TY - JOUR
T1 - First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE
AU - Shimada, Masashi
AU - Hatano, Y.
AU - Calderoni, P.
AU - Oda, T.
AU - Oya, Y.
AU - Sokolov, M.
AU - Zhang, K.
AU - Cao, G.
AU - Kolasinski, R.
AU - Sharpe, J. P.
PY - 2011/8/1
Y1 - 2011/8/1
N2 - 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.
AB - 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.
UR - https://www.scopus.com/pages/publications/80054843064
U2 - 10.1016/j.jnucmat.2010.11.050
DO - 10.1016/j.jnucmat.2010.11.050
M3 - Article
AN - SCOPUS:80054843064
SN - 0022-3115
VL - 415
SP - S667-S671
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1 SUPPL
ER -