• Title of article

    Conceptual design of Tritium Extraction System for the European HCPB Test Blanket Module

  • Author/Authors

    Ciampichetti، نويسنده , , A. and Nitti، نويسنده , , F.S. and Aiello، نويسنده , , A. and Ricapito، نويسنده , , I. and Liger، نويسنده , , K. and Demange، نويسنده , , D. and Sedano، نويسنده , , L. and Moreno، نويسنده , , C. and Succi، نويسنده , , M.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2012
  • Pages
    5
  • From page
    620
  • To page
    624
  • Abstract
    The HCPB (Helium Cooled Pebble Bed) Test Blanket Module (TBM), developed in EU to be tested in ITER, adopts a ceramic containing lithium as breeder material, beryllium as neutron multiplier and helium at 80 bar as primary coolant. B-TBM the main function of Tritium Extraction System (TES) is to extract tritium from the breeder by gas purging, to remove it from the purge gas and to route it to the ITER Tritium Plant for the final tritium processing. s paper, starting from a revision of the so far reference process considered for HCPB-TES and considering a new modeling activity aimed to evaluate tritium concentration in purge gas, an updated conceptual design of TES is reported.
  • Keywords
    Tritium extraction , Tritium removal , ITER , Ceramic breeding blanket
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2012
  • Journal title
    Fusion Engineering and Design
  • Record number

    2359366