Conveners
ITER Technology: FIP/1
- Jerome Pamela (CEA Cadarache)
Prof.
Peng FU
(Institute of Plasma Physics, Chinese Academy of Sciences)
17/10/2016, 16:40
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
ASIPP has taken the responsibility of most CN ITER package. All packages follow current ITER schedule.
The superconducting conductor package consists of 106 conductors with 6 kinds includes 7.5% TF conductor,totalPF conductor from PF2 to PF5, total CC conductor, and MB and CB conductor of feeder. Now total CN TF conductor package has been completed in production,and delivered to IO; completed...
Mr
John Smith
(General Atomics)
17/10/2016, 17:00
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The fabrication of the modules for the ITER Central Solenoid (CS) has started in a dedicated production facility located in Poway, California, USA. The necessary tools have been designed, built, installed and tested in the facility to enable the start of production. The current schedule has first module fabrication completed in 2017, followed by testing and subsequent shipment to ITER.
The...
Dr
JUNICHI HIRATSUKA
(National Institutes for Quantum and Radiological Science and Technology)
17/10/2016, 17:20
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
A. In order to realize the negative-ion-based neutral beam (NB) systems for ITER and JT-60SA, development of the Multi-Aperture and Multi-Grid (MAMuG) electrostatic accelerator is one of common critical issues. For these NB injectors, 5- and 3-stage MAMuG accelerators are being developed to achieve the acceleration of negative ion beams up to 1 MeV, 40 A (200 A/m^2) for 3600 s and 0.5 MeV, 22...
Dr
Masashi Kisaki
(JpNIFS)
17/10/2016, 17:40
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
Development of the high performance negative hydrogen ion source is a fundamental demand in realizing fusion reactor. In order to clarify the extraction mechanism of H^-, temporal and spatial variations of the negative ions and electrons in the extraction region are intensively surveyed at NIFS. In addition, the beam acceleration experiments have been performed by changing the accelerator...
Mrs
Aparajita Mukherjee
(Institute for Plasma Research, India)
17/10/2016, 18:00
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The IC H&CD system is one of the major tools for achieving the plasma performances foreseen in ITER's operation scenario. This system is designed to provide 20 MW into the plasma, at frequencies included in the band 40 MHz to 55 MHz. For ensuring 20 MW power availability for plasma operation, 24 MW is required at the output of the RF sources. India is responsible to deliver nine numbers of RF...
Prof.
Grigory Denisov
(Institute of Applied Physics Ruissian Academy of Sciences)
17/10/2016, 18:20
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
A. Gyrotrons for plasma fusion installations usually operate at frequencies 40-170 GHz. Requested output power of the tubes is about 1 MW and pulse duration is between seconds and thousands seconds. To provide operation with indicated parameters the gyrotrons have very large transverse cavity sizes, output barrier windows made of CVD diamond discs, effective collectors with particle energy...
