• Title of article

    High heat flux thermal–hydraulic analysis of ITER divertor and blanket systems

  • Author/Authors

    Raffray، نويسنده , , A.R and Chiocchio، نويسنده , , S and Ioki، نويسنده , , K and Krassovski، نويسنده , , D and Kubik، نويسنده , , D and Tivey، نويسنده , , R، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 1998
  • Pages
    9
  • From page
    323
  • To page
    331
  • Abstract
    Three separate cooling systems are used for the divertor and blanket components, based mainly on flow routing access and on grouping together components with the highest heat load levels and uncertainties: divertor, limiter/outboard baffle, and primary first wall/inboard baffle. The coolant parameters for these systems are set to accommodate peak heat load conditions with a reasonable critical heat flux (CHF) margin. Material temperature constraints and heat transport system space and cost requirements are also taken into consideration. This paper summarises the three cooling system designs and highlights the high heat flux thermal–hydraulic analysis carried out in converging on the design values for the coolant operating parameters. Application of results from on-going high heat flux R&D and a brief description of future R&D effort to address remaining issues are also included.
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    1998
  • Journal title
    Fusion Engineering and Design
  • Record number

    2364582