Annealing effect on deuterium retention in W-Cr-Y alloy
Source abstract
Abstract
Deuterium (D) trapping in the W-11.4Cr-0.6Y alloy manufactured by field assisted sintering technology (FAST) and pre-annealed at temperatures of 1050, 1250, 1473 K was studied by in-situ thermal desorption spectroscopy (TDS). D incorporation in W-11.4Cr-0.6Y alloy was carried out by irradiation with deuterium ions (670 eV/ D + ) to a fluence of 5 × 10 19 D/m 2 . The change in Cr concentration in the bulk of the W-Cr-Y alloy was studied using energy dispersive spectroscopy (EDS). The elemental composition on the surface of alloy samples before and after annealing was investigated using low energy ion scattering spectroscopy (LEIS). The Cr concentration increases on the surface of alloy sample during annealing at 1000 and 1050 K due to intensive Cr segregation, while it decreases at temperatures of 1250 K and above by dominant Cr sublimation. Pre-annealing of W-Cr-Y alloy at 1050 K leads to a decrease in the D trapping in the alloy which is connected with an increase in the Cr concentration on the surface. At high annealing temperatures of 1250 K and above, the appearance of new phases and decomposition-induced grain refinement leads to new types of defects with high binding energy for D.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Advanced materials and composites
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (36)
Show source-provided references
1. Litnovsky · 2021 · 594
2. Issues and strategies for DEMO in-vessel component integration10.1016/j.fusengdes.2016.05.040 ↗
3. Evaluation and optimization of tritium breeding, shielding and nuclear heating performances of the helium cooled solid breeder blanket for CFETR10.1016/j.ijhydene.2017.07.215 ↗
4. Pintsuk · 2012 · 551
5. The European power plant conceptual study10.1016/j.fusengdes.2005.06.095 ↗
6. Development of yttrium-containing self-passivating tungsten alloys for future fusion power plants10.1016/j.nme.2016.07.011 ↗
7. Development of advanced high heat flux and plasma-facing materials10.1088/1741-4326/aa6f71 ↗
8. Materials for the plasma-facing components of fusion reactors10.1016/j.jnucmat.2004.04.005 ↗
9. Self passivating W-based alloys as plasma-facing material10.1016/j.jnucmat.2008.12.179 ↗
10. Tungsten–chromium–yttrium alloys as first wall armor material: yttrium concentration, oxygen content and transmutation elements10.1016/j.fusengdes.2020.111667 ↗
11. Advanced self-passivating alloys for an application under extreme conditions10.3390/met11081255 ↗
12. Deuterium retention in tungsten based materials for fusion applications10.1016/j.nme.2018.12.032 ↗
13. Analysis of trapping sites for deuterium in W–Cr–Y SMART alloy10.1016/j.vacuum.2022.110956 ↗
14. Deuterium retention in W-Cr-Y alloy: impact of the manufacturing method and helium presence10.1016/j.jnucmat.2023.154353 ↗
15. Temporally resolved LEIS measurements of Cr segregation after preferential sputtering of WCrY alloy10.1016/j.nimb.2020.06.005 ↗
16. Segregation and preferential sputtering of Cr in WCrY smart alloy
17. Characteristics of microstructure evolution during fast joining of the tungsten foil laminate10.3390/met11060886 ↗
18. The influence of powder characteristics on densification behavior and microstructure evolution of W-Cr-Zr alloy consolidated by field-assisted sintering technology10.1016/j.ijrmhm.2022.105939 ↗
19. CASINO V2.42—A Fast and Easy-to-use modeling tool for scanning electron microscopy and microanalysis users10.1002/sca.20000 ↗
20. Penetration and energy-loss theory of electrons in solid targets10.1088/0022-3727/5/1/308 ↗
21. Application of keV-energy proton scattering for thin film analysis10.1016/j.nimb.2018.10.043 ↗
22. Facility and the method for MEIS analysis of layers redeposited in plasma devices10.1088/1742-6596/748/1/012016 ↗
23. On the possibility of quantitative W-Cr-Y analysis by grazing ion-surface scattering spectroscopy
24. Calculations of nuclear stopping powers and ranges in the low-energy region10.1103/PhysRevB.15.2458 ↗
25. Bromley · Treatise Heavy-Ion Sci. · 1985 · 95
26. Deuterium trapping in the subsurface layer of tungsten pre-irradiated with helium ions10.1016/j.jnucmat.2021.152848 ↗
27. Babich · 1991
28. Deuterium retention in tungsten in dependence of the surface conditions10.1016/S0022-3115(02)01375-2 ↗
29. Effect of the presence of helium in tungsten on deuterium retention10.1016/j.jnucmat.2021.152873 ↗
30. Deuterium thermal desorption and re-emission from RAFM steels10.1088/1402-4896/aa878d ↗
31. Helium and deuterium retention in Eurofer97 under sequential irradiation at low fluxes10.1016/j.jnucmat.2022.153871 ↗
32. Influence of thin surface oxide films on hydrogen isotope release from ion-irradiated tungsten
33. Microstructure and phase stability of W-Cr alloy prepared by spark plasma sintering10.1016/j.fusengdes.2018.01.012 ↗
34. High temperature microstructural stability of self-passivating W-Cr-Y alloys for blanket first wall application10.1016/j.fusengdes.2019.02.136 ↗
35. Decreasing the W-Cr solid solution decomposition rate: theory, modelling and experimental verification10.1016/j.jnucmat.2023.154288 ↗
36. Ultrafine-grained W-Cr composite prepared by controlled W-Cr solid solution decomposition10.1016/j.matlet.2021.130728 ↗