TY - JOUR
T1 - GD-OES study of the influence of second phase particles on the deuterium depth distribution in dispersion-strengthened tungsten
AU - Lang, E.
AU - Taylor, C. N.
AU - Allain, J. P.
N1 - Funding Information:
The characterization was carried out in part in the Frederick Seitz Materials Research Laboratory Central Research Facilities, University of Illinois. This work is supported by US DOE Contract No. DE-SC0014267 and DE-AC07-05ID14517 .
Funding Information:
The characterization was carried out in part in the Frederick Seitz Materials Research Laboratory Central Research Facilities, University of Illinois. This work is supported by US DOE Contract No. DE-SC0014267 and DE-AC07-05ID14517.
Publisher Copyright:
© 2020 Elsevier B.V.
PY - 2020/4/15
Y1 - 2020/4/15
N2 - Dispersion-strengthened tungsten materials represent a new class of W-based materials to be investigated for use as plasma-facing component in nuclear fusion reactors. However, the retention and permeation characteristics of these materials under low energy deuterium (D) irradiation need to be elucidated before the efficacy of these materials can be judged. Due to possible deep penetration of D in W, depth profile techniques such as glow discharge optical emission spectroscopy (GD-OES) are needed to probe D concentrations many microns beneath the material surface. In this study, the D retention behavior of W materials containing 1–10 wt% TaC, TiC, or ZrC are investigated with GD-OES. After exposure to a 5 × 1018cm−2 D ion fluence at 100 °C, D was observed beyond the D implantation depth the surface in many specimens, and the D depth profile was found to depend on the type and concentration of the added second phase. Combined with in-situ X-ray Photoelectron Spectroscopy (XPS) studies, the effects of impurity oxygen atoms on the D retention is considered, as an increasing oxygen content correlates with decreased D retention. The influence of grain size, second phase particles, and oxygen content on the retained D depth and concentration in these complex W-based materials is discussed.
AB - Dispersion-strengthened tungsten materials represent a new class of W-based materials to be investigated for use as plasma-facing component in nuclear fusion reactors. However, the retention and permeation characteristics of these materials under low energy deuterium (D) irradiation need to be elucidated before the efficacy of these materials can be judged. Due to possible deep penetration of D in W, depth profile techniques such as glow discharge optical emission spectroscopy (GD-OES) are needed to probe D concentrations many microns beneath the material surface. In this study, the D retention behavior of W materials containing 1–10 wt% TaC, TiC, or ZrC are investigated with GD-OES. After exposure to a 5 × 1018cm−2 D ion fluence at 100 °C, D was observed beyond the D implantation depth the surface in many specimens, and the D depth profile was found to depend on the type and concentration of the added second phase. Combined with in-situ X-ray Photoelectron Spectroscopy (XPS) studies, the effects of impurity oxygen atoms on the D retention is considered, as an increasing oxygen content correlates with decreased D retention. The influence of grain size, second phase particles, and oxygen content on the retained D depth and concentration in these complex W-based materials is discussed.
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U2 - 10.1016/j.jnucmat.2020.152047
DO - 10.1016/j.jnucmat.2020.152047
M3 - Article
AN - SCOPUS:85079872516
SN - 0022-3115
VL - 532
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 152047
ER -