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

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

Nuclear Fusion, 54(9), p.093010_1 - 093010_13, 2014/09

https://doi.org/10.1088/0029-5515/54/9/093010

Development of advanced inductive scenarios for ITER

Luce, T. C.*; Challis, C. D.*; Ide, Shunsuke; Joffrin, E.*; Kamada, Yutaka; Politzer, P. A.*; Schweinzer, J.*; Sips, A. C. C.*; Stober, J.*; Giruzzi, G.*; et al.

Nuclear Fusion, 54(1), p.013015_1 - 013015_15, 2013/12

https://doi.org/10.1088/0029-5515/54/1/013015

Optimization of JT-60SA plasma operational scenario with capabilities of installed actuators

Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Challis, C. D.*; Fujita, Takaaki; Giruzzi, G.*; Joffrin, E.*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

http://www-naweb.iaea.org/napc/physics/FEC/FEC2012/papers/228_FTPP722.pdf

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

Experimental studies of ITER demonstration discharges

Sips, A. C. C.*; Casper, T.*; Doyle, E. J.*; Giruzzi, G.*; Gribov, Y.*; Hobirk, J.*; Hogeweij, G. M. D.*; Horton, L. D.*; Hubbard, A. E.*; Hutchinson, I.*; et al.

Nuclear Fusion, 49(8), p.085015_1 - 085015_11, 2009/08

https://doi.org/10.1088/0029-5515/49/8/085015

Key parts of the ITER scenarios are determined by the capability of the proposed poloidal field (PF) coil set. They include the plasma breakdown at low loop voltage, the current rise phase, the performance during the flat top (FT) phase and a ramp down of the plasma. The ITER discharge evolution has been verified in dedicated experiments. New data are obtained from C-Mod, ASDEX Upgrade, DIII-D, JT-60U and JET. Results show that breakdown for 0.23-0.33 V m is possible unassisted (ohmic) for large devices like JET and attainable in devices with a capability of using ECRH assist. For the current ramp up, good control of the plasma inductance is obtained using a full bore plasma shape with early X-point formation. This allows optimization of the flux usage from the PF set. Additional heating keeps (3) 0.85 during the ramp up to = 3. A rise phase with an H-mode transition is capable of achieving (3) 0.7 at the start of the FT. Operation of the H-mode reference scenario at 3 and the hybrid scenario at = 4-4.5 during the FT phase is documented, providing data for the (3) evolution after the H-mode transition and the (3) evolution after a back-transition to L-mode. During the ITER ramp down it is important to remain diverted and to reduce the elongation. The inductance could be kept 1.2 during the first half of the current decay, using a slow ramp down, but still consuming flux from the transformer. Alternatively, the discharges can be kept in H-mode during most of the ramp down, requiring significant amounts of additional heating.

Integrated modeling of steady-state scenarios for ITER; Physics and computational challenges

Giruzzi, G.*; Park, J. M.*; Murakami, M.*; Kessel, C. E.*; Polevoi, A.*; Sips, A. C. C.*; Artaud, J. F.*; Basiuk, V.*; Bonoli, P.*; Budny, R. V.*; et al.

Proceedings of 22nd IAEA Fusion Energy Conference (FEC 2008) (CD-ROM), 8 Pages, 2008/10

Simulation of the hybrid and steady state advanced operating modes in ITER

Kessel, C. E.*; Giruzzi, G.*; Sips, A. C. C.*; Budny, R. V.*; Artaud, J. F.*; Basiuk, V.*; Imbeaux, F.*; Joffrin, E.*; Schneider, M.*; Luce, T.*; 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/node78.htm#20378

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, , 

Assessment of the range of controls in JT-60SA plasmas and scenario development

Ide, Shunsuke; Aiba, Nobuyuki; Bolzonella, T.*; Challis, C. D.*; Fujita, Takaaki; Giruzzi, G.*; Joffrin, E.*; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; et al.

no journal, ,