHD Experimental Group, Masuzaki, S., Morisaki, T., Morita, S., Motojima, O., Nakamura, Y., Narihara, K., Ohyabu, N., Sato, K., Tamura, N., Yamada, H., Yamada, I.   +17 more
core   +1 more source