Title of article
Tritium permeation in EUROFER in EXOTIC and LIBRETTO irradiation experiments
Author/Authors
Fedorov، نويسنده , , A.V. and van Til، نويسنده , , S. and Magielsen، نويسنده , , A.J and Stijkel، نويسنده , , M.P.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2013
Pages
4
From page
2918
To page
2921
Abstract
The reduced activation martensitic steel (RAFM) EUROFER is foreseen as a structural material in test breeder module (TBM) in ITER and breeder blanket in DEMO design. In a number of irradiation experiments conducted in high flux reactor (HFR) in Petten EUROFER was used as a containment wall of the breeder material, through which tritium permeation was monitored on line. Thus in EXOTIC-9/1 (EXtraction Of Tritium In Ceramics) experiment where Li2TiO3 pebbles were the breeder material, EUROFER was irradiated up to 1.3 dpa at 340–580 °C. In LIBRETTO experiments (LIBRETTO-4/1, -4/2 and -5) the breeder material was lead lithium eutectic which was in direct contact with the EUROFER containment wall. The neutron damage in steel achieved in the LIBRETTO experiments varied from 2 to 3.5 dpa. The irradiation temperature was 350 °C (LIBRETTO-4/1), 550 °C (LIBRETTO-4/2), and 300–500 °C (LIBRETTO-5).
m permeability was studied by varying the irradiation temperature and hydrogen concentration in the purge gas. From the analysis of the temperature transients performed in all four experiments yielded the tritium diffusion coefficients were derived, which appear to be factor ten lower than the literature data obtained in the gas driven permeation experiments.
Keywords
diffusion , Neutron irradiation , EUROFER , tritium , permeation
Journal title
Fusion Engineering and Design
Serial Year
2013
Journal title
Fusion Engineering and Design
Record number
2370427
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