Title of article
Hydrogen release from irradiated vanadium alloy V–4Cr–4Ti
Author/Authors
Klepikov، نويسنده , , A.Kh and Romanenko، نويسنده , , O.G and Chikhray، نويسنده , , Y.V and Tazhibaeva، نويسنده , , I.L and Shestakov، نويسنده , , V.P and Longhurst، نويسنده , , G.R، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2000
Pages
7
From page
127
To page
133
Abstract
The present work is an attempt to obtain data concerning the influence of neutron and γ irradiation upon hydrogen retention in V–4Cr–4Ti vanadium alloy. The experiments on in-pile loading of vanadium alloy specimens at the neutron flux density 1014 n/cm2 s, hydrogen pressure of 80 Pa, and temperatures of 563, 613 and 773 K were carried out using the IVG.1M reactor of the Kazakhstan National Nuclear Center. A preliminary set of loading/degassing experiments with non-irradiated material has been carried out to obtain data on hydrogen interaction with vanadium alloy. The, data presented in this work are related both to non-irradiated and irradiated samples.
Keywords
Irradiated materials , Hydrogen retention and release , Vanadium alloys
Journal title
Fusion Engineering and Design
Serial Year
2000
Journal title
Fusion Engineering and Design
Record number
2366186
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