First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE

Masashi Shimada, Y. Hatano, P. Calderoni, T. Oda, Y. Oya, M. Sokolov, K. Zhang, G. Cao, R. Kolasinski, J. P. Sharpe

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75 Scopus citations

Abstract

With the Japan-US joint research project Tritium, Irradiations, and Thermofluids for America and Nippon (TITAN), an initial set of tungsten samples (99.99% purity, A.L.M.T. Co.) were irradiated by high flux neutrons at 323 K to 0.025 dpa in High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Subsequently, one of the neutron-irradiated tungsten samples was exposed to a high-flux deuterium plasma (ion flux: 5 × 1021 m -2 s-1, ion fluence: 4 × 1025 m -2) in the Tritium Plasma Experiment (TPE) at Idaho National Laboratory (INL). The deuterium retention in the neutron-irradiated tungsten was 40% higher in comparison to the unirradiated tungsten. The observed broad desorption spectrum from neutron-irradiated tungsten and associated TMAP modeling of the deuterium release suggest that trapping occurs in the bulk material at more than three different energy sites.

Original languageEnglish
Pages (from-to)S667-S671
JournalJournal of Nuclear Materials
Volume415
Issue number1 SUPPL
DOIs
StatePublished - Aug 1 2011

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