Refine your search:     
Report No.
Search Results: Records 1-3 displayed on this page of 3
  • 1

Presentation/Publication Type

Initialising ...


Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...


Initialising ...


Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Progress on the heating and current drive systems for ITER

Jacquinot, J.*; Albajar, F.*; Beaumont, B.*; Becoulet, A.*; Bonicelli, T.*; Bora, D.*; Campbell, D.*; Chakraborty, A.*; Darbos, C.*; Decamps, H.*; et al.

Fusion Engineering and Design, 84(2-6), p.125 - 130, 2009/06

 Times Cited Count:24 Percentile:82.52(Nuclear Science & Technology)

The electron cyclotron (EC), ion cyclotron (IC), neutral beam (NB) and, lower hybrid (LH) systems for ITER have been reviewed in 2007/2008 in light of progress of physics and technology. Although the overall specifications are unchanged, notable changes have been approved. Firstly, the full 73MW should be commissioned and available on a routine basis before the D/T phase. Secondly, the possibility to operate the NB at full power during the hydrogen phase requiring new shine through protection; IC with 2 antennas with increased robustness; 2 MW transmission systems to provide an easier upgrading of the EC power; the addition of a building dedicated to the RF power sources and to a testing facility for acceptance of diagnostics and heating port plugs. Thirdly, the need of a plan for developing, in time for the active phase, a CD system such as LH suitable for very long pulse operation of ITER was recognized.

Journal Articles

Design of electron cyclotron heating and current drive system of ITER

Kobayashi, Noriyuki; Bigelow, T.*; Bonicelli, T.*; Cirant, S.*; Denisov, G.*; Heidinger, R.*; Henderson, M.*; Hogge, J.-P.*; Piosczyk, B.*; Ramponi, G.*; et al.

AIP Conference Proceedings 933, p.413 - 416, 2007/10

Since the EDA 2001, Design of Electron Cyclotron Heating and Current Drive (ECH&CD) System have been modified due to progress of physics understanding and change of interface. Nominal RF power 20 MW is injected by four upper launchers or one equatorial launcher. RF beams are steered by a front steering mirror. DCHV power supply will be composed of IGBT pulse step modulators because of high frequency modulation and design flexibility to three different types of 170 GHz gyrotrons from three parties. The RF power is transmitted by 63.5 mm dia corrugated waveguide and switched by a waveguide switch between the upper launcher and the equatorial launcher. A start-up system for initial discharge is composed of three 127.5 GHz gyrotrons and dedicated DCHV power supply. Three of transmission lines are shared between 170 GHz and 127.5 GHz gyrotrons to inject start-up RF beam through the equatorial launcher. R&Ds for high power long pulse have been on-going to obtain a reliable ITER ECH&CD system.

Oral presentation

Pellet fueling technology development for efficient fueling of burning plasma in ITER

Baylor, L. R.*; Parks, P. B.*; Jernigan, T. C.*; Caughman, J. B.*; Combs, S. K.*; Fenstermacher, M. E.*; Foust, C. R.*; Houlberg, W. A.*; Lasnier, C. J.*; Maruyama, So; et al.

no journal, , 

Pellet injection is the primary fuelling technique for efficient core fuelling of ITER burning plasma. Pellet survivability and pellet mass loss have been demonstrated using a mockup of ITER inboard injection line. This experiment has revealed that pellets survive intact up to 300m/s, which is required for inboard injection. The series of experiments have demonstrated that pellet mass loss at extremely high back pressure remains $$<$$20% ($$<$$10% at $$<$$300m/s). The pellet mass deposition has been numerically evaluated. It shows that inboard launching, present ITER reference, of 3 mm and 5mm cylindrical pellets at 300 m/s has a capability to fuel well inside the separatrix. The fuelling efficiency is predicted to be nearly 100%, which will help to minimize the tritium retention of the first wall. Pellet injected in to the present day tokamaks have been found to trigger ELMs in H-mode plasma. ITER will have the pellet injection technology as an ELM mitigation system.

3 (Records 1-3 displayed on this page)
  • 1