Abstract
Tungsten samples (99.99% purity from A.L.M.T. Corp., 6 mm in diameter, 0.2 mm in thickness) were irradiated by high-flux neutrons at 50°C to 0.025 dpa in the High Flux Isotope Reactor at Oak Ridge National Laboratory. Subsequently, the neutron-irradiated tungsten samples were exposed to high-flux deuterium plasmas (ion flux: 10 21-10 22 m -2 s -1, ion fluence: 10 25-10 26 m -2) in the Tritium Plasma Experiment at Idaho National Laboratory. This paper reports the results of deuterium depth profiling in neutron-irradiated tungsten exposed to plasmas at 100, 200 and 500°C via nuclear reaction analysis (NRA). The NRA measurements show that a significant amount of deuterium (>0.1 at.% D/W) remains trapped in the bulk material (up to 5 μm) at 500°C. Tritium Migration Analysis Program simulation results using the NRA profiles indicate that different trapping mechanisms exist for neutron-irradiated and unirradiated tungsten.
Original language | English |
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Article number | 014051 |
Journal | Physica Scripta T |
Volume | T145 |
DOIs | |
State | Published - 2011 |
Event | 13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications, PFMC-13 and 1st International Conference on Fusion Energy Materials Science, FEMaS-1 - Rosenheim, Germany Duration: 2011/05/09 → 2011/05/13 |
ASJC Scopus subject areas
- Atomic and Molecular Physics, and Optics
- Mathematical Physics
- Condensed Matter Physics