TY - JOUR
T1 - Hydrogen behavior in carbon and graphite before and after neutron irradiation - Trapping, diffusion and the simulation of bulk retention
AU - Atsumi, H.
AU - Tanabe, T.
AU - Shikama, T.
PY - 2011/10/1
Y1 - 2011/10/1
N2 - Bulk hydrogen retention and the mechanisms of hydrogen transport in graphite and carbon materials are summarized in the first half of the paper. From the various data on hydrogen retention, diffusion coefficients, nature of trapping sites and annealing effects, simulation of bulk hydrogen retention is performed. Neutron irradiation tends to increase hydrogen retention approximately 100 times larger than that of unirradiated graphite.
AB - Bulk hydrogen retention and the mechanisms of hydrogen transport in graphite and carbon materials are summarized in the first half of the paper. From the various data on hydrogen retention, diffusion coefficients, nature of trapping sites and annealing effects, simulation of bulk hydrogen retention is performed. Neutron irradiation tends to increase hydrogen retention approximately 100 times larger than that of unirradiated graphite.
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U2 - 10.1016/j.jnucmat.2010.12.100
DO - 10.1016/j.jnucmat.2010.12.100
M3 - Article
AN - SCOPUS:80053606327
VL - 417
SP - 633
EP - 636
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
SN - 0022-3115
IS - 1-3
ER -