DIII-D RESEARCH OPPORTUNITIES FORUM FOR THE 2008 EXPERIMENTAL CAMPAIGN
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| Title | 29: ITER-AT demonstration discharge | ||
| Name: | Holger Reimerdes ( |
Affiliation: | Columbia University |
| Research Area: | ITER Demonstration Discharges | Presentation time: | Not requested | Co-Author(s): | -- |
| Description: | The goal of this experiment is to develop a scale model of the proposed ITER-AT discharge (scenario 4 in Polevoi et al, IAEA 2002) with the same shape (SND) and the same safety factor profile in DIII-D. This scenario should be used to verify predicted stability limits. | ||
| Experimental Approach/Plan: | The main novelty of this experiment is the use of the ITER plasma shape (SND, kappa=1.76, delta=0.4) as an AT target. The q-profile is characterized by qmin>2 and q95 ranging from 4.1 to 5.1 (corresponds to ITER with Ip=9 to 12MA). The q-profiles have weak negative central shear and a large rho(qmin), which is expected to lead to an ITB at large radius. We plan to use ECCD to tailor the current profile and increase the fraction of non-inductive current. Since the main objective is the creation of a reference, steady-state operation is not a requirement. The ideal MHD no-wall limit is measured using active MHD spectroscopy. Tearing mode limits are evaluated as a function of beta and plasma rotation. | ||
| Background: | One of the ITER objectives is to aim at demonstrating steady-state operation using non-inductive current drive at Q>5 [Shimomura et al, Plasma Phys, Control. Fusion 43 (2001) A385]. The main candidate is a weak negative central shear plasma with a transport barrier at rho=0.75. Recent DIII-D experiments have demonstrated that a transport barrier can be compatible with operation well above the no-wall stability limit [A.M. Garofalo et al, Phys. Plasmas 13 (2006) 056110]. | ||
| Resource Requirements: | 7 NBI sources, AMAP gyrotrons | ||
| Diagnostic Requirements: | -- | ||
| Analysis Requirements: | -- | ||
| Other Requirements: | -- | ||
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