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. 2022 Oct 19;15(20):7296.
doi: 10.3390/ma15207296.

Irradiation Damage Independent Deuterium Retention in WMoTaNbV

Anna Liski  1 , Tomi Vuoriheimo  1 , Pasi Jalkanen  1 , Kenichiro Mizohata  1 , Eryang Lu  1 , Jari Likonen  2 , Jouni Heino  1 , Kalle Heinola  3 , Yevhen Zayachuk  4 , Anna Widdowson  4 , Ko-Kai Tseng  5 , Che-Wei Tsai  5   6 , Jien-Wei Yeh  5   6 , Filip Tuomisto  1 , Tommy Ahlgren  1
Affiliations

Irradiation Damage Independent Deuterium Retention in WMoTaNbV

Anna Liski et al. Materials (Basel). .

Abstract

High entropy alloys are a promising new class of metal alloys with outstanding radiation resistance and thermal stability. The interaction with hydrogen might, however, have desired (H storage) or undesired effects, such as hydrogen-induced embrittlement or tritium retention in the fusion reactor wall. High entropy alloy WMoTaNbV and bulk W samples were used to study the quantity of irradiation-induced trapping sites and properties of D retention by employing thermal desorption spectrometry, secondary ion mass spectrometry, and elastic recoil detection analysis. The D implantation was not found to create additional hydrogen traps in WMoTaNbV as it does in W, while 90 at% of implanted D is retained in WMoTaNbV, in contrast to 35 at% in W. Implantation created damage predicted by SRIM is 0.24 dpa in WMoTaNbV, calculated with a density of 6.044×1022 atoms/cm3. The depth of the maximum damage was 90 nm. An effective trapping energy for D in WMoTaNbV was found to be about 1.7 eV, and the D emission temperature was close to 700 °C.

Keywords: deuterium; elastic recoil; fusion; high entropy alloy; hydrogen; metals; secondary ion; thermal desorption.

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Conflict of interest statement

The authors declare no conflict of interest. The funders had no role in the design of the study; in the collection, analyses, or interpretation of data; in the writing of the manuscript; or in the decision to publish the results.

Figures

Figure 1
Figure 1
Concentration profiles of D in WMoTaNbV and W. The profiles were measured by SIMS and calibrated with the total D amounts from ERDA. The SRIM profiles show approximately how the profiles would look if there were no D diffusion. Displacement threshold energies used were W = 90 eV, Mo = 65 eV, Nb = 78 eV, Ta = 90 eV and V = 57 eV [11]. The units of SRIM-calculated damage profiles are arbitrary.
Figure 2
Figure 2
Thermal release D signals from WMoTaNbV and W with 10 °C/min heating rate.
Figure 3
Figure 3
The three thermal desorption measurements from the WMoTaNbV alloy with heating rates of 5, 10, and 20 °C per minute. The D release peak positions correspond to the trapping energy of 1.66 ± 0.78 eV.
Figure 4
Figure 4
Hydrogen release signals from WMoTaNbV and W during the TDS measurements. The second measurement was taken after the samples had spent several weeks in the NTP conditions. Both materials reabsorb hydrogen from the atmosphere, WMoTaNbV significantly more than W.
See this image and copyright information in PMC

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