Overview of diagnostics on ITER neutral beam test facility

نویسندگان

  • R. Pasqualotto
  • M. Agostini
  • M. Barbisan
  • F. Bonomo
  • M. Brombin
  • G. Croci
  • M. Dalla Palma
  • R. S. Delogu
  • M. De Muri
  • N. Fonnesu
  • G. Gorini
  • A. Muraro
  • N. Pomaro
  • G. Serianni
  • S. Spagnolo
  • M. Spolaore
  • M. Tardocchi
  • B. Zaniol
چکیده

ITER operation relies on heating neutral beam injectors (HNB) based on negative ion deuterium beams accelerated at 1 MeV, with up to one hour 17 MW power, uniform intensity and low divergence. A neutral beam test facility is being built at Consorzio RFX to demonstrate the feasibility of a prototype injector with such demanding specifications and to optimize its performances. It comprises SPIDER, a 100 kV negative hydrogen/deuterium RF source, full size prototype of the HNB source, and MITICA, a prototype of the full HNB. The diagnostics for SPIDER and MITICA are essential to qualify and optimize the HNB for ITER and to assess the information on source and beam obtainable with the reduced set of the HNB diagnostics. Main parameters are measured with different complementary techniques to exploit the combination of their specific features. In the source the still open issues of cesium dynamics, negative ion generation and uniformity are investigated with a set of electrostatic probes, with optical emission spectroscopy, laser absorption for neutral cesium density and cavity ring down spectroscopy for negative ion density. The beam profile uniformity and its divergence will be studied with beam emission spectroscopy, visible tomography, neutron imaging and a special calorimeter made of carbon tiles which can achieve a spatial resolution of few millimetres. All components heated by beam power load will be monitored with a large set of thermocouples behind the heated surfaces and on the cooling water circuits. The test facility will also be the natural choice for hosting experiments on innovative concepts for DEMO HNBs, e.g. more efficient neutralization techniques and cesium free source operation.

برای دانلود رایگان متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Preliminary Design Concepts for the Control and Data Acquisition Systems of the Iter Neutral Beam Injector and Associated Test Facility

ITER is a joint international research and development project aiming to demonstrate the scientific and technical feasibility of fusion power. The ITER Neutral Beam Injector (negative H or D ion source, 1MV acceleration voltage, 40A ion current, 16.5MW beam power, 1 hour continuous operation) is a major and innovative component of ITER and will be supported by a dedicated Test Facility. The neu...

متن کامل

Negative Ion Based Heating and Diagnostic Neutral Beams for ITER

To meet the requirements of the four operating and one start-up scenarios foreseen in the International Tokamak Experimental Reactor (ITER) a flexible heating mix will be required, which has to include a reliable contribution from neutral beams. The current baseline of ITER foresees 2 Heating Neutral Beam (HNB) systems based on negative ion technology, each operating at 1 MeV 40 A D ions, and e...

متن کامل

Electron Energy Distribution Function Measurements by Langmuir Probe in ITER like Negative Ion Sources

Related Articles Measurement of ion and electron temperatures in plasma blobs by using an improved ion sensitive probe system and statistical analysis methods Rev. Sci. Instrum. 83, 023502 (2012) Diagnostics of the ITER neutral beam test facility Rev. Sci. Instrum. 83, 02B103 (2012) Electron cyclotron resonance ion source plasma chamber studies using a network analyzer as a loaded cavity probe ...

متن کامل

Intense Diagnostic Neutral Beam for ITER

An intense pulsed diagnostic neutral beam (IDNB) is proposed to enable active spectroscopic diagnostics on ITER. The proposed intense neutral beam source will employ a magnetically insulated diode (MID) ion source, consisting of a plasma anode and a virtual cathode. Clean, intense (~25 A/cm) hydrogen or deuterium neutral beams will be generated with an energy up to 125 keV/amu. A short pulse (1...

متن کامل

High energy, high current accelerator development for ITER NBI at JADA

At JAEA as the JApan Domestic Agency (JADA) for ITER, a MAMuG (multi-aperture multi-grid) accelerator has been developed for the ITER neutral beam injector (NBI). Beam parameters achieved by the MAMuG accelerator were increased to 0.32 A H at the ion current density of 140 A/m, from the 0.2 A reported at Chengdu, and 796 keV at the beam energy, which was almost the power supply limit (0.5 A) of...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2015