TY - JOUR
T1 - Retention, sputtering and surface chemistry at tungsten oxide surface facing deuterium plasma
AU - Sharkass, Meral
AU - Dwivedi, Swarit
AU - Shin, Yun Kyung
AU - Nieto-Perez, Martin
AU - van Duin, Adri C.T.
AU - Krstic, Predrag S.
N1 - Publisher Copyright:
© 2025
PY - 2025/2
Y1 - 2025/2
N2 - Our study investigates the response of an oxidized tungsten surface to deuterium irradiation in the 5–120 eV impact energy range. Using the LAMMPS molecular dynamics tool and a ReaxFF force field, we analyze the retention, reflection, sputtering, and surface chemistry of oxidized layers at various thicknesses at room temperature. These layers, formed on the tungsten (001) surface through cumulative oxygen irradiation, show that most reflected D atoms and sputtered O atoms originate in the oxide ad-layer, not reaching the W-bulk. The retention probability of D atoms is notably high at the lowest energies, decreasing with energy and approaching metallic tungsten values at higher energies. Our findings, which are compared with those of metallic tungsten and existing literature, provide valuable insights into the behavior of oxidized tungsten surfaces under deuterium plasma irradiation, with potential applications in the design of plasma-facing components for fusion reactors.
AB - Our study investigates the response of an oxidized tungsten surface to deuterium irradiation in the 5–120 eV impact energy range. Using the LAMMPS molecular dynamics tool and a ReaxFF force field, we analyze the retention, reflection, sputtering, and surface chemistry of oxidized layers at various thicknesses at room temperature. These layers, formed on the tungsten (001) surface through cumulative oxygen irradiation, show that most reflected D atoms and sputtered O atoms originate in the oxide ad-layer, not reaching the W-bulk. The retention probability of D atoms is notably high at the lowest energies, decreasing with energy and approaching metallic tungsten values at higher energies. Our findings, which are compared with those of metallic tungsten and existing literature, provide valuable insights into the behavior of oxidized tungsten surfaces under deuterium plasma irradiation, with potential applications in the design of plasma-facing components for fusion reactors.
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U2 - 10.1016/j.jnucmat.2025.155622
DO - 10.1016/j.jnucmat.2025.155622
M3 - Article
AN - SCOPUS:85215084765
SN - 0022-3115
VL - 606
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 155622
ER -