journal article·2025-09Open access

The effect of initial microstructure on the irradiation hardening of the W fiber in Wf/W–Y2O3 composites

C. Chen, J.H. Chen, Y. Chen, J. Wang, Y.F. Zhang, S. Wang, H.Y. Chen, Y.R. Mao, L.M. Luo

Abstract

Tungsten fiber-reinforced tungsten (W f /W) composites are promising candidates for plasma facing materials for fusion devices. The hardening behaviors of unrecrystallized W fiber (NRX-W fiber) and fully recrystallized W fiber (RX-W fiber) in the W f /W-Y 2 O 3 composites after helium ion irradiation (180 keV) were studied. The results reveal that the lattice distortion and microscopic residual stress in both the NRX-W fiber and the RX-W fiber increase after irradiation. The observation of dislocation loops with lower number density and smaller size in the NRX-W fiber compared to the RX-W fiber indicates that the NRX-W fiber has an enhanced capacity for capturing irradiation-induced defects. This enhanced capacity arises from its characteristics, including an initially larger proportion of high-angle grain boundaries (HAGBs), a higher density of subgrain boundaries, and geometrically necessary dislocations (GNDs). Nanoindentation tests show that the irradiation hardening increments for NRX-W fiber and RX-W fiber are 4.38 ± 0.10 GPa and 5.08 ± 0.17 GPa, respectively. Notably, the irradiation hardening rate of NRX-W fiber is 52.96%, which is significantly lower than that of RX-W fiber (84.95%), indicating superior resistance to helium ion irradiation hardening in the NRX-W fiber. Consistent with these experimental findings, theoretical calculations using the dispersed barrier hardening (DBH) model yield irradiation hardening increments of 3.68 GPa and 4.99 GPa for NRX-W fiber and RX-W fiber, respectively. Additionally, dislocation loops exhibit a uniform distribution within the equivalent crystallographic direction, with their contributions being dominant in the irradiation hardening of both fiber types.
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Research context

OpenAlex topics: Metal and Thin Film Mechanics · Diamond and Carbon-based Materials Research · Advanced materials and composites

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References (37)

Show source-provided references
1. Development of tungsten fibre-reinforced tungsten composites towards their use in DEMO—potassium doped tungsten wire10.1088/0031-8949/T167/1/014006 ↗
2. Microstructure and mechanical properties of tungsten composite reinforced by fibre network10.1007/s11706-017-0378-8 ↗
3. Structural and optical properties of yttrium trioxide thin films prepared by RF magnetron sputtering10.1016/j.vacuum.2011.04.016 ↗
4. Phase transitions and thermodynamic properties of yttria, Y2O3: inelastic neutron scattering shell model and first-principles calculations10.1103/PhysRevB.84.094301 ↗
5. The influence of annealing on yttrium oxide thin film deposited by reactive magnetron sputtering: process and microstructure10.1016/j.nme.2016.12.031 ↗
6. Forrest · 2009 · 552
7. Influence of the interface strength on the mechanical properties of discontinuous tungsten fiber-reinforced tungsten composites produced by field assisted sintering technology10.1016/j.compositesa.2018.01.022 ↗
8. Materials challenges for ITER – current status and future activities10.1016/j.jnucmat.2007.03.017 ↗
9. Tensile properties of neutron irradiated TZM and tungsten10.1016/0022-3115(76)90112-4 ↗
10. The effect of 800 MeV proton irradiation on the mechanical properties of tungsten at room temperature and at 475 °C10.1016/j.jnucmat.2004.12.018 ↗
11. Microstructure and failure mechanism of Y2O3 coating on the W fiber in Wf/W composites during field assisted sintering10.1016/j.jmrt.2024.05.237 ↗
12. Estimation of the fracture toughness of tungsten fibre-reinforced tungsten composites10.1016/j.engfracmech.2020.107011 ↗
13. Interface and mechanical properties of the single-layer long fiber reinforced Wf/W-Y2O3 composites fabricated via field assisted sintering technology10.1016/j.msea.2022.144098 ↗
14. Electrophoretic deposition prepared yttria as interface of tungsten fiber reinforced tungsten composites
15. Interfacial microstructure and mechanical property of the discontinuous short tungsten fiber-reinforced tungsten matrix composites10.1016/j.matchar.2024.114214 ↗
16. The effect of Y2O3 particles on the microstructure and mechanical properties of tungsten fiber-reinforced tungsten composites10.1016/j.msea.2024.147449 ↗
17. Irradiation hardening of pure tungsten exposed to neutron irradiation10.1016/j.jnucmat.2016.08.024 ↗
18. A new Multiple Beams–Material Interaction Research Facility for radiation damage studies in fusion materials10.1016/S0920-3796(00)00181-2 ↗
19. JANNUS: experimental validation at the scale of atomic modelling
20. Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: microstructure, effect of dpa rate, temperature, and grain size10.1016/j.actamat.2018.02.035 ↗
21. Irradiation hardening in pure tungsten before and after recrystallization10.1016/j.fusengdes.2015.06.192 ↗
22. Isotropic thermal conductivity in rolled large-sized W-Y2O3 bulk material prepared by powder metallurgy route and rolling deformation technology10.1016/j.fusengdes.2018.10.009 ↗
23. Ziegler · 1985
24. A note on integral equations of the Kinchin-Pease type10.1080/00337576908234453 ↗
25. 1996
26. Measurement of hardness and elastic modulus by instrumented indentation: advances in understanding and refinements to methodology10.1557/jmr.2004.19.1.3 ↗
27. Effects of fusion relevant transient energetic radiation, plasma and thermal load on PLANSEE double forged tungsten samples in a low energy plasma focus device10.1016/j.apsusc.2018.03.039 ↗
28. Structural changes induced by heavy ion irradiation in titanium silicon carbide10.1016/j.jnucmat.2010.12.235 ↗
29. In-situ TEM observation and MD simulation of the reaction and transformation of <100> loops in tungsten during H2+ & He+ dual-beam irradiation10.1016/j.scriptamat.2021.114154 ↗
30. Indentation size effects in crystalline materials: a law for strain gradient plasticity10.1016/S0022-5096(97)00086-0 ↗
31. Anisotropy in the hardness of single crystal tungsten before and after neutron irradiation10.1016/j.jnucmat.2020.152759 ↗
32. Direct imaging of the disconnection climb mediated point defects absorption by a grain boundary10.1038/s41467-022-29162-2 ↗
33. Integrated experimental and computational study on the effect of hydrogen in mechanical responses of pure tungsten10.1016/j.actamat.2024.120341 ↗
34. In-situ TEM investigation of 30 keV He+ irradiated tungsten: effects of temperature, fluence, and sample thickness on dislocation loop evolution10.1016/j.actamat.2020.116618 ↗
35. Meyers · 2009
36. Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials10.1016/j.jnucmat.2018.03.021 ↗
37. Dislocation depinning from ordered nanophases in a model fcc crystal: from cutting mechanism to Orowan looping10.1016/j.actamat.2010.06.018 ↗