Bulk hydrogen retention in neutron-irradiated graphite at elevated temperatures

H. Atsumi, T. Tanabe, Tatsuo Shikama

Research output: Contribution to journalArticlepeer-review

15 Citations (Scopus)


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.

Original languageEnglish
Pages (from-to)581-584
Number of pages4
JournalJournal of Nuclear Materials
Issue number1
Publication statusPublished - 2009 Jun 15

ASJC Scopus subject areas

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


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