Microstructure of long-term annealed highly irradiated beryllium

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The Material Testing Reactor BR2 of SCKÆCEN has a beryllium matrix which has been replaced in 1995. Pieces of this matrix, which were irradiated over a period of 15 yr at about ±50 C up to a fast neutron fluence (E > 1 MeV) of 4.67 · 1022 n/cm2, have been retrieved for creep and microstructure studies. An amount of helium resulting from transmutation has accumulated up to approximately 2.2 at.% which is comparable to the expected He content of a fusion reactor blanket at its end of life. Post-irradiation anneals have been performed at 500, 750 and 900 C, with an annealing time ranging between 50 hours and three months. Microstructural analyses show a clear evolution in bubble growth and He diffusion towards the grain boundaries where the bubbles coalesce. Complete release of 4He is observed at temperatures >750 C, resulting in a stagnation of the beryllium swelling. The microstructural changes are mainly temperature driven. Only at high annealing temperature, an influence of the annealing time is observed.


Original languageEnglish
Pages (from-to)256-262
JournalJournal of Nuclear Materials
Issue number2-3
Publication statusPublished - 31 Jan 2008


  • Beryllium, microstructure

ID: 70741