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T.V. Kulsartov, Y.V. Chikhray, I.L. Tazhibaeva, V.P. Shestakov
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 919-923
Plasma Facing Components Technology (Poster Session) | doi.org/10.13182/FST98-A11963730
Articles are hosted by Taylor and Francis Online.
Be-copper alloy duplex structures are planed to be used as the structural material of the first wall for ITER. CuCr1Zr0.1 copper alloy is one of the prospective components of such structures. To ensure safety and to solve ecological problems concerning fusion reactor operation it is necessary to have estimations of tritium inventory in the copper alloy CuCr1Zr0.1 and in Be-copper alloy duplex structures.
In this work the results of the following experiments on determination of hydrogen permeation parameters are presented:
• Investigation of hydrogen permeation for beryllium-copper duplex structure. Experiments were carried out in the temperature range from 873 K to 1023 K, at input hydrogen pressures between 102 Pa and 103 Pa.
• Investigation of hydrogen permeation for copper alloy CuCr1Zr0.1 in the temperature range from 723 K to 973 K, at input pressures of hydrogen between 102 and 103 Pa and for samples with different thickness.
