Zobrazeno 1 - 10
of 88
pro vyhledávání: '"S.W. Lisgo"'
Autor:
D. Borodin, J. Romazanov, R.A. Pitts, S.W. Lisgo, S. Brezinsek, I. Borodkina, A. Eksaeva, E. Safi, K. Nordlund, A. Kirschner, Ch. Linsmeier
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 510-515 (2019)
ERO is a 3D Monte-Carlo impurity transport and plasma-surface interaction code. In 2011 it was applied for the ITER first wall (FW) life time predictions [1] (critical blanket module BM11). After that the same code was significantly improved during i
Externí odkaz:
https://doaj.org/article/b387f3edfb974689b395ea93aa2f8599
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 899-907 (2017)
As part of an effort to validate the edge plasma model in the SOLPS-ITER code suite under ITER-relevant divertor plasma and neutral conditions, we report on progress in the modeling of the Alcator C-Mod divertor plasma with the new code. We perform s
Externí odkaz:
https://doaj.org/article/3425848499a34f70a0a102140eab6d9d
Autor:
J.R. Harrison, W.A.J. Vijvers, C. Theiler, B.P. Duval, S. Elmore, B. Labit, B. Lipschultz, S.H.M. van Limpt, S.W. Lisgo, C.K. Tsui, H. Reimerdes, U. Sheikh, K.H.A. Verhaegh, M. Wischmeier
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 1071-1076 (2017)
Divertor detachment in the TCV tokamak has been investigated through experiments and modelling. Density ramp experiments were carried out in ohmic heated L-mode pulses with the ion ∇B drift directed away from the primary X-point, similar to previou
Externí odkaz:
https://doaj.org/article/68355bcd64214fd6bfee8145a4908413
Autor:
G. Meisl, M. Oberkofler, A. Hakola, K. Krieger, K. Schmid, S.W. Lisgo, M. Mayer, A. Lahtinen, A. Drenik, S. Potzel, L. Aho-Mantila, ASDEX Upgrade Team
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 51-59 (2017)
We have studied the retention of nitrogen in surfaces with varying roughness and the transport of nitrogen from the divertor to the outer midplane in experiments at the tokamak ASDEX Upgrade. To allow for a reliable identification of nitrogen retaine
Externí odkaz:
https://doaj.org/article/50324dba111f428baae3a45271cac886
Autor:
A. Khan, G. De Temmerman, S.W. Lisgo, X. Bonnin, H. Anand, M.A. Miller, R.A. Pitts, K. Schmid, A.S. Kukushkin
Publikováno v:
Nuclear Materials and Energy, Vol 20, Iss , Pp - (2019)
Deposition and fuel retention profiles in low power hydrogen L-mode plasmas and neon (Ne) seeded ITER DT burning plasmas have been investigated. Two different Ne seeded plasma backgrounds with varying sub-divertor neutral pressures but the same Ne im
Externí odkaz:
https://doaj.org/article/5567f3d3e6eb461a9bd43fe989b70243
Autor:
Y. Feng, V. Bobkov, T. Lunt, A. M. Messiaen, R.A. Pitts, Xavier Bonnin, W. Zhang, D. P. Coster, J.-M. Noterdaeme, S.W. Lisgo, R. Bilato, Ph. Jacquet
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss, Pp 364-371 (2019)
Nuclear Materials and Energy
Nuclear Materials and Energy
The coupling of ion cyclotron range of frequencies (ICRF) power to the plasma depends critically on the scrape-off layer (SOL) density since the fast wave is evanescent below the cut-off density. The ICRF power coupling can be improved by increasing
Publikováno v:
Fusion Engineering and Design. 123:825-829
The performance of ITER Main Chamber H-alpha (and Visible Light) Spectroscopy diagnostics is challenged by the problem of separating the Balmer-alpha light emitted in the scrape-off-layer (SOL) in the main chamber from the much more intense divertor
Autor:
Wouter Dekeyser, J.L. Terry, Brian LaBombard, R.A. Pitts, S.W. Lisgo, Xavier Bonnin, Dan Brunner
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss, Pp 899-907 (2017)
As part of an effort to validate the edge plasma model in the SOLPS-ITER code suite under ITER-relevant divertor plasma and neutral conditions, we report on progress in the modeling of the Alcator C-Mod divertor plasma with the new code. We perform s
Autor:
M.A. Miller, Karl Schmid, R.A. Pitts, A. Khan, A.S. Kukushkin, G. De Temmerman, Xavier Bonnin, H. Anand, S.W. Lisgo
Publikováno v:
Nuclear Materials and Energy, Vol 20, Iss, Pp-(2019)
Khan, A, De Temmerman, G, Lisgo, S, Bonnin, X, Anand, H, Miller, M, Pitts, R, Schmid, K & Kukushkin, A 2019, ' WallDYN simulations of material migration and fuel retention in ITER low power H plasmas and high power neon-seeded DT plasmas ', Nuclear Materials and Energy, vol. 20, 100674 . https://doi.org/10.1016/j.nme.2019.100674
Nuclear Materials and Energy
Khan, A, De Temmerman, G, Lisgo, S, Bonnin, X, Anand, H, Miller, M, Pitts, R, Schmid, K & Kukushkin, A 2019, ' WallDYN simulations of material migration and fuel retention in ITER low power H plasmas and high power neon-seeded DT plasmas ', Nuclear Materials and Energy, vol. 20, 100674 . https://doi.org/10.1016/j.nme.2019.100674
Nuclear Materials and Energy
Deposition and fuel retention profiles in low power hydrogen L-mode plasmas and neon (Ne) seeded ITER DT burning plasmas have been investigated. Two different Ne seeded plasma backgrounds with varying sub-divertor neutral pressures but the same Ne im
Publikováno v:
Nuclear Materials and Energy, Vol 18, Iss, Pp 125-130 (2019)
The SOLPS-ITER code suite is used worldwide for plasma edge modeling, the interpretation of experiments, as well as for the design of the ITER divertor. The numerical scheme of the plasma solver of the code, B2.5, is based on the assumption of perfec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f7be128eb2c32afdef391ea788ed1ca2
https://lirias.kuleuven.be/handle/20.500.12942/692477
https://lirias.kuleuven.be/handle/20.500.12942/692477