Advance in integrated modelling towards prediction and control of JT-60SA plasmas

Hayashi, Nobuhiko; Honda, Mitsuru; Shiraishi, Junya; Miyata, Yoshiaki; Wakatsuki, Takuma; Hoshino, Kazuo; Toma, Mitsunori; Suzuki, Takahiro; Urano, Hajime; Shimizu, Katsuhiro; et al.

Europhysics Conference Abstracts (Internet), 39E, p.P5.145_1 - P5.145_4, 2015/06

http://ocs.ciemat.es/EPS2015PAP/pdf/P5.145.pdf

Current ramp-up scenario with reduced central solenoid magnetic flux consumption in JT-60SA

Wakatsuki, Takuma; Suzuki, Takahiro; Hayashi, Nobuhiko; Shiraishi, Junya; Ide, Shunsuke; Takase, Yuichi*

Europhysics Conference Abstracts (Internet), 39E, p.P5.144_1 - P5.144_4, 2015/06

http://ocs.ciemat.es/EPS2015PAP/pdf/P5.144.pdf

Role of seed impurity for H-mode plasmas in JT-60U

Urano, Hajime; Nakata, Motoki; Aiba, Nobuyuki; Kubo, Hirotaka; Honda, Mitsuru; Yoshida, Maiko; Hayashi, Nobuhiko; Kamada, Yutaka; JT-60 Team

Europhysics Conference Abstracts (Internet), 38F, p.P4.018_1 - P4.018_4, 2014/06

http://ocs.ciemat.es/EPS2014PAP/pdf/P4.018.pdf

This paper reports the analysis result of heat transport and pedestal structure in H-mode plasmas with and without argon seeding on JT-60U.

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

Actively circulated liquid metal divertor (ACLMD)

Shimada, Michiya; Hirooka, Yoshihiko*; Zhou, H.*

Europhysics Conference Abstracts (Internet), 38F, p.O2.110_1 - O2.110_4, 2014/00

http://ocs.ciemat.es/EPS2014PAP/pdf/O2.110.pdf

Tungsten is considered to be most promising candidate for divertor target material for fusion reactor. Although tungsten target can withstand the heat loads of ITER, the heat exhaust requirement for DEMO is much more demanding. Pulsive heat loads associated with disurption would melt the tungsten divertor target. Melting and subsequent resolidification will roughen the tungsten surface, significantly deteriorating the heat handling capability. Further, tungsten has a rather high DBTT (Ductile-Brittle-Transition temperature) of 400C. Neutron irradiation would further increase the DBTT, which could result in cracks. In view of these issues, liquid metal divertor is proposed, which is actively circulated with the Lorentz force introduced through the electrodes in the liquid metal. A modest flow speed of 0.3 m/s seems to be adequate for the heat load exhaust of DEMO. A simple treatment of MHD equation in a cylindrical geometry suggests that the requirements on the current and voltage are modest if the ramp-up of current is made slowly (e.g. in a minute), implying that the this concept is worth further study.

Optimization of ITER operational space for long-pulse scenarios

Polevoi, A. R.*; Hayashi, Nobuhiko; Kim, H. S.*; Kim, S. H.*; Koechl, F.*; Kukushkin, A. S.*; Leonov, V. M.*; Loarte, A.*; Medvedev, S. Yu.*; Murakami, Masakatsu*; et al.

Europhysics Conference Abstracts (Internet), 37D, p.P2.135_1 - P2.135_4, 2013/07

http://ocs.ciemat.es/EPS2013PAP/pdf/P2.135.pdf

Utilizing relativistic mirrors for photon-photon scattering

Koga, J. K.; Bulanov, S. V.; Esirkepov, T. Z.; Pirozhkov, A. S.; Kando, Masaki; Rosanov, N. N.*

Europhysics Conference Abstracts (Internet), 36F, p.O5.214_1 - O5.214_4, 2012/00

http://ocs.ciemat.es/EPSICPP2012PAP/pdf/O5.214.pdf

Energy confinement characterization of hydrogen and deuterium H-mode plasmas in JT-60U tokamak

Urano, Hajime; Takizuka, Tomonori*; Kikuchi, Mitsuru; Nakano, Tomohide; Fujita, Takaaki; Hayashi, Nobuhiko; Oyama, Naoyuki; Kamada, Yutaka; JT-60 Team

Europhysics Conference Abstracts (Internet), 36F, p.P1.016_1 - P1.016_4, 2012/00

http://ocs.ciemat.es/EPSICPP2012PAP/pdf/P1.016.pdf

Energy confinement properties for hydrogen and deuterium H-mode plasmas were examined in JT-60U. The energy confinement time became larger by a factor of 1.2-1.3 for deuterium than for hydrogen at a given . When the plasma energy was fixed, the profiles of density and temperature became identical for both cases while higher heating power was required for hydrogen. The ion conductive heat flux for hydrogen became approximately two times that for deuterium. Hence, the ion heat diffusivity for hydrogen was higher than for deuterium. It was found that the ion-temperature-gradient scale length became smaller by a factor of 1.2 for deuterium than for hydrogen.

Integrated modelling of JT-60SA scenarios with the METIS code

Giruzzi, G.*; Artaud, J. F.*; Joffrin, E.*; Garcia, J.*; Ide, Shunsuke; JT-60SA Research Plan Contributors; JT-60SA Team

Europhysics Conference Abstracts (Internet), 36F, p.P5.018_1 - P5.018_4, 2012/00

http://ocs.ciemat.es/EPSICPP2012PAP/pdf/P5.018.pdf

Approach for efficient linear MHD analysis without spectrum pollution in tokamaks

Aiba, Nobuyuki; Cooper, W.*; Gruber, R.*

Europhysics Conference Abstracts (Internet), 36F, p.P2.045_1 - P2.045_4, 2012/00

http://ocs.ciemat.es/EPSICPP2012PAP/pdf/P2.045.pdf

We developed a new numerical method for analyzing linear ideal MHD stability with higher-order finite element. Since the linear ideal MHD problem is a typical ill-posed problem from numerical viewpoints, a kind of numerical instability, called spectrum pollution, sometimes appears. About 30 years ago, a method realizing to suppress this numerical instability was developed, but this cannot fully suppress this. In fact, when the radial mesh number decreases, numerical instability appears. After revisiting this method, we found that the numerical integral method in this method is not appropriate for suppressing this instability. To fix this issue, we developed a new method with Gauss-Legendre quadrature, and realized to fully suppress numerical instability. This method can apply to the stability analysis with plasma rotation.