Conveners
Heating & Disruption: FIP/2
- Alexander Litvak (Russian Federation)
Mr
So Maruyama
(ITER Organization)
15/10/2014, 08:30
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
Disruptions present a challenge for ITER to withstand the intense heat flux, the large forces from halo currents, and the potential first wall damage from multi-MeV runaway electrons. Injecting large quantities of material into the plasma when a disruption is detected will reduce the plasma energy and increase its resistivity and electron density to mitigate these effects and thus a system...
Mr
Yasuhisa Oda
(Japan)
15/10/2014, 08:50
Oral
A
To study the operational performance of ITER EC heating and current drive system (H&CD), a mock-up of the ITER mm wave system has been assembled using the high power long gyrotron test stand in JAEA. The prototype system is composed of the primary parts of the EC H&CD system, including: 170GHz gyrotron, power supply, transmission line (TL) and mock-up of equatorial launcher (EL) and control...
Mr
Stephen Wukitch
(USA)
15/10/2014, 09:10
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
Future fusion reactors will present more severe constraints on ion cyclotron range of frequency (ICRF) heating and current drive actuators than ITER. Reliably coupling power to the plasma despite load variations is critical. In addition, ICRF interaction with the edge plasma, particularly impurity contamination and enhanced localized heat loads, is challenging. We report on progress...
Mr
Antonio Masiello
(European Commission)
15/10/2014, 09:30
Oral
The development of the Neutral beam system for ITER has been progressing well thanks to the start of the operations of the ELISE (Extraction from a Large Ion Source Experiment) at the Max Planck Institute for Plasma Physics in Garching, Germany, and to the big effort devoted to the establishment of the ITER Neutral Beam (NB) Test Facility in Padua, Italy.
This paper presents the main...
Mr
Hiroyuki Tobari
(Japan)
15/10/2014, 09:50
Oral
A
In the ITER NBI for plasma heating and current drive, a 1 MeV, 40 A deuterium negative ion (D-) beam is designed to be accelerated for 3600 s. The beam energy and the pulse duration of the D- beam are 2-5.5 times higher and 360 times longer than those in the negative-ion-based NBIs on LHD and JT-60U, respectively. Thus, to realize higher voltage and longer pulse duration, the generation,...
