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
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