Login

29th Symposium on Fusion Technology (SOFT 2016)

Sep 5 – 9, 2016
Prague Congress Centre
Europe/Prague timezone

Session

O4B

Sep 8, 2016, 11:00 AM
Prague Congress Centre

Prague Congress Centre

5. května 65, Prague, Czech Republic

Presentation materials

There are no materials yet.

  1. 49528. O4B.1 Potential approach of IR-analysis for HHF quality assessment of ITER tungsten divertor targets
    Henri Greuner (Max-Planck-Institut für Plasmaphysik)
    9/8/16, 11:00 AM
    F. Plasma Facing Components
    Oral
    Plasma-facing units equipped with tungsten (W) monoblock geometry are employed at the vertical targets of the ITER divertor. This contribution discusses a statistical approach for high heat flux (HHF) tests as potential quality assessment of the ITER divertor additional to the quality assurance performed by the manufacturer during the manufacturing. The IR analysis of the local temperature...
    Go to contribution page
  2. 49529. O4B.2 Fabrication and acceptance of ITER vertical target divertor full scale plasma facing units
    Eliseo Visca (Department of Fusion and Technology for Nuclear Safety and Security)
    9/8/16, 11:20 AM
    F. Plasma Facing Components
    Oral
    ENEA and Ansaldo Nucleare S.p.A. (ANN) have being deeply involved in the European International Thermonuclear Experimental Reactor (ITER) development activities for the manufacturing of the inner vertical target (IVT) plasma-facing components of the ITER divertor. During normal operation the heat flux deposited on the bottom segment of divertor is 5-10 MW/m2 but the capability to remove up to...
    Go to contribution page
  3. 49530. O4B.3 DiMES PMI research at DIII-D in support of ITER and beyond
    Dmitry Rudakov (Center for Energy Research)
    9/8/16, 11:40 AM
    F. Plasma Facing Components
    Oral
    An overview of recent Plasma-Material Interactions (PMI) research at DIII-D tokamak using the Divertor Material Evaluation Station (DiMES) is presented. The DiMES manipulator allows exposing material samples in the lower divertor of DIII-D under well-diagnosed ITER-relevant plasma conditions. Plasma parameters during the exposures are characterized by the extensive diagnostic suite including a...
    Go to contribution page
  4. 49531. O4B.4 HELCZA – High Heat Flux Test Facility for Testing ITER EU First Wall Components
    Jan Prokupek (Technological Experimental Loops)
    9/8/16, 12:00 PM
    F. Plasma Facing Components
    Oral
    The ITER first wall panels are exposed directly to thermonuclear plasma and must extract heat loads of about 2 MW/m² (EU) to 4.7 MW/m² (RF + CN). The panels are qualified through high heat flux cyclic testing before the installation in ITER. Initially the first wall panel prototypes will undergo full-power tests, this will be followed by the pre-series panels and finally the series panels. The...
    Go to contribution page
Building timetable...