Author/Authors :
Norajitra، نويسنده , , P. and Giniyatulin، نويسنده , , R. and Ihli، نويسنده , , T. and Janeschitz، نويسنده , , G. and Krauss، نويسنده , , W. and Kruessmann، نويسنده , , R. and Kuznetsov، نويسنده , , V. and Mazul، نويسنده , , I. and Widak، نويسنده , , V. and Ovchinnikov، نويسنده , , I. and Ruprecht، نويسنده , , R. and Zeep، نويسنده , , B.، نويسنده ,
Abstract :
Goal of the He-cooled divertor development for future fusion power plants is to resist a high heat flux of at least 10 MW/m2. The development includes the fields of design, analyses, and experiments. A helium-cooled modular jet concept (HEMJ) has been defined as reference solution, which is based on jet impingement cooling. In cooperation with the Efremov Institute, work was aimed at construction and high heat flux tests of prototypical tungsten mockups to demonstrate their manufacturability and their performances. A helium loop was built for this purpose to simulate the realistic thermo-hydraulics conditions close to those of DEMO (10 MPa He, 600 °C). The first high heat flux test results confirm the feasibility and the performance of the divertor design.
Keywords :
Helium-cooled divertor , Joining of tungsten parts , High-temperature brazing , High-heat-flux experiment
