Hydrogen release from irradiated vanadium alloy V–4Cr–4Ti

Hydrogen release from irradiated vanadium alloy V–4Cr–4Ti

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 10 14 n/cm 2 s, hydrogen pressure of 80 Pa, and temperat...

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Veröffentlicht in:Fusion engineering and design 2000-11, Vol.51, p.127-133
Hauptverfasser: Klepikov, A.Kh, Romanenko, O.G, Chikhray, Y.V, Tazhibaeva, I.L, Shestakov, V.P, Longhurst, G.R
Format: Artikel
Sprache:eng
Schlagworte:
Applied sciences
Controled nuclear fusion plants
Energy
Energy. Thermal use of fuels
Exact sciences and technology
FLUX DENSITY
GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
HYDROGEN
Hydrogen retention and release
Installations for energy generation and conversion: thermal and electrical energy
Irradiated materials
IRRADIATION
KAZAKHSTAN
NEUTRON FLUX
NEUTRONS
RETENTION
Ternary systems
VANADIUM ALLOYS
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Zusammenfassung: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 10 14 n/cm 2 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.
ISSN:0920-3796
1873-7196
DOI:10.1016/S0920-3796(00)00305-7