Hydrogenic retention in tungsten exposed to ITER divertor relevant plasma flux densities

G.M. Wright, A.W. Kleyn, E. Alves, L.C. Alves, N.P. Barradas, G.J. Rooij, van, A.J. Lange, van, A.E. Shumack, J. Westerhout, R.S. Al, W.A.J. Vijvers, B. Groot, de, M.J. Pol, van de, H.J. Meiden, van der, J. Rapp, N.J. Lopes Cardozo

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Tungsten targets are exposed to the plasma conditions expected at the strike point of a detached ITER divertor (~1024 D/m2s, Te ~ 2 eV). The surface temperature of the target is ~1600 K at the center and decreased radially to ~1000 K at the edges. A 2-D spatial scan of the W target using nuclear reaction analysis (NRA) shows an asymmetric D retention profile with the lowest retention values at the center of the target and the highest 6 mm off-center. Even in the regions of larger retention, the D concentrations were =5 × 1015 D/cm2 as measured by NRA. Thermal desorption spectroscopy (TDS) is used to measure the global D retention. Very low retention with retained fractions ranging from 10-7 to 10-5 Dretained/Dincident were measured with TDS. Both NRA and TDS results show no clear dependence of retention on incident fluence possibly indicating the absence of plasma-driven trap production in W under these conditions.
Original languageEnglish
Pages (from-to)610-613
JournalJournal of Nuclear Materials
Issue number1
Publication statusPublished - 2009

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