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 m2 s1, ion fluence: 4 1025 m2) 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.
