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We present integrated modeling of steady-state and hybrid scenarios for ITER parameters, using validated models for the non-inductive current drive sources in conjunction with various theory-based and semiempirical transport models. A significant benchmarking activity has been undertaken in order to validate the current drive models and reference scenarios. Both cross-code and code-experiment comparisons are reported for NBCD, ECCD and LHCD models. Comparisons are made between simulations and a reference set of experimental discharges selected for their relevance to the ITER steady-state and hybrid scenarios. The aim of the chosen current drive schemes is to optimize the q profile for maximum fusion performance and noninductive current fraction. Simulations are then performed with various transport modeling codes, selfconsistently calculating heating and current drive with ITER design parameters. Operating constraints, such as beta limits and power loss to the divertor, are also taken into account. The simulations address both the final stationary state and dynamic access to it.

Additional information

Authors: HOULBERG WA, Oak Ridge National Laboratory, Oak Ridge (US)
Bibliographic Reference: An oral paper given at: 20th IAEA Fusion Energy Conference Organised by: International Atomic Energy Agency Held at: Centrtro de Fusao Nuclear, Vilamoura (PT)
Availability: Available from Association EURATOM-CEA, Département de Recherches sur la Fusion Contrôlée, CEA Cadarache, F-13108 St Paul-Lez-Durance, France Tel: (+33) 4 42 25 70 01; Fax: (+33) 4 42 25 64 21 E-mail:
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