Quantitative evaluation of resistance of plasma facing materials to helium plasma irradiation
Source abstract
Abstract
The damage to Plasma-Faced Materials (PFMs) under helium (He) plasma irradiation includes upward fuzz growth and inward He bubble erosion. While current research on PFMs mainly focuses on fuzz growth, the equally critical issue of inward erosion into materials by high-flux, low-energy He plasma irradiation is often ignored. To fill this gap, we propose He bubble erosion thickness ( L ) as a quantitative metric to characterize the degree of He bubble erosion in PFMs induced by He plasma, defined as the thickness difference between the pristine sample and the remaining undamaged region after irradiation. Experimental studies on tantalum (Ta) and tungsten (W) films reveal that L follows a square-root dependence on He fluence, closely linked to He diffusion and He bubble formation. Similar to the diffusion coefficient of fuzz ( D ), the diffusion coefficient of He bubble erosion ( D' ) is introduced as a new quantitative parameter for evaluating the He bubble erosion rate of PFMs. A parameter, η, is further introduced to distinguish the dominant damage mode. Notably, designed Ta/W multilayer exhibits significantly reduced D and similar D′ values compared to W, which is attributed to semi-coherent interfaces and the formation of a Ta–W alloy within the fuzz. This study provides not only valuable parameters for PFM evaluation but also a promising strategy for designing future PFMs.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Fusion materials and technologies · Laser-Plasma Interactions and Diagnostics · Vacuum and Plasma Arcs
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (42)
Show source-provided references
1. Magnetic-confinement fusion10.1038/nphys3745 ↗
2. Materials research for fusion10.1038/nphys3735 ↗
3. Gross and net erosion balance of plasma-facing materials in full-W tokamaks10.1088/1741-4326/ac22d2 ↗
4. Studies of erosion-deposition of plasma-facing materials due to plasma-wall interactions in EAST tokamak10.1016/j.jnucmat.2024.155195 ↗
5. Multiscale modelling of plasma–wall interactions in fusion reactor conditions10.1088/0022-3727/47/22/224018 ↗
6. Formation of nanostructured tungsten with arborescent shape due to helium plasma irradiation10.1585/pfr.1.051 ↗
7. The influence of impurities on the erosion of tungsten by low energy high flux deuterium plasma irradiation10.1016/j.jnucmat.2021.153168 ↗
8. Helium plasma-induced surface modifications of unirradiated and pre-ion irradiated tungsten at LHD divertor leg position
9. The dependence of tungsten fuzz layer thickness and porosity on tungsten deposition rate and helium ion fluence10.1088/1741-4326/ad0b1e ↗
10. Interfaces enhanced plasma irradiation resistance in CrMoTaWV/W multilayer films through blocking he diffusion10.1088/1741-4326/ad5aaf ↗
11. Enhanced resistance to helium irradiations through unusual interaction between high-entropy-alloy and helium10.1016/j.actamat.2023.118765 ↗
12. Nanochannel structures in W enhance radiation tolerance10.1016/j.actamat.2018.04.048 ↗
13. Molecular dynamics study on the origin of fuzz structure on tungsten surface10.1016/j.jnucmat.2021.152835 ↗
14. Tungsten surface evolution by helium bubble nucleation, growth and rupture10.1088/0029-5515/53/7/073015 ↗
15. Helium induced nanoscopic morphology on tungsten under fusion relevant plasma conditions10.1088/0029-5515/48/3/035001 ↗
16. Tungsten ‘fuzz’ growth re-examined: the dependence on ion fluence in non-erosive and erosive helium plasma10.1088/0029-5515/55/9/093033 ↗
17. A review of late-stage tungsten fuzz growth10.1007/s42864-021-00133-2 ↗
18. Surface modification of ZrC dispersion-strengthened W under low energy he plasma irradiation10.1088/1741-4326/ad2f4c ↗
19. Effect of Ta addition on the fuzz formation of additively manufactured W-based materials10.1088/1741-4326/ab8a69 ↗
20. A new type of plasma irradiation-resistant amorphous TiZrHfTaW refractory multi-component alloy10.1016/j.actamat.2025.120822 ↗
21. Impact of low energy helium irradiation on plasma facing metals10.1016/j.jnucmat.2004.10.162 ↗
22. Divertor erosion at ASDEX upgrade during helium plasma operations
23. ERO modelling of net and gross erosion of marker samples exposed to L-mode plasmas on ASDEX upgrade
24. Influence of surface morphology on erosion of plasma-facing components in H-mode plasmas of ASDEX upgrade
25. Temperature-dependent surface modification of Ta due to high-flux, low-energy he+ ion irradiation10.1016/j.jnucmat.2015.09.035 ↗
26. Cone array formation on Si surfaces by low-energy he plasma irradiation with magnetron sputtering pre-deposited Ta
27. First principle calculations of energy of agglomerated helium in the period 6 elements10.1016/j.nme.2018.07.003 ↗
28. The helium behavior and thermal stability of W/Ta bilayer nanocomposite investigated by neutron reflectometry10.1016/j.nimb.2021.06.023 ↗
29. Self-interstitial atom defects in bcc transition metals: group-Specific trends10.1103/PhysRevB.73.020101 ↗
30. Materials selection for nuclear applications in view of divacancy energies by comprehensive first-principles calculations10.1016/j.jnucmat.2020.152253 ↗
31. Helium accumulation in metals during irradiation – where do we stand?10.1016/j.jnucmat.2003.09.001 ↗
32. Energetics and formation kinetics of helium bubbles in metals10.1080/00337578308207371 ↗
33. Theoretical model of helium bubble growth and density in plasma-facing metals10.1038/s41598-020-58581-8 ↗
34. 2016 · vol. 12 · 37
35. The surface energy of metals. Sur
36. Radiation damage tolerant nanomaterials10.1016/j.mattod.2013.10.019 ↗
37. Experimental identification for physical mechanism of fiber-form nanostructure growth on metal surfaces with helium plasma irradiation10.1016/j.apsusc.2015.08.112 ↗
38. Comparison between helium plasma induced surface structures in group 5 (Nb, Ta) and group 6 elements (Mo, W)10.1063/1.4981128 ↗
39. Elastic moduli of BBC V-Ti, Mo-Nb and W-Ta alloys10.1088/0305-4608/18/6/017 ↗
40. Diffusion characteristics and atomic mobilities for bcc refractory Mo–Ta, Mo–W, and Mo–Nb alloys10.1016/j.calphad.2011.12.004 ↗
41. Acquisition and evaluation procedure to improve the accuracy ofSAED10.1002/jemt.24229 ↗
42. On deviations from vegard's law at increasing pressure in alloys10.1134/S0020168520090125 ↗