Title of article
Bulk hydrogen retention in neutron-irradiated graphite at elevated temperatures
Author/Authors
Atsumi، نويسنده , , H. and Tanabe، نويسنده , , T. and Shikama، نويسنده , , T.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2009
Pages
4
From page
581
To page
584
Abstract
Bulk hydrogen retention and the analysis of absorption kinetics have been studied on graphite samples irradiated with neutrons at various fluences. There are two kinds of hydrogen trapping sites: interstitial cluster loop edge sites (trap 1) and carbon dangling bonds at edge surfaces of a crystallite (trap 2). Neutron irradiation preferably creates trap 2 sites at lower fluences and trap 1 sites at higher fluences. The dissociation enthalpy becomes 2–3 times higher for neutron-irradiated samples due to the creation of high energy trapping sites. Absorption kinetics, such as diffusion coefficients and absorption rate constants are strongly affected by neutron irradiation and annealing after irradiation.
Journal title
Journal of Nuclear Materials
Serial Year
2009
Journal title
Journal of Nuclear Materials
Record number
1365915
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