Abstract
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.
| Original language | English |
|---|---|
| Pages (from-to) | 633-636 |
| Number of pages | 4 |
| Journal | Journal of Nuclear Materials |
| Volume | 417 |
| Issue number | 1-3 |
| DOIs | |
| Publication status | Published - 2011 Oct 1 |
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering
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Atsumi, H., Tanabe, T., & Shikama, T. (2011). Hydrogen behavior in carbon and graphite before and after neutron irradiation - Trapping, diffusion and the simulation of bulk retention. Journal of Nuclear Materials, 417(1-3), 633-636. https://doi.org/10.1016/j.jnucmat.2010.12.100