EVALUATION OF THE EFFECTS OF IMPURITIES ON SAES® ST198 HYDROGEN GETTERING
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Presently, the use of tungsten as the plasma facing material (PFM) is foreseen at the strikepoints and far-target regions of divertors for next generation (e.g. ITER) tokamak reactor experiments.
Abstract not provided.
Presented by NETL at TMS 2019, 3/19
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Presented by NETL at MS&T 2019, 09/19
Presented by NETL at TMS 2020, 02/20
Abstract not provided.
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Abstract not provided.