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Takenaga, Hidenobu; Asakura, Nobuyuki; Kubo, Hirotaka; Konoshima, Shigeru; Nakano, Tomohide; Porter, G.*; Rognlien, T.*; Rensink, M.*
Journal of Plasma and Fusion Research SERIES, Vol.7, p.35 - 39, 2006/00
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：19 Percentile：52.36(Physics, Fluids & Plasmas)no abstracts in English
Kallenbach, A.*; Asakura, Nobuyuki; Kirk, A.*; Korotkov, A.*; Mahdavi, M. A.*; Mossessian, D.*; Porter, G. D.*
Journal of Nuclear Materials, 337-339, p.381 - 385, 2005/03
Times Cited Count：67 Percentile：96.50(Materials Science, Multidisciplinary)Edge profile data for H-mode discharges in 6 tokamaks have been analysed with the main focus on the edge density profile as well as electron temperature and density gradient lengths and steep gradient zone widths. A uniform procedure of data treatment and assignment of the separatrix position via power balance allowed to put the multi-machine data on an even base. The machine size appears to be the leading parameter for the width of the steep edge transport barrier gradient zone, as well as for the temperature decay length at the separatrix. Effects associated with neutral penetration physics are visible in the edge density profile.
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：75 Percentile：89.65(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.
Loarte, A.*; Saibene, G.*; Sartori, R.*; Campbell, D.*; Becoulet, M.*; Horton, L.*; Eich, T.*; Herrmann, A.*; Matthews, G.*; Asakura, Nobuyuki; et al.
Plasma Physics and Controlled Fusion, 45(9), p.1549 - 1569, 2003/10
Times Cited Count：469 Percentile：99.70(Physics, Fluids & Plasmas)Analysis of Type I ELMs from ongoing experiments shows that ELM energy losses are correlated with the density and temperature of the pedestal plasma before the ELM crash. The Type I ELM plasma energy loss normalized to the pedestal energy is found to correlate across experiments with the collisionality of the pedestal plasma. Other parameters affect the ELM size such as the edge magnetic shear, etc, which influence the plasma volume affected by the ELMs. ELM particle losses are influenced by this ELM affected volume and are weakly dependent on other pedestal plasma parameters. In JET and DIII-D, minimum Type I ELMs with energy losses acceptable for ITER were found, that do not affect the plasma temperature. The duration of the divertor ELM power pulse is correlated with the typical ion transport time from the pedestal to the divertor target and not with the duration of the ELM associated MHD activity. Extrapolation of the present experimental results to ITER is summarized.
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：24 Percentile：81.33(Materials Science, Multidisciplinary)no abstracts in English
Loarte, A.*; Saibene, G.*; Sartori, R.*; Becoulet, M.*; Horton, L.*; Eich, T.*; Herrmann, A.*; Laux, M.*; Matthews, G.*; Jachmich, S.*; et al.
Journal of Nuclear Materials, 313-316, p.962 - 966, 2003/03
Times Cited Count：117 Percentile：98.41(Materials Science, Multidisciplinary)no abstracts in English
Asakura, Nobuyuki; Sakurai, Shinji; Itami, Kiyoshi; Naito, Osamu; Takenaga, Hidenobu; Higashijima, Satoru; Koide, Yoshihiko; Sakamoto, Yoshiteru; Kubo, Hirotaka; Porter, G. D.*
Journal of Nuclear Materials, 313-316, p.820 - 827, 2003/03
Times Cited Count：36 Percentile：89.20(Materials Science, Multidisciplinary)no abstracts in English
Asakura, Nobuyuki; Takenaga, Hidenobu; Sakurai, Shinji; Sakasai, Akira; Tamai, Hiroshi; Shimizu, Katsuhiro; Porter, G. D.*
Plasma Physics and Controlled Fusion, 44(10), p.2101 - 2119, 2002/10
Times Cited Count：21 Percentile：55.32(Physics, Fluids & Plasmas)no abstracts in English
Asakura, Nobuyuki; Loarte, A.*; Porter, G.*; Philipps, V.*; Lipschultz, B.*; Kallenbach, A.*; Matthews, G.*; Federici, G.*; Kukushkin, A.*; Mahdavi, A.*; et al.
IAEA-CN-94/CT/P-01, 5 Pages, 2002/00
Three important physics issues for the ITER divertor design and operation are summarized based on the experimental and numerical work from multi-machine database (JET, JT-60U, ASDEX Upgrade, DIII-D, Alcator C-Mod and TEXTOR). (i) The energy load associated with Type-I ELMs is of great concern for the lifetime of the ITER divertor target. In order to understand the physics base of the scaling models, the ELM heat and particle transport to the divertor is investigated. Convective transport during ELMs plays an important role in heat transport to the divertor. (ii) Determination of the SOL flow pattern and the driving mechanism has progressed experimentally and numerically. Influences of the drift effects on the SOL and divertor plasma transport were discussed. (iii) Characteristics of chemical yield at two different deposited carbon surfaces, i.e. erosion- and redeposition-dominated areas, have been studied. Progress of understanding the chemical erosion is reviewed.
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：23 Percentile：58.17(Physics, Fluids & Plasmas)no abstracts in English
