25th IAEA Fusion Energy Conference - IAEA CN-221

Session

Overview 1

OV1

13 Oct 2014, 10:45

Blue 1-5 (Hotel Park Inn Pribaltiyskaya)

Conveners

Overview 1: Magnetic Fusion: OV/1

• Aleksandr Burdakov (Russian Federation)

479. Fusion Research in Ioffe Institute

Mr Leonid Askinazi (Russian Federation)

13/10/2014, 10:45

OV - Overviews

Overview

Overview of activity of the Plasma Physics Division at the Ioffe Institute in support of fusion program is presented. Experiments on LHCD (100kW, 2.5GHz) at the Globus-M tokamak (R=0.36m, a=0.24m, B_tor=0.4T, I_pl=200kA) with poloidally oriented grill resulted in RF driven current of up to 40 kA, in agreement with the theory predictions. At the FT-2 tokamak (R=0.56m, a=0.08m, B_tor=2.3T,...

608. The ITER Project Construction Status

Mr Osamu Motojima (ITER Organization)

13/10/2014, 11:10

OV - Overviews

Overview

The ITER Project has visibly made its transition to the construction phase in the two years since the last Fusion Energy Conference in San Diego. By mid-February 2014 commitments to in-kind procurement are approaching 89.6 percentage of the total credit value and 70.7 percentage (99 out of 140) in the number of Procurement Arrangements. Construction is accelerating and the appearance of the...

234. Overview of the JET Results

Mr Francesco Romanelli (European Commission)

13/10/2014, 11:35

OV - Overviews

Overview

The European fusion programme is moving into the phase of implementation of its Roadmap. In this context, the JET programme has focused on consolidation of ITER design choices and preparation for ITER operation, with a specific emphasis given to the Bulk Tungsten Melt Experiment that has been crucial for the final decision on the material choice for the day-one tungsten divertor in ITER. In...

541. DIII-D Research to Address Key Challenges for ITER and Fusion Energy

Mr Richard J. Buttery (USA)

13/10/2014, 12:00

OV - Overviews

Overview

The DIII-D tokamak has addressed key challenges in preparation for ITER and the next generation of fusion devices. The robustness of RMP-ELM suppression was demonstrated using as few of 5 of the usual 12 coils. QH mode was extended to 80% Greenwald density fraction, establishing its viability for ITER. Disruption mitigation led to relatively symmetric non-localized heat loads, while vertical...