A first study of the complex-concentrated-alloy W38Ta36Cr15V11 in Pisces-RF high-flux deuterium plasma

Bulk targets of W 38 Ta 36 Cr 15 V 11 complex concentrated alloy (CCA) were produced by spark plasma sintering at the Vecchio materials research lab at the University of California–San Diego. Targets fabricated were reasonably dense, BCC phase, compositionally close in match to that of El-Atwani et al. (2019), and homogeneous, as measured by electron microscopy, energy dispersive x-ray microanalysis (EDX), EDX mapping, and x-ray diffraction. The targets were exposed to deuterium plasma of associated 100 eV ion fluences of 2 × 1 0 26 m −2 at 523 K, 773 K and 1023 K in the Pisces-RF high-flux linear plasma device. Plasma exposure is found to produce surface compositional enrichment in W and Ta, as determined by Auger electron spectroscopy and EDX, that is caused by a depletion of surface Cr and V, the former being observed with optical emission spectroscopy in the target plasma. Accompanying the compositional change, transient grating spectroscopy analysis, taken pre- and post-plasma exposure on the 1023 K exposed target, revealed ∼ 30 % reduction in surface thermal diffusivity from 9 . 4 × 1 0 − 6 m 2 s −1 to 6 . 7 × 1 0 − 6 m 2 s −1 . Lastly, D retention in the CCA targets was found to be characterized by a singular thermal release peak at ∼ 900 K, and retention varied from 2 × 1 0 23 m −2 to 3 × 1 0 20 m −2 for exposure in the temperature range 523–1023 K, as measured by thermal desorption spectrometry. This level of D retention is found to be high relative to pure tungsten. • Bulk W 38 Ta 36 Cr 15 V 11 CCA is synthesized, characterized, and exposed to Pisces-RF high-flux D plasma. • Plasma material interaction performance is evaluated in terms of D retention, erosion, and thermal diffusivity. • The results are compared to similar plasma exposure response by W.

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Publication Details

Journal
Nuclear Materials and Energy
Published
2025-05-05
DOI
https://doi.org/10.1016/j.nme.2025.101943
Citations
1
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.52

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article

A first study of the complex-concentrated-alloy W38Ta36Cr15V11 in Pisces-RF high-flux deuterium plasma

B. Schwendeman, George Tynan, A. Založnik, M.J. Baldwin et al.
1 citations
Nuclear Materials and Energy
Fusion materials and technologies
0.52
article

A first study of the complex-concentrated-alloy W38Ta36Cr15V11 in Pisces-RF high-flux deuterium plasma

B. Schwendeman, George Tynan, A. Založnik, M.J. Baldwin, Miquela Vigil, M.I. Patino, D. Nishijima, S. Faulhaber, Kenneth S. Vecchio, M.J. Simmonds
article en
1 citations

Abstract

Bulk targets of W 38 Ta 36 Cr 15 V 11 complex concentrated alloy (CCA) were produced by spark plasma sintering at the Vecchio materials research lab at the University of California–San Diego. Targets fabricated were reasonably dense, BCC phase, compositionally close in match to that of El-Atwani et al. (2019), and homogeneous, as measured by electron microscopy, energy dispersive x-ray microanalysis (EDX), EDX mapping, and x-ray diffraction. The targets were exposed to deuterium plasma of associated 100 eV ion fluences of 2 × 1 0 26 m −2 at 523 K, 773 K and 1023 K in the Pisces-RF high-flux linear plasma device. Plasma exposure is found to produce surface compositional enrichment in W and Ta, as determined by Auger electron spectroscopy and EDX, that is caused by a depletion of surface Cr and V, the former being observed with optical emission spectroscopy in the target plasma. Accompanying the compositional change, transient grating spectroscopy analysis, taken pre- and post-plasma exposure on the 1023 K exposed target, revealed ∼ 30 % reduction in surface thermal diffusivity from 9 . 4 × 1 0 − 6 m 2 s −1 to 6 . 7 × 1 0 − 6 m 2 s −1 . Lastly, D retention in the CCA targets was found to be characterized by a singular thermal release peak at ∼ 900 K, and retention varied from 2 × 1 0 23 m −2 to 3 × 1 0 20 m −2 for exposure in the temperature range 523–1023 K, as measured by thermal desorption spectrometry. This level of D retention is found to be high relative to pure tungsten. • Bulk W 38 Ta 36 Cr 15 V 11 CCA is synthesized, characterized, and exposed to Pisces-RF high-flux D plasma. • Plasma material interaction performance is evaluated in terms of D retention, erosion, and thermal diffusivity. • The results are compared to similar plasma exposure response by W.

Nuclear Materials and EnergyVol. 43
University of Wisconsin–Madison (US), University of California San Diego (US)
U.S. Department of Energy, Fusion Energy Sciences
Openalex Percentile: Top 39%
Fusion materials and technologies
0.52
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