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Tillack, M. S.*; Turnbull, A. D.*; Kessel, C. E.*; Asakura, Nobuyuki; Garofalo, A. M.*; Holland, C.*; Koch, F.*; Linsmeier, Ch.*; Lisgo, S.*; Maingi, R.*; et al.
Nuclear Fusion, 53(2), p.027003_1 - 027003_23, 2013/02
Times Cited Count：5 Percentile：22.48(Physics, Fluids & Plasmas)This review summarizes the presentations and discussions by experts in the fields of edge plasma physics and plasma material interactions at a workshop organized for the purpose of evaluating current status and extrapolating forward to the post-ITER power plant regime. The topics included physics, modelling, experimental results, benchmarking and programme planning.
Kamada, Yutaka; Leonard, A. W.*; Bateman, G.*; Becoulet, M.*; Chang, C. S.*; Eich, T.*; Evans, T. E.*; Groebner, R. J.*; Guzdar, P. N.*; Horton, L. D.*; et al.
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03
no abstracts in English
Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Higashijima, Satoru; Konoshima, Shigeru; Nakano, Tomohide; Oyama, Naoyuki; Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; et al.
Nuclear Fusion, 45(12), p.1618 - 1627, 2005/12
Times Cited Count：18 Percentile：51.61(Physics, Fluids & Plasmas)no abstracts in English
Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Higashijima, Satoru; Konoshima, Shigeru; Nakano, Tomohide; Oyama, Naoyuki; Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; et al.
Proceedings of 20th IAEA Fusion Energy Conference (FEC 2004) (CD-ROM), 8 Pages, 2004/11
no abstracts in English
Asakura, Nobuyuki; Takenaga, Hidenobu; Sakurai, Shinji; Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; Shimizu, Katsuhiro; Higashijima, Satoru; Kubo, Hirotaka
Nuclear Fusion, 44(4), p.503 - 512, 2004/04
Times Cited Count：73 Percentile：89.9(Physics, Fluids & Plasmas)The measurements of the SOL flow and plasma profiles both at the high-field-side (HFS) and low-field-side (LFS), for the first time, found out the SOL flow pattern and its driving mechanism. "Flow reversal" was found near the HFS and LFS separatrix of the main plasma for the ion ▽B drift direction towards the divertor. Radial profiles of the SOL flow were similar to those calculated numerically using the UEDGE code with the plasma drifts included although Mach numbers in measurements were faster than those obtained numerically. Particle fluxes towards the HFS and LFS divertors produced by the parallel SOL flow and Er
B drift flow were evaluated. The particle flux for the case of intense gas puff and divertor pump (puff and pump) was investigated, and it was found that both flow velocity and collisionality were enhanced, in particular, at HFS SOL. Drift flux in the private flux region was also evaluated, and important physics issues for the divertor design and operation, such as in-out asymmetries of the heat and particle fluxes, and control of impurity ions were investigated.
-drift, current, and kinetic effects on divertor plasma profiles during ELMsRognlien, T. D.*; Shimada, Michiya
Journal of Nuclear Materials, 313-316, p.1000 - 1004, 2003/03
Times Cited Count：8 Percentile：50.12(Materials Science, Multidisciplinary)Edge Localized Mode (ELM) heat load on material surfaces is a key issue for burning-plasma tokamak experiments, e.g., ITER or FIRE. When a hot and dense plasma is injected to open field lines near the midplane at an ELM event, there will be a pressure imbalance along the field line, because ion motion is slow. Therefore an electric field will develop along the field line(an extended presheath). Due to the rotational transform, the parallel electric field becomes a poloidal electric field. The field Ep generates an . Therefore, as the injected plasma flows toward the divertor surface to deposit its energy, it experiences a radial shift 1cm. As the target plate is usually inclined to reduce the heat load, a radial shift of 1 cm is appreciable. For ITER, this would correspond to 3 cm on the target. As different portions of the hot ion plasma feel different electric field, the heat flux should also spread radially. A detailed assessment of these cross-field drift effects is given for an ITER-sized device using time-dependent simulations with the 2D UEDGE transport code.
Porter, G. D.*; Rognlien, T. D.*; Rensink, M. E.*; Loarte, A.*; Asakura, Nobuyuki; Takenaga, Hidenobu; Matthews, G.*; Contributors to JET-EFDA Workprogramme*
Journal of Nuclear Materials, 313-316, p.1085 - 1088, 2003/03
Times Cited Count：23 Percentile：80.96(Materials Science, Multidisciplinary)no abstracts in English
Takenaga, Hidenobu; Sakasai, Akira; Kubo, Hirotaka; Asakura, Nobuyuki; Schaffer, M. J.*; Petrie, T. W.*; Mahdavi, M. A.*; Baker, D. R.*; Allen, S. L.*; Porter, G. D.*; et al.
Nuclear Fusion, 41(12), p.1777 - 1787, 2001/12
Times Cited Count：22 Percentile：57.74(Physics, Fluids & Plasmas)no abstracts in English
