Hydrogen behavior in carbon and graphite before and after neutron irradiation - Trapping, diffusion and the simulation of bulk retention

H. Atsumi, T. Tanabe, T. Shikama

Research output: Contribution to journalArticle

29 Citations (Scopus)

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 languageEnglish
Pages (from-to)633-636
Number of pages4
JournalJournal of Nuclear Materials
Volume417
Issue number1-3
DOIs
Publication statusPublished - 2011 Oct 1

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

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