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Chakraborty, S.*; Datta, U.*; Aumann, T.*; Beceiro-Novo, S.*; Boretzky, K.*; Caesar, C.*; Carlson, B. V.*; Catford, W. N.*; Chartier, M.*; Cortina-Gil, D.*; et al.
Physical Review C, 96(3), p.034301_1 - 034301_9, 2017/09
Times Cited Count:4 Percentile:32.59(Physics, Nuclear)no abstracts in English
Lane, J. F. W.*; Andreyev, A. N.*; Antalic, S.*; Ackermann, D.*; Gerl, J.*; Heberger, F. P.*; Hofmann, S.*; Huyse, M.*; Kettunen, H.*; Kleinb
hl, A.*; et al.
Physical Review C, 87(1), p.014318_1 - 014318_7, 2013/01
Times Cited Count:16 Percentile:69.05(Physics, Nuclear)Schaffer, M. J.*; Snipes, J. A.*; Gohil, P.*; de Vries, P.*; Evans, T. E.*; Fenstermacher, M. E.*; Gao, X.*; Garofalo, A. M.*; Gates, D. A.*; Greenfield, C. M.*; et al.
Nuclear Fusion, 51(10), p.103028_1 - 103028_11, 2011/10
Times Cited Count:37 Percentile:80.67(Physics, Fluids & Plasmas)Experiments at DIII-D investigated the effects of ferromagnetic error fields similar to those expected from proposed ITER Test Blanket Modules (TBMs). Studied were effects on: plasma rotation and locking; confinement; L-H transition; edge localized mode (ELM) suppression by resonant magnetic perturbations; ELMs and the H-mode pedestal; energetic particle losses; and more. The experiments used a 3-coil mock-up of 2 magnetized ITER TBMs in one ITER equatorial port. The experiments did not reveal any effect likely to preclude ITER operations with a TBM-like error field. The largest effect was slowed plasma toroidal rotation v across the entire radial profile by as much as via non-resonant braking. Changes to global
,
and
were
3 times smaller. These effects are stronger at higher
and lower
. Other effects were smaller.
Tomiyasu, Keisuke*; Kageyama, Hiroshi*; Lee, C.*; Whangbo, M. H.*; Tsujimoto, Yoshihiro*; Yoshimura, Kazuyoshi*; Taylor, J. W.*; Llobet, A.*; Trouw, F.*; Kakurai, Kazuhisa; et al.
Journal of the Physical Society of Japan, 79(3), p.034707_1 - 034707_4, 2010/03
Times Cited Count:16 Percentile:65.58(Physics, Multidisciplinary)Murakami, Masanori*; Park, J. M.*; Petty, C. C.*; Luce, T. C.*; Heidbrink, W. W.*; Osborne, T. H.*; Prater, R.*; Wade, M. R.*; Anderson, P. M.*; Austin, M. E.*; et al.
Nuclear Fusion, 49(6), p.065031_1 - 065031_8, 2009/06
Times Cited Count:45 Percentile:82.74(Physics, Fluids & Plasmas)Modification of the two existing DIII-D neutral beam lines is planned to allow vertical steering to provide off-axis neutral beam current drive (NBCD) peaked as far off-axis as half the plasma minor radius. New calculations for a downward-steered beam indicate strong current drive with good localization off-axis so long as the toroidal magnetic field, BT, and the plasma current, Ip, point in the same direction. This is due to good alignment of neutral beam injection (NBI) with the local pitch of the magnetic field lines. This model has been tested experimentally on DIII-D by an injecting equatorially-mounted NBs into reduced size plasmas that are vertically displaced with respect to the vessel midplane. The existence of off-axis NBCD is evident in the changes seen in sawtooth behavior in the internal inductance. By shifting the plasma upward or downward, or by changing the sign of the toroidal field, measured off-axis NBCD profiles measured with motional Stark effect data and internal loop voltage show a difference in amplitude (40%-45%) consistent with predicted differences predicted by the changed NBI alignment with respect to the helicity of the magnetic field lines. The effects of NB injection direction relative to field line helicity can be large even in ITER: off-axis NBCD can be increased by more than 20% if the BT direction is reversed. Modification of the DIII-D NB system will strongly support scenario development for ITER and future tokamaks as well as providing flexible scientific tools for understanding transport, energetic particles and heating and current drive.
Nakamura, Mitsutaka; Iwase, Hiroki; Arai, Masatoshi; Kartini, E.*; Russina, M.*; Yokoo, Tetsuya*; Taylor, J. W.*
Physica B; Condensed Matter, 385-386(1), p.552 - 554, 2006/11
Times Cited Count:3 Percentile:17.26(Physics, Condensed Matter)The mechanism of high ionic conductivity in superionic glass constitute an unsolved problem in the field of science.Here we performed inelastic neutron scattering measurements of superionic glass system (AgI)(Ag
S)
(AgPO
)
by using MARI spectrometer at ISIS, and found that the
-dependence of inelastic intensity in the energy region from 1 to 3 meV of superionic phase glass shows an excess intensity above
=1.8
compared with insulator phase one. Similar phenomena were also observed in another superionic glass (AgI)
(AgPO
)
by using NEAT spectrometer at HMI with high resolution measurement. These results clearly suggest peculiar low energy vibrational excitations should be universal features of superionic glass.
Nakamura, Mitsutaka; Arai, Masatoshi; Kartini, E.*; Taylor, J. W.*; Russina, M.*
AIP Conference Proceedings 832, p.504 - 507, 2006/05
Superionic glasses (AgI)(Ag
S)
(AgPO
)
and (AgI)
(AgPO
)
have high ionic conductivity at room temperature (
S/cm). The inelastic neutron scattering measurements show that the superionic glass has larger intensity in low-energy region compared with undoped insulator glass (AgPO
). For superionic glasses we find an excess intensity above
=1.8
and peak profile at around 2.2
by investigating the
-dependent features in low-energy region. These phenomena should be universal features of silver-salt superionic glass. We suppose that Ag-Ag dynamical correlation should promote the successive hopping process, and result in high ionic conductivity.
Yoshino, Ryuji; D.J.Campbell*; E.Fredrickson*; Fujisawa, Noboru; N.Granetz*; Gruber, O.*; T.C.Hender*; D.A.Humphreys*; N.Ivanov*; S.Jardin*; et al.
Fusion Energy 2000 (CD-ROM), 4 Pages, 2001/05
no abstracts in English
Gordon, C.*; Bartels, H.-W.*; Honda, Takuro; Iseli, M.*; Raeder, J.*; Topilski, L.*; Moshonas, K.*; Taylor, N.*
Fusion Engineering and Design, 54(3-4), p.397 - 403, 2001/04
Times Cited Count:2 Percentile:19.35(Nuclear Science & Technology)no abstracts in English
Enoeda, Mikio; Yamanishi, Toshihiko; Yamada, Masayuki; Konishi, Satoshi; Okuno, Kenji; Willms, R. S.*; Taylor, D.*; W.Harbin*; Bartlit, J. R.*; Anderson, J. L.*
JAERI-Research 95-034, 29 Pages, 1995/05
no abstracts in English
Konishi, Satoshi; Yamanishi, Toshihiko; Enoeda, Mikio; Hayashi, Takumi; Ohira, Shigeru; Yamada, Masayuki; Suzuki, Takumi; Okuno, Kenji; Sherman, R. H.*; Willms, R. S.*; et al.
Fusion Engineering and Design, 28, p.258 - 264, 1995/00
Times Cited Count:4 Percentile:43.46(Nuclear Science & Technology)no abstracts in English
Yamanishi, Toshihiko; Hayashi, Takumi; Nakamura, Hirofumi; Okuno, Kenji; Sherman, R. H.*; Taylor, D.*; Barnes, J. W.*; Bartlit, J. R.*
JAERI-M 93-188, 31 Pages, 1993/10
no abstracts in English
Hayashi, Takumi; Nakamura, Hirofumi; Konishi, Satoshi; Inoue, Masahiko*; Hirata, Kazuhiro*; Okuno, Kenji; Naruse, Yuji; Anderson, J. L.*; Sherman, R. H.*; Willms, R. S.*; et al.
JAERI-M 93-083, 54 Pages, 1993/03
no abstracts in English
Hayashi, Takumi; Nakamura, Hirofumi; Konishi, Satoshi; Yamanishi, Toshihiko; Inoue, Masahiko*; Hirata, Kazuhiro*; Okuno, Kenji; Naruse, Yuji; Anderson, J. L.*; Barnes, J. W.*; et al.
JAERI-M 93-081, 35 Pages, 1993/03
no abstracts in English
Sherman, R. H.*; Taylor, D. J.*; Barnes, J. W.*; Yamanishi, Toshihiko; Enoeda, Mikio; Konishi, Satoshi; Okuno, Kenji
Proceedings of 15th IEEE/NPSS Symposium on Fusion Engineering, p.77 - 79, 1993/00
no abstracts in English
Tomiyasu, Keisuke*; Kageyama, Hiroshi*; Tsujimoto, Yoshihiro*; Yoshimura, Kazuyoshi*; Taylor, J. W.*; Llobet, A.*; Kakurai, Kazuhisa; Yamada, Kazuyoshi*
no journal, ,
no abstracts in English
Snipes, J. A.*; Schaffer, M. J.*; Gohil, P.*; de Vries, P.*; Fenstermacher, M. E.*; Evans, T. E.*; Gao, X. M.*; Garofalo, A.*; Gates, D. A.*; Greenfield, C. M.*; et al.
no journal, ,
A series of experiments was performed on DIII-D to mock-up the field that will be induced in a pair of ferromagnetic Test Blanket Modules (TBMs) in ITER to determine the effects of such error fields on plasma operation and performance. A set of coils producing both poloidal and toroidal fields was placed inside a re-entrant horizontal port close to the plasma. The coils produce a localized ripple due to the toroidal field (TF) + TBM up to 5.7%, which is more than four times that expected from a pair of representative 1.3 ton TBMs in ITER. The experiments show that the reduction in the toroidal rotation is sensitive to the ripple. On the other hand, the confinement is reduced by up to 15-18% for local ripple 3% but is hardly affected at 1.7% local ripple.