D retention in C- and O-contaminated tungsten during D + irradiation
D retention in C- and O-contaminated tungsten during D + irradiation
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DOI:
10.1016/j.jnucmat.2012.04.004
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发表时间:
2012-08
影响因子:
3.1
通讯作者:
J. Roszell;A. Labelle;P. Brodersen;J. Davis;A. A. Haasz-A.
中科院分区:
文献类型:
--
作者:
J. Roszell;A. Labelle;P. Brodersen;J. Davis;A. A. Haasz-A.
Deuterium retention during 10eV and 500eV/D+irradiations at 300 and 500K was compared for 99.96% pure polycrystalline tungsten (PCW) foils and similar PCW foils contaminated with carbon and oxygen impurities. The contaminated foils showed reduced deuterium retention at 500K compared with pure foil specimens while there was no difference for 300K irradiations. X-ray photoelectron spectroscopy (XPS) and secondary ion mass spectroscopy (SIMS) of the unirradiated specimens showed regions of highly localised, non-homogeneous C and O contamination as well as a broader region of low level contamination of about 1–10% areal coverage. It is hypothesised that the C/O contamination creates a diffusion barrier in the PCW foil preventing deuterium from diffusing from the near surface into the bulk, thus reducing overall D retention at 500K. This finding has implications for tritium retention in ITER; if carbon contamination even at low levels can impede T diffusion into the bulk it would mean reduced T loading in W plasma-facing components.