Details

Autor(en) / Beteiligte

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

Titel

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

Ist Teil von

• Journal of nuclear materials, 2011-08, Vol.415 (1), p.S667-S671

Ort / Verlag

Amsterdam: Elsevier B.V

Erscheinungsjahr

2011

Quelle

Alma/SFX Local Collection

Beschreibungen/Notizen

• 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 323K to 0.025dpa 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: 5×1021m−2s−1, ion fluence: 4×1025m−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.