(IT/P1-7) Simulation of the Hybrid and Steady State Advanced Operating Modes in ITER

C.E. Kessel1), G. Giruzzi2), A.C.C. Sips3), R.V. Budny1), J.F. Artaud2), V. Basiuk2), F. Imbeaux2), E. Joffrin2), M. Schneider2), T. Luce4), M. Murakami5), H. StJohn4), T. Oikawa6), N. Hayashi7), T. Takizuka7), T. Ozeki7), Y-S. Na8), J-M. Park8), J. Garcia9), A.A. Tucillo10)
1) Princeton Plasma Physics Laboratory, Princeton, NJ, United States of America
2) CEA Cadarache, Saint-Paul-Lez Durance, France
3) Max-Planck-Institut fur Plasmaphysik, EURATOM-Assoziation, Garching, Germany
4) Oak Ridge National Laboratory, Oak Ridge, TN, United States of America
5) General Atomics, San Diego, CA, United States of America
6) ITER International Team, ITER Naka Joint Work Site, Naka,Ibaraki, Japan
7) Japan Atomic Energy Agency, Naka, Ibaraki, Japan
8) National Fusion Research Center, 52 Yeoeun-Dong, Yusung-Gu, Daejeon, Korea
9) Universitat Politecnica de Catalunya, Barcelona, Spain
10) Associazione EURATOM-ENEA, CR ENEA-Frascati, Rome, Italy

Abstract.  The International Thermonuclear Experimental Reactor (ITER) project has identified three primary operating modes for demonstrating controlled burning plasmas, the ELMy H-mode, the Hybrid mode, and the Steady State Mode. Integrated simulations are done to establish a physics basis, in conjunction with present tokamak experiments, for the operating modes in ITER. Since it is not possible to reproduce all the physics parameters of ITER plasmas simultaneously in present experiments, simulations are used to project to the ITER regime using theoretically based physics models, that are being benchmarked on present tokamak experiments. Simulations of the hybrid mode are done using both fixed and free-boundary 1.5D transport evolution codes including CRONOS, ONETWO, TSC/TRANSP, TASK, and ASTRA. The hybrid operating mode is simulated using the GLF23 energy transport model. The injected powers are limited to the negative ion neutral beam (NNBI, 33 MW), ion cyclotron rf heating (ICRF, 20 MW), and electron cyclotron (EC, 20 MW). Overall, results indicate that the pedestal temperatures required to access the βN of 3 regime are in the 8-10 keV range. Simulations of the steady state operating mode are done with the same 1.5D transport evolution codes cited above. In these cases the energy transport model is more difficult to prescribe since the models, used for H-mode plasmas (like the ELMy H-mode and hybrid) that are dominated by E×B shear stabilization, have deficiencies when applied to reversed shear (dq/dr<0), and high pressures (Shafranov shift). Therefore the energy confinement models will range from theory based to empirically based. The injected powers include the NNBI, ICRF, EC, and lower hybrid (LH, up to 40 MW). Results using NNBI, ICRF, and LHCD indicate that if an internal transport barrier is formed, with a T ped of 3 keV, a βN of 3.0 can be reached, giving H98 of 1.7. Another case using NNBI, ICRF FW, and EC with the GLF23 theoretical energy transport model and a Tped of 7.5 keV, giving βN of 3.0, and an H98 of 1.5. These simulations will be presented and compared with particular focus on code to code results when using the same energy transport model, and within the same code when using different energy transport models.

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