27th IEEE Symposium on Fusion Engineering

Session

R.OP5: Experimental Devices II

R.OP5

8 Jun 2017, 15:00

Marriott Shanghai City Center

265. Design and Analysis of an Actively Cooled Window for a High Power Helicon Plasma Source

Dr Arnold Lumsdaine (Oak Ridge National Lab)

08/06/2017, 15:00

Plasma-material interactions, plasma edge physics

Oral

The development of the next generation of magnetically confined plasma fusion facilities on the path to commercial fusion power will depend on an increased understanding of plasma material interactions (PMI). Plasma facing components in future facilities such as a Fusion Nuclear Science Facility (FSNF) or DEMO will experience high heat fluxes, high energy neutron fluence, and helium and...

132. Tokamak design and maintenance scheme trade off Application on CFETR

Eric Villedieu (CEA)

08/06/2017, 15:20

Operations and maintenance

Oral

The new tokamak generation will be characterized by the necessity of full remote maintenance for most of the critical components. Because no human intervention can be envisaged, the remote systems will have to prove high reliability and rescue capabilities. The availability of the fusion facility will have to be maximized, as a consequence, the efficiency of the maintenance equipment will...

480. Study of the impact of pre- and real-time deposition of lithium on plasma performance on NSTX

Gustavo P. Canal (General Atomics)

08/06/2017, 15:40

Plasma-material interactions, plasma edge physics

Oral

Experiments in many machines have shown improvements on plasma confinement and edge stability with increasing levels of lithium (Li) conditioning. Different methods were used in these experiments to deposit lithium into the plasma, such as a laser-based injection of Li aerosol, injection by movable probe, use of a rotatable Li-coated limiter and use of a movable porous capillary Li limiter....

137. CODAC Core System for ITER plant system I&C

Mr Franck Di Maio (ITER Organization)

08/06/2017, 16:00

Project management, systems engineering

Oral

Construction of the ITER project is distributed among its many members. The ITER plant systems are built including their local controls by many partners all around the world, to be delivered as in-kind contributions to the ITER site after factory acceptance testing. A total of 171 separate Instrumentation and Control (I&C) sub-systems, for power supplies, cooling water, cryogenics, magnets,...

352. Extreme ultraviolet spectroscopy applied to study RMP effects on core impurity concentration in EAST

Germán Vogel (University of Science and Technology of China)

08/06/2017, 16:20

Diagnostics and instrumentation

Oral

Impurity control is one of the key issues to improve confinement performance in present fusion research. The application of resonant magnetic perturbations (RMP) has been proposed as a candidate method to reduce impurity concentration in the core region of magnetically-confined plasmas. In order to understand the effects of RMP on impurity transport, a space-resolved extreme ultraviolet (EUV)...

288. Development of a utility negative ion test equipment with RF source at ASIPP

Dr Jianglong Wei (Institute of Plasma Physics, Chinese Academy of Sciences)

08/06/2017, 16:40

Plasma heating and current drive

Oral

The negative ion source is a key component of the neutral beam injector for the reactor-scale fusion devices, such as ITER, CFETR, and DEMO. Considered the lack of research on the negative ion source for NBI application in China, a utility negative ion test equipment with RF source is being developed at Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP). The original task of the...