SOFT 2018

Session

O1.A

O1.A.

17 Sept 2018, 14:30

LIPARI Hall - ATA Hotel Naxos Beach Resort (Giardini Naxos)

41. Plasma control for EAST long pulse non-inductive H-mode operation in a quasi-snowflake shape

Dr Bingjia Xiao (Division of Control and Computer Application, Institute of Plasma Physics, Chinese Academy of Sciences)

17/09/2018, 14:30

Experimental Fusion Devices and Supporting Facilities

Advanced magnetic divertor configuration is one of the attractive methods to spread the heat fluxes over divertor targets in tokamak because of enhanced scrape-off layer transport and an increased plasma wetted area on divertor target. Exact snowflake (SF) for EAST is only possible at very low plasma current due to poloidal coil system limitation. However, we found an alternative way to...

42. Implementation and exploitation of jet enhancements in preparation for dt operation and next step devices

Dr Andrea Murari (Programme Management Unit, EUROfusion Consortium)

17/09/2018, 14:50

Experimental Fusion Devices and Supporting Facilities

JET presents some unique capabilities: the reactor fuel, ITER wall materials and the capability to confine the alphas. JET next T-T and D-T experimental campaigns can therefore address major physics and technological gaps for the development of fusion energy: the isotopic effects on confinement, the access the H mode and ELM behaviour. The total yield of the final D-T phase is expected to be...

43. Electromagnetic FEM studies of disruptions and engineering consequences for the power supply and coils design of planned upper divertor at ASDEX Upgrade

Dr Markus Teschke (Max Planck Institute for Plasma Physics (IPP))

17/09/2018, 15:10

Materials Technology

There is proposed a new upper divertor for the ASDEX Upgrade tokamak experiment [1]. It is planned to be equipped with internal coils for investigation of advanced magnetic configurations like e.g. „snowflake“. Due to the close vicinity of the coils to the plasma, high induced and very stiff voltages are expected during disruption events. Because only very vague analytical estimates of...

44. Integrated current profile, normalized beta and NTM control in DIII-D

Dr Andres Pajares (Lehigh University)

17/09/2018, 16:00

There is an increasing need for integrating individual plasma-control algorithms with the ultimate goal of simultaneously regulating more than one plasma property. Some of these integrated-control solutions should have the capability of arbitrating the authority of the individual plasma-control algorithms over the available actuators within the tokamak. Such decision-making process must run in...

45. Conceptual design of the COMPASS-U tokamak

Dr Radomir Panek (Institute of Plasma Physics of the Czech Academy of Sciences)

17/09/2018, 16:20

Experimental Fusion Devices and Supporting Facilities

The Institute of Plasma Physics of the CAS in Prague has recently started construction of new COMPASS-U tokamak. It will be a compact, medium-size (R = 0,85 m, a = 0,3 m), high-magnetic-field (5 T) device. COMPASS-U will be equipped by a flexible set of poloidal field coils and capable to operate with plasma current up to 2 MA and, therefore, high plasma density (~ 10^20 m^-3). The device is...

46. Development of HINEG and its experimental campaigns

Dr Yican Wu (Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences)

17/09/2018, 16:40

Experimental Fusion Devices and Supporting Facilities

Fusion energy becomes essential to solve the problem of increasing energy demands. A high intensity D-T fusion neutron generator is keenly needed for the research and development (R&D) of fusion technology, especially for fusion materials research.
The Institute of Nuclear Energy Safety Technology (INEST), Chinese Academy of Sciences (CAS) has launched the High Intensity D-T Fusion Neutron...

47. Neutron spectrum determination at the ITER material irradiation stations at JET

Dr Lee Packer (Nuclear Technology, UKAEA,)

17/09/2018, 17:00

Experimental Fusion Devices and Supporting Facilities

The experiments that are planned over the next few years at the Joint European Torus (JET), notably including a deuterium-tritium (DT) experimental phase, are expected to produce large neutron yields, up to 1.7E21 neutrons. The scientific objectives of the experiments are linked with a technology programme, WPJET3, to deliver the maximum scientific and technological return from those...