Hydrogen release of reactor irradiated RGT-graphite

Experiments on thermal stimulated hydrogen release of irradiated and control samples of RGT-graphite were carried out. Processing of two TDS peaks at temperatures near 770 K and 1100 K in a frame of second order desorption model gives the values of activation energies 2.8 eV/H 2 and 4.0 eV/H 2. Proc...

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Bibliographic Details
Published in:Journal of nuclear materials 1996-10, Vol.233, p.1198-1201
Main Authors: Tazhibaeva, I.L., Klepikov, A.Kh, Shestakov, V.P., Romanenko, O.G., Chikhray, E.V., Kenzhin, E.A., Cherepnin, Yu.S., Tikhomirov, L.N., Zverev, V.A.
Format: Article
Language:English
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Summary:Experiments on thermal stimulated hydrogen release of irradiated and control samples of RGT-graphite were carried out. Processing of two TDS peaks at temperatures near 770 K and 1100 K in a frame of second order desorption model gives the values of activation energies 2.8 eV/H 2 and 4.0 eV/H 2. Processing of a third peak at a temperature near 1300 K, which appeared only for graphite samples irradiated in hydrogen, allows to obtain hydrogen diffusivity in graphite grains D = 1, 8 m 2/s 10 −4exp(−2.5 eV/ kT). It was also shown that simultaneous influence of reactor irradiation and exposition to hydrogen could increase hydrogen retention in graphite.
ISSN:0022-3115
1873-4820
DOI:10.1016/S0022-3115(96)00069-4