journal article·2025-11Open access

Effect of irradiation temperature on the microstructure and hardness of W-0.3Cr alloy after irradiation with 6.4 MeV Fe ions

Jing Wang, Jingxian Sun, Yingying Jia, Yifan Zhang, Yuji Hatano, Diancheng Geng, Katsuya Suzuki, Chang Chen, Laima Luo, Kiyohiro Yabuuchi, Ryuta Kasada

Materials & Design· Volume 259

Abstract

• The diffraction peaks shift to lower 2θ at all temperatures (773–1273 K), confirming irradiation-induced lattice swelling due to defects. • An increase in irradiation temperature resulted in the growth of large dislocation loops and a slight reduction in the number density of dislocation loops. • The precipitation of Cr was absent in the sample after irradiation at 773 K but was clearly observed in the samples irradiated at 1073 and 1273 K. • Irradiation hardening was observed at all temperatures. The hardness change, estimated with the dispersion barrier hardening model considering dislocation loops and Cr precipitates, was much higher than the nanoindentation results due to Cr atom depletion from precipitation. The W-0.3 at.% Cr alloy samples were irradiated with 6.4 MeV Fe ions at 773, 1073 and 1273 K, and the damage peak was 0.26 dpa. The evolution of the microstructure, defects, and hardness was investigated using grazing-incidence X-ray diffraction (GIXRD), transmission electron microscopy (TEM) and nanoindentation tests. The GIXRD results showed that diffraction peaks shifted towards lower 2θ values, indicating that lattice swelling was caused by irradiation-induced defects after irradiation at elevated temperatures. According to the TEM observations, the size of the dislocation loops remained nearly constant, while their number density decreased with an increase in irradiation temperature. The precipitation of Cr was not observed in the W-0.3Cr alloy after irradiation at 773 K. In contrast, it was significant in the samples irradiated at temperatures of 1073 and 1273 K, showing increases in both the size and number density of the precipitates. Irradiation hardening was observed in all samples, primarily attributed to the presence of dislocation loops. The hardness change was estimated with the dispersion barrier hardening model by taking into account the contributions of dislocation loops and Cr precipitates. The values evaluated with the model were significantly larger than those obtained with the nanoindentation tests. This difference was ascribed to the depletion of solute Cr atoms from the W matrix by precipitation.
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Research context

OpenAlex topics: Fusion materials and technologies · Advanced materials and composites · Metal and Thin Film Mechanics

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References (55)

Show source-provided references
1. How does radiation damage materials?10.1126/science.1150394 ↗
2. Coherent displacement of atoms during ion irradiation10.1038/17983 ↗
3. Controlling radiation damage10.1126/science.1188088 ↗
4. Materials research for fusion10.1038/nphys3735 ↗
5. Plasma material interactions in current tokamaks and their implications for next-step fusion reactors10.1088/0029-5515/41/12/218 ↗
6. Behavior of tungsten under irradiation and plasma interaction10.1016/j.jnucmat.2019.03.035 ↗
7. Deuterium trapping at defects created with neutron and ion irradiations in tungsten10.1088/0029-5515/53/7/073006 ↗
8. Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys10.1016/j.jnucmat.2019.151910 ↗
9. Neutron irradiation-induced recrystallization simulation for tungsten in nuclear fusion device10.1016/j.ijrmhm.2024.106635 ↗
10. The superior thermal stability and irradiation resistance capacities of tungsten composites synthesized by simple second-phase particle component modulation10.1016/j.jnucmat.2022.153522 ↗
11. D2 retention behavior and microstructural evolution of W-2wt.%Y2O3 alloy during He-ion irradiation at high temperatures10.1016/j.jnucmat.2020.152273 ↗
12. D2 retention and microstructural evolution during He irradiation in candidate plasma facing material W-La2O3 alloy10.1016/j.jnucmat.2017.09.033 ↗
13. 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 ↗
14. Neutron irradiation-enhanced grain growth in tungsten and tungsten alloys10.1016/j.jallcom.2021.163419 ↗
15. Interplay of composition, structure, and electron density of states in W-Os cathode materials and relationship with thermionic emission10.1116/1.4972857 ↗
16. Towards understanding the trapping, migration and clustering of He atoms in W-Ta alloy10.1016/j.jnucmat.2021.153095 ↗
17. Structural stability, electronic structures, mechanical properties and debye temperature of W-Re alloys: a first-principles study10.1016/j.fusengdes.2020.112081 ↗
18. Effects of Re content and fabrication process on microstructural changes and hardening in neutron irradiated tungsten10.2320/matertrans.MBW201110 ↗
19. Neutron irradiation effects on the microstructural development of tungsten and tungsten alloys10.1016/j.jnucmat.2015.10.047 ↗
20. Deuterium retention in W and binary W alloys irradiated with high energy Fe ions10.1016/j.jnucmat.2020.152749 ↗
21. Irradiation effects on binary tungsten alloys at elevated temperatures: vacancy cluster formation, precipitation of alloying elements and irradiation hardening10.1016/j.matdes.2023.111899 ↗
22. R.K. Williams, F.W. Wiffen, J. Bentley, et al., Irradiation induced precipitation in tungsten based, W-Re alloys, Metall Mater Trans. A VOLUME 14A, APRIL 1983—655. doi: 10.1007/BF02643781.10.1007/BF02643781 ↗
23. Neutron energy spectrum influence on irradiation hardening and microstructural development of tungsten10.1016/j.jnucmat.2016.06.051 ↗
24. Ion-irradiation-induced clustering in W-Re and W-Re-Os alloys: a comparative study using atom probe tomography and nanoindentation measurements10.1016/j.actamat.2014.12.049 ↗
25. Atomistic investigation on radiation-induced segregation in W-Re alloy under cumulative flux irradiation: a hybrid simulation with MD and VC-SGC-MC10.1016/j.jnucmat.2023.154520 ↗
26. Suppression of vacancy formation and hydrogen isotope retention in irradiated tungsten by addition of chromium10.1016/j.jnucmat.2021.153449 ↗
27. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
28. Deuterium retention in MeV self-implanted tungsten: Influence of damaging dose rate10.1016/j.nme.2017.02.003 ↗
29. J. F. Ziegler, SRIM - The stopping and range of ions in matter, ver. SRIM-2008.4. http://srim.org.
30. Standard Practice for Neutron Radiation Damage Simulation by Charged Particle Irradiation, ASTM International, West Conshohocken, PA, 2009.
31. The displacement of atoms in solids by radiation10.1088/0034-4885/18/1/301 ↗
32. Practical method to determine the effective zero-point of indentation depth for continuous stiffness measurement nanoindentation test with Berkovich tip10.1038/s41598-022-10490-8 ↗
33. An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments10.1557/JMR.1992.1564 ↗
34. The indentation size effect: a critical examination of experimental observations and mechanistic interpretations10.1146/annurev-matsci-070909-104456 ↗
35. Radiation damage evolution in pure W and W-Cr-Hf alloy caused by 5 MeV Au ions in a broad range of dpa
36. He2+ irradiation induced microstructure evolution in sub-surface layer of the coarse-grained tungsten accessed by synchrotron GIXRD and GISAXS10.1016/j.apsusc.2022.153461 ↗
37. Heavy ion irradiation induced defects in Zircaloy-410.1088/1402-4896/abe3bf ↗
38. Understanding and modeling plasticity error during nanoindentation with continuous stiffness measurement
39. Size dependence of micro-scale mechanical properties on heavy-ion irradiated tempered-martensitic steel evaluated through nanoindentation and micropillar compression tests10.1016/j.jnucmat.2024.155013 ↗
40. Neutron irradiation and defect recovery of tungsten10.1016/0022-3115(70)90193-5 ↗
41. The annealing of radiation damage in tungsten investigated by field-ion microscopy
42. High-temperature damage evolution in 10 keV He+ irradiated W and W-5Re10.1016/j.matchar.2018.08.026 ↗
43. In-situ TEM studies of 150 keV W+ ion irradiated W and W-alloys: damage production and microstructural evolution10.1016/j.actamat.2016.03.051 ↗
44. Designing radiation resistance in materials for fusion energy10.1146/annurev-matsci-070813-113627 ↗
45. Was · 2007
46. Neutron irradiation behavior of tungsten10.2320/matertrans.MG201208 ↗
47. Irradiation effects in high-entropy alloys and their applications10.1016/j.jallcom.2022.166768 ↗
48. The role of interstitial binding in radiation induced segregation in W-Re alloys10.1063/1.4956377 ↗
49. First-principles study of solvent-solute mixed dumbbells in body-centered-cubic tungsten crystals10.1016/j.jnucmat.2018.03.052 ↗
50. Suppression of radiation-induced point defects by rhenium and osmium interstitials in tungsten10.1038/srep36738 ↗
51. Irradiation hardening of pure tungsten exposed to neutron irradiation10.1016/j.jnucmat.2016.08.024 ↗
52. Nanohardness measurements of heavy ion irradiated coarse- and nanocrystalline-grained tungsten at room and high temperature10.1016/j.jnucmat.2018.06.023 ↗
53. Dislocation movement through random arrays of obstacles10.1139/p67-044 ↗
54. The relationship between hardness and yield stress in irradiated austenitic and ferritic steels10.1016/j.jnucmat.2004.09.024 ↗
55. Irradiation hardening of pure vanadium and vanadium alloys due to helium ion implantation and displacement damage10.1016/j.jnucmat.2020.152381 ↗