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    8th International Workshop on Mechanisms of Vacuum Arcs (MeVArc 2019)

    15–19 Sept 2019
    Orto Botanico - Padova
    Europe/Rome timezone

    MeVArc 2019 contact

    Session

    Applications

    17 Sept 2019, 14:30
    Orto Botanico - Padova

    Orto Botanico - Padova

    Via Orto Botanico, 15 – 35123 Padova, Italy GPS: 45.399444, 11.879807 Orto Botanico - http://www.ortobotanicopd.it/en/

    Presentation materials

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    1. 96. Progress of the ITER Neutral Beam Test Facility project
      Vanni Toigo
      17/09/2019, 14:30
      Applications
      Oral

      This paper gives an overview of the progress of the Neutral Beam Test Facility realization, including the experimental status of SPIDER.

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    2. 93. First year of operation of SPIDER, prototype source of ITER neutral beam injectors
      Dr Gianluigi Serianni (Consorzio RFX)
      17/09/2019, 14:50
      Applications
      Oral

      To reach fusion conditions and to control the plasma configuration in ITER, the next step in thermonuclear fusion research, two heating and current-drive neutral beam injectors (NBIs), each supplying 17MW, by accelerating negative hydrogen or deuterium ions to 1MeV. The requirements of ITER NBIs (40A negative H or D ions for 1 hour) have never been simultaneously attained. So in the dedicated...

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    3. 79. Design of the first vacuum and low-pressure gas insulation tests for the MITICA 1 MV electrostatic Accelerator
      Dr Giuseppe Chitarin (University of Padova and Consorzio RFX)
      17/09/2019, 15:30
      Applications
      Oral

      MITICA is the prototype of the ITER Heating Neutral Beam Injector (NBI), which is designed to generate a 40 A beam of Hydrogen/Deuterium negative ions, to accelerate the ions up to an energy of 1MeV and then to neutralize them, producing a neutral beam of about 16.6 MW power. The design of MITICA is as far as possible identical to the design of the ITER HNB, except that in the ITER NBI, the...

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    4. 89. Surface coatings for arc prevention between plasma facing components
      Dr Luigi Cordaro (Consorzio RFX)
      17/09/2019, 15:50
      Experiments and Diagnostics
      Oral

      The design of the RFX-mod device upgrade requires a 3 mm copper shell close to the plasma to achieve improved plasma confinement properties. Although a continuous conductive structure would be preferred as a passive plasma stabilizer, such a conductive structure shall have an electrical discontinuity in both the poloidal and toroidal directions, in order to allow the penetration of...

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