Dr
Masataka Nakahira
(JpQSTNFI)
22/10/2018, 16:40
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
This paper reports the completion of the first Toroidal Field Coil Structure (TFCS) of ITER of which Japan Domestic Agency (JADA) takes 100% share on procurement responsibility. The major technical challenges of the TFCS of ITER are (i) new material development for high ductility under cryogenic temperature (4K), (ii) application of partial penetration welding (PPW), (iii) welding deformation...
Dr
Yasuhisa Oda
(National Institute for Quantum and Radiological Science and Technology)
22/10/2018, 17:00
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
A. This paper presents a summary of recent progress pertaining to the manufacturing and inspection of ITER gyrotrons and their operation system in QST. Major achievements are as follows: (i) The final design of ITER gyrotron was accomplished and manufacturing of 2 ITER gyrotrons was finished. Then their factory acceptance test (FAT) in QST has started with ITER relevant high voltage power...
Dr
Yasuhisa Oda
(Japan Atomic Energy Agency)
22/10/2018, 17:10
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
As a part of in-kind contribution, India is responsible to deliver nine numbers (1 Prototype + 8 series production) of RF Sources to ITER system, each having power handling capability of 2.5 MW/CW at VSWR 2:1 in the frequency range 35 – 65 MHz or 3.0 MW/CW at VSWR 1.5:1 in the frequency range 40 – 55 MHz, along with other stringent requirements. As there is no such amplifier chain able to meet...
Dr
Yasuhisa Oda
(Japan Atomic Energy Agency)
22/10/2018, 17:15
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The European 1 MW, 170 GHz industrial prototype CW gyrotron for ECRH&CD on ITER is a conventional (hollow-cavity) gyrotron, which is being developed by the European GYrotron Consortium (EGYC) in cooperation with the industrial partner Thales Electron Devices (TED), under the coordination of the European Joint Undertaking for ITER and the Development of Fusion Energy (F4E).
The CW industrial...
Mr
Jaydeepkumar Joshi
(ITER-India (Institute for Plasma Research))
22/10/2018, 17:20
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
A. Technologies for manufacturing of small and medium size Ion source (upto four RF driver) for positive and negative neutral beam systems have been evolved over last many decades and such ion sources are being successfully operated at various experimental facilities across the world. However, as the need arises for the larger size ion sources (eight driver) for ITER diagnostics and heating...
Mr
Jaydeepkumar Joshi
(ITER-India (Institute for Plasma Research))
22/10/2018, 17:30
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
The ITER Heating Neutral Beam (HNB) injectors, one of the tools necessary both to achieve burning conditions and to control plasma instabilities, are characterized by such demanding parameters as to require the construction of a test facility dedicated to their development and optimization.
This facility, called NBTF, is in an advanced state of realization in Padua (Italy), with the direct...
Mr
Jaydeepkumar Joshi
(ITER-India (Institute for Plasma Research))
22/10/2018, 17:35
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
For the ITER neutral beam (NB) system, a measure to achieve the 1 MV vacuum insulation of the beam source have been developed. For this purpose, design basis for 1 MV vacuum insulation has been developed by integrating previous empirical scaling for plane and coaxial electrodes and new scaling for area with locally-concentrated electric field. Consequently, as the measure, the beam source is...
Dr
Andrey Litnovsky
(Forschungszentrum Juelich, Germany)
22/10/2018, 17:40
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
Mirrors will be used as first plasma-viewing elements in optical and laser-based diagnostics in ITER. Deterioration of the mirror performance due to e.g. sputtering of the mirror surface by plasma particles or deposition of plasma impurities will hamper the entire performance of the affected diagnostic. Specialists Working Group on First Mirrors (FM SWG) in the Topical Group on Diagnostics of...
Dr
Eugene Mukhin
(Ioffe Institute)
22/10/2018, 18:00
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
This paper describes the benefits and challenges of divertor Thomson scattering 55.C4 (DTS) and laser-induced fluorescence 55.EA (LIF) integration in the divertor port #8 of ITER. One of the main challenges for the DTS system is to measure extremely low electron temperatures in the vicinity of the divertor plates. The cool and dense divertor plasma leads to pronounced collective effects and...
Prof.
Xiaoyu WANG
(Southwestern Institute of Physics)
22/10/2018, 18:20
FIP - Fusion Engineering, Integration and Power Plant Design
Oral
As the testing mockup of tritium breeding blanket for DEMO, Chinese Helium Coolant Ceramic Breeder (HCCB) Test Blanket System (TBS) are under developing by China and will be tested in ITER to verify the key tritium breeding blanket technologies. After the approval of conceptual design by ITER Organization in 2015, the design optimization and more R&D activities for HCCB TBS have been under...
