• DocumentCode
    3201703
  • Title

    Heat flux test of various Be mockups for ITER FW development at Korea heat load test facility KoHLT-1

  • Author

    Bae, Young-Dug ; Kim, Suk-Kwon ; Lee, Dong-Won ; Shin, Hee-Yun ; Hong, Bong-Guen

  • Author_Institution
    Nucl. Fusion Eng. Div., Korea Atomic Energy Res. Inst., Daejeon, South Korea
  • fYear
    2009
  • fDate
    1-5 June 2009
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    We established a heat load test facility using a graphite heating panel in 2008 in order to verify the integrity of a HIP bonded first wall. The facility is called KoHLT-1 and is currently in operation to test the Be mockups. The KoHLT-1 consists of a graphite heating panel, a box-type test chamber with water-cooling jackets, an electrical power supply, a water-cooling system, an evacuation system, an He gas system, and some diagnostics, which are equipped in an authorized laboratory with a special ventilation system for the Be treatment. We designed and fabricated several graphite heating panels to have various heating areas depending on the tested mockups. The heat fluxes on the two mockups are independently measured by a calorimetric method. We have carried out the thermal cycle tests of various Be mockups. The nominal heat flux was 0.625 MW/m2 or 1.5 MW/m2 depending on the mockup sizes.
  • Keywords
    Tokamak devices; beryllium; fusion reactor design; fusion reactor materials; fusion reactor operation; graphite; hot pressing; plasma heating; plasma-wall interactions; test facilities; Be mockups; HIP bonded first wall; He gas system; ITER first wall; KoHLT-1; Korea Heat Load Test Facility; box-type test chamber; calorimetric method; electrical power supply; evacuation system; graphite heating panel; heat flux test; heat fluxes; heat load test facility; hot isostatic pressing; thermal cycle tests; ventilation system; water-cooling jackets; Bonding; Heat engines; Heat sinks; Heat treatment; Hip; Resistance heating; System testing; Temperature; Test facilities; Water heating; ITER; KoHLT-1; first wall; heat flux test;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    978-1-4244-2635-5
  • Electronic_ISBN
    978-1-4244-2636-2
  • Type

    conf

  • DOI
    10.1109/FUSION.2009.5226501
  • Filename
    5226501