Tritium permeation in EUROFER in EXOTIC and LIBRETTO irradiation experiments

被引:9
作者
Fedorov, A. V. [1 ]
van Til, S. [1 ]
Magielsen, A. J. [1 ]
Stijkel, M. P. [1 ]
机构
[1] Nucl Res & Consultancy Grp, NL-1755 ZG Petten, Netherlands
关键词
Tritium; Permeation; Diffusion; EUROFER; Neutron irradiation; HYDROGEN TRANSPORT; BEHAVIOR; REACTOR; STEELS;
D O I
10.1016/j.fusengdes.2013.06.003
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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 degrees 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 degrees C (LIBRETTO-4/1), 550 degrees C (LIBRETTO-412), and 300-500 degrees C (LIBRETTO-5). Tritium 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. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:2918 / 2921
页数:4
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