Antiferromagnetic NiO thickness dependent sign of the spin Hall magnetoresistance in -FeO/NiO/Pt epitaxial stacks

Dong, B.-W.*; Baldrati, L.*; Schneider, C.*; Niizeki, Tomohiko*; Ramos, R.*; Ross, A.*; Cramer, J.*; Saito, Eiji; Klui, M.*

Applied Physics Letters, 114(10), p.102405_1 - 102405_5, 2019/03

https://doi.org/10.1063/1.5080766

Analysis of JT-60SA scenarios on the basis of JET and JT-60U discharges

Garcia, J.*; Hayashi, Nobuhiko; Giruzzi, G.*; Schneider, M.*; Joffrin, E.*; Ide, Shunsuke; Sakamoto, Yoshiteru; Suzuki, Takahiro; Urano, Hajime; JT-60 Team; et al.

Europhysics Conference Abstracts (Internet), 38F, p.P1.029_1 - P1.029_4, 2014/06

http://ocs.ciemat.es/EPS2014PAP/pdf/P1.029.pdf

Comparative transport analysis of JET and JT-60U discharges

Garcia, J.*; Hayashi, Nobuhiko; Giruzzi, G.*; Schneider, M.*; Joffrin, E.*; Ide, Shunsuke; Sakamoto, Yoshiteru; Suzuki, Takahiro; Urano, Hajime; JT-60 Team; et al.

Europhysics Conference Abstracts (Internet), 36F, p.P5.057_1 - P5.057_4, 2012/00

http://ocs.ciemat.es/EPSICPP2012PAP/pdf/P5.057.pdf

The Temperature evolution of the magnetic correlations in pure and diluted spin ice HoYTiO

Chang, L.-J.; Su, Y.*; Kao, Y.-J.*; Chou, Y. Z.*; Kakurai, Kazuhisa; Mittal, R.*; Schneider, H.*; Brckel, T.*; Balakrishnan, G.*; Lees, M. R.*

Physica B; Condensed Matter, 406(12), p.2393 - 2396, 2011/06

https://doi.org/10.1016/j.physb.2010.10.077

Current ramps in tokamaks; From present experiments to ITER scenarios

Imbeaux, F.*; Basiuk, V.*; Budny, R.*; Casper, T.*; Citrin, J.*; Fereira, J.*; Fukuyama, Atsushi*; Garcia, J.*; Gribov, Y. V.*; Hayashi, Nobuhiko; et al.

Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 8 Pages, 2010/10

http://www-naweb.iaea.org/napc/physics/FEC/FEC2010/html/node62.htm#15641

In order to prepare adequate current ramp-up and ramp-down scenarios for ITER, present experiments from several tokamaks have been analyzed by means of integrated modeling in view of determining relevant heat transport models for these operation phases. The results of these studies are presented and projections to ITER current ramp-up and ramp-down scenarios are done, focusing on the baseline inductive scenario (main heating plateau current of 15 MA). Various transport models have been tested by means of integrated modeling against experimental data from ASDEX Upgrade, C-Mod, DIII-D, JET and Tore Supra, including both Ohmic plasmas and discharges with additional heating/current drive. With using the most successful models, projections to the ITER current ramp-up and ramp-down phases are carried out. Though significant differences between models appear on the electron temperature prediction, the final q-profiles reached in the simulation are rather close.

Benchmarking of lower hybrid current drive codes with application to ITER-relevant regimes

Bonoli, P. T.*; Harvey, R. W.*; Kessel, C. E.*; Imbeaux, F.*; Oikawa, Toshihiro; Schneider, M.*; Barbato, E.*; Decker, J.*; Giruzzi, G.*; Forest, C. B.*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

http://www-naweb.iaea.org/napc/physics/FEC/FEC2006/html/node74.htm#19304

no abstracts in English

Benchmarking of neutral beam current drive codes as a basis for the integrated modeling for ITER

Oikawa, Toshihiro; Park, J. M.*; Polevoi, A. R.*; Schneider, M.*; Giruzzi, G.*; Murakami, M.*; Tani, Keiji*; Sips, A. C. C.*

no journal, , 

The author has been leading a neutral beam current drive code benchmark in the ITPA IOS topical group frame. Presently, the orbit following Monte-Carlo codes OFMC, NUBEAM and SPOT and the Fokker-Planck codes ACCOME and ASTRA have been compared. The NB fast ion source profile agrees well among the codes that employ different beam models and beam stopping models. The heating profile generally agrees, but there is visible discrepancy. This is considerted to result from finite orbit width effects. Large differenence is observed in the NBCD profile. OFMC and ACCOME calculates the initial pitch angle of a fast ion against the toroidal magnetic field, which should correctly be against the equilibrium field. By correcting this the difference is expected to be resolved to some degree. ASTRA's deviation from other codes results from its too simplified NBI geometry and a Fokker-Planck equation derived for a cylinder plasma being used, which does not accordingly include toroidal effects.

Physics comparison and modeling of the JET and JT-60U core and edge; Towards JT-60SA predictions

Garcia, J.*; Hayashi, Nobuhiko; Baiocchi, B.*; Citrin, J.*; Giruzzi, G.*; Honda, Mitsuru; Ide, Shunsuke; Maget, P.*; Narita, Emi*; Schneider, M.*; et al.

no journal, ,