Microstructural evolution of ion-irradiated commercially pure titanium
Source abstract
Abstract
Radiation-induced dislocation loop evolution in ion-irradiated commercially pure (CP) Ti was investigated through both ex situ 4 MeV Ar beams and by in situ TEM irradiation with 1 MeV Kr ion beams at different temperatures. The dominant mechanism for dislocation loop growth was loop coalescence. Both - and c-component loops exhibited an increase in size and density with increased irradiation dose and temperature. C-component loops were observed only after reaching a threshold incubation dose (TID). In CP Ti, these loops initiated at lower doses compared to previous observations in Zr, and the TID decreased with increasing temperature.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Ion-surface interactions and analysis
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (40)
Show source-provided references
1. Use of titanium in fusion components10.1016/0022-3115(94)90168-6 ↗
2. Radiation Damage Studies on Titanium Alloys as High Intensity Proton Accelerator Beam Window Materials
3. Swift heavy ion irradiation damage in Ti–6Al–4V and Ti–6Al–4V–1B: Study of the microstructure and mechanical properties10.1016/j.nimb.2015.09.029 ↗
4. Thermal, mechanical and fluid flow aspects of the high power beam dump for FRIB10.1016/j.nimb.2016.02.068 ↗
5. Evolution of microstructure in hcp metals during irradiation10.1016/0022-3115(93)90085-D ↗
6. Effect of displacement dose and irradiation temperature on tensile and fracture toughness properties of titanium alloys10.1016/j.jnucmat.2007.03.042 ↗
7. NEUTRON DAMAGE IN a-TITANIUM10.1016/0022-3115(83)90196-4 ↗
8. Impact of irradiation on the tensile and fatigue properties of two titanium alloys10.1016/S0022-3115(01)00564-5 ↗
9. Temperature dependence of irradiation effects in pure titanium10.1080/14786430412331319992 ↗
10. Structure–mechanics relationships in proton irradiated pure titanium10.1016/S0022-3115(02)01190-X ↗
11. Evolution of defects in titanium grade 2 under Ti 2+ ion irradiation10.1111/jmi.12499 ↗
12. Evolution of defects in Ti6-4 under Ti2+ ion irradiation: Focus on radiation-induced precipitates10.1016/j.jnucmat.2018.09.027 ↗
13. Jouanny · 2017
14. Heavy ion irradiation of a Ti-6Al-4V alloy10.1016/0022-3115(78)90466-X ↗
15. A simple method for the analysis of dislocation loops by means of the inside-outside contrast on transmission electron micrographs10.1002/pssa.2210310223 ↗
16. Intrinsic point defects in hexagonal close-packed metals10.1016/0022-3115(88)90090-6 ↗
17. Damage structure in zirconium alloys neutron irradiated at 573 to 923 k10.1016/0022-3115(79)90157-0 ↗
18. Defect accumulation behaviour in hcp metals and alloys10.1016/S0022-3115(99)00172-5 ↗
19. Microstructure evolution in h.c.p. metals during irradiation10.1080/01418619108213917 ↗
20. Proton irradiation studies on pure Ti and Ti-6Al-4V10.1016/j.nimb.2016.09.010 ↗
21. In situ TEM observation of interactions between gliding dislocations and prismatic loops in Zr-ion irradiated zirconium alloys10.1016/j.pnucene.2011.10.005 ↗
22. TEM with in situ Ion Irradiation of Nuclear Materials: The IVEM-Tandem User Facility10.1017/S1431927615002986 ↗
23. Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling10.1080/14786435.2012.662601 ↗
24. In situ study of defect accumulation in zirconium under heavy ion irradiation10.1016/j.jnucmat.2012.09.014 ↗
25. Li · 2013
26. E04 Committee, Test Methods for Determining Average Grain Size, ASTM International, n.d. https://doi.org/10.1520/E0112-96R04.10.1520/E0112-96R04 ↗
27. SRIM – The stopping and range of ions in matter (2010)10.1016/j.nimb.2010.02.091 ↗
28. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
29. Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation, in: E521-Annu. Book ASTM Stand., American Society for Testing and Materials, Philadelphia, PA, n.d.
30. Characterisation of radiation-damage microstructures by TEM10.1016/0022-3115(94)90010-8 ↗
31. Fiji: an open-source platform for biological-image analysis10.1038/nmeth.2019 ↗
32. Y. Idrees, Microstructural evolution in Zr and Zr alloy Excel under ion irradiation., Library and Archives Canada = Bibliothèque et Archives Canada, 2014.
33. 〈c〉Component dislocations in annealed Zircaloy irradiated at about 570 K10.1016/0022-3115(86)90218-7 ↗
34. Dislocation loops in irradiated zirconium10.1080/14786436608244779 ↗
35. Impact of an applied stress on c-component loops under Zr ion irradiation in recrystallized Zircaloy-4 and M5®10.1016/j.jnucmat.2015.10.009 ↗
36. A review of microstructure evolution in zirconium alloys during irradiation10.1016/0022-3115(88)90093-1 ↗
37. Theory of irradiation deformation in non-cubic metals: Effects of anisotropic diffusion10.1016/0022-3115(88)90096-7 ↗
38. 4.01 - Radiation Effects in Zirconium Alloys
39. Effects of ion irradiation on microstructure and properties of zirconium alloys—A review10.1016/j.net.2014.12.015 ↗
40. Toward a better understanding of the hydrogen impact on the radiation induced growth of zirconium alloys10.1016/j.jnucmat.2013.05.045 ↗