journal article·2026-03

First phase diagram of dislocation loops achieved through an innovative analytical framework

Junjie Cao, Liping Guo, Yiheng Chen, Congxiao Liu, Rui Yan, Hongtai Luo

Acta Materialia· Volume 306
Publisher page

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

Source: Not provided · Quality: missing

Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Hydrogen embrittlement and corrosion behaviors in metals

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (58)

Show source-provided references
1. Hirth · 1982
2. In-situ observation of an irradiation creep deformation mechanism in zirconium alloys10.1016/j.scriptamat.2018.05.030 ↗
3. Irradiation creep due to dislocation climb and glide10.1016/0022-3115(77)90177-5 ↗
4. In-situ atomic-scale observation of irradiation-induced void formation10.1038/ncomms3288 ↗
5. Designing radiation resistance in materials for fusion energy10.1146/annurev-matsci-070813-113627 ↗
6. Materials challenges in nuclear energy10.1016/j.actamat.2012.11.004 ↗
7. Challenges in developing materials for fusion technology-past, present and future10.13182/FST13-631 ↗
8. Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket10.1016/j.jnucmat.2011.05.023 ↗
9. Dislocation loops in irradiated iron10.1038/200254a0 ↗
10. Dislocation loops in irradiated iron10.1080/14786436508223952 ↗
11. In-situ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing10.1016/j.mtla.2020.100778 ↗
12. An electron microscope study of neutron irradiation damage in alpha-iron10.1080/14786436508218869 ↗
13. Stability and mobility of self-interstitials and small interstitial clusters in α-iron: Ab initio and empirical potential calculations10.1016/j.nimb.2004.10.028 ↗
14. Mechanism of formation and growth of <100>interstitial loops in ferritic materials10.1103/PhysRevLett.88.255507 ↗
15. Solving the puzzle of 100 interstitial loop formation in bcc iron10.1103/PhysRevLett.110.265503 ↗
16. Cascade debris overlap mechanism of 100 dislocation loop formation in Fe and FeCr10.1209/0295-5075/119/56003 ↗
17. Shockwave generates < 100 >dislocation loops in bcc iron10.1038/s41467-018-07102-3 ↗
18. Formation of prismatic loops from C15 Laves phase interstitial clusters in body-centered cubic iron10.1016/j.scriptamat.2014.10.033 ↗
19. The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures10.1080/14786430903430981 ↗
20. Effect of the α-γ Phase transition on the stability of dislocation loops in bcc iron10.1103/PhysRevLett.100.135503 ↗
21. Microstructure of irradiated ferritic/martensitic steels in relation to mechanical properties10.1016/S0022-3115(02)01034-6 ↗
22. Changes in the burgers vector of perfect dislocation loops without contact with the external dislocations10.1103/PhysRevLett.96.125506 ↗
23. Dynamic observations of heavy-ion damage in Fe and Fe-Cr alloys10.1016/j.jnucmat.2009.02.003 ↗
24. Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys10.1016/j.actamat.2017.07.011 ↗
25. Irradiation damage in 304 and 316 stainless steels : experimental investigation and modeling . Part I : Evolution of the microstructure10.1016/j.jnucmat.2003.11.007 ↗
26. Microstructure modeling of nuclear structural materials: Recent progress and future directions10.1016/j.commatsci.2023.112503 ↗
27. Predicting the Irradiation Swelling of Austenitic and Ferritic/Martensitic Steels, Based on the Coupled Model of Machine Learning and Rate Theory
28. Relative population of 1/2<111>and <100>interstitial loops in alpha-Fe under irradiation: effects of C15 cluster stability and loop one-dimensional movement10.1016/j.actamat.2022.117983 ↗
29. Reactions between a 1/2 〈111〉 screw dislocation and 〈100〉 interstitial dislocation loops in alpha-iron modelled at atomic scale10.1080/14786430903019073 ↗
30. A new mechanism of loop formation and transformation in bcc iron without dislocation reaction10.1016/j.jnucmat.2013.05.074 ↗
31. Collision cascades overlapping with self-intersititial defect clusters in Fe and W
32. Was · 2017
33. Size-distribution and annealing behavior of end-of-range dislocation loops in silicon-implanted silicon10.1063/1.364099 ↗
34. An overview of the welding technologies of CLAM steels for fusion application10.1016/j.fusengdes.2012.06.009 ↗
35. Status and improvement of CLAM for nuclear application10.1088/1741-4326/aa763f ↗
36. Establishment of multi-beam irradiation facility at Wuhan University10.1016/j.nima.2022.167202 ↗
37. J. Ziegler, SRIM & TRIM, (2013). http://www.srim.org/.
38. ASTM E521, Standard practice for neutron radiation damage simulation by charged-particle, 2009. https://doi.org/10.1520/E0521-96R09E02.Copyright.
39. TEM characterization of dislocation loops in irradiated bcc Fe-based steels10.1016/j.jnucmat.2012.12.002 ↗
40. Indentation size effects in crystalline materials: a law for strain gradient plasticity10.1016/S0022-5096(97)00086-0 ↗
41. Characterization of radiation induced defects in EUROFER 97 after neutron irradiation10.1016/j.jnucmat.2010.12.261 ↗
42. Effect of irradiation temperature on radiation hardening of CLF-1 steel10.1016/j.fusengdes.2023.113488 ↗
43. Temperature effects on the radiation damage morphology in nanocrystalline iron10.1016/j.scriptamat.2022.114607 ↗
44. Dislocation loop structure, energy and mobility of self-interstitial atom clusters in bcc iron10.1016/S0022-3115(99)00166-X ↗
45. Wolfer · 2012
46. Dislocation pile-ups in Fe at high temperature
47. Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature10.1016/j.jnucmat.2019.151845 ↗
48. Effect of self-interstitial diffusion anisotropy in electron-irradiated zirconium: A cluster dynamics modeling10.1016/j.jnucmat.2005.06.024 ↗
49. Synergistic effect of displacement damage and helium atoms on radiation hardening in F82H at TIARA facility10.1016/j.jnucmat.2004.04.290 ↗
50. Quantitative characterization of microstructural defects in up to 32 dpa neutron irradiated EUROFER9710.1016/j.jnucmat.2012.03.027 ↗
51. Z. Yao, M.L. Jenkins, M.A. Kirk, M.L. Jenkins, Heavy-ion irradiations of Fe and Fe – Cr model alloys part 1 : damage evolution in thin-foils at lower doses, 6435 (2008). https://doi.org/10.1080/14786430802380469.10.1080/14786430802380469 ↗
52. Microstructural examination of neutron-irradiated simple ferritic alloys10.1016/0022-3115(82)90523-2 ↗
53. The evolution of mechanical property change in irradiated austenitic stainless steels10.1016/0022-3115(93)90129-M ↗
54. On the relationship between uniaxial yield strength and resolved shear stress in polycrystalline materials10.1016/S0022-3115(00)00378-0 ↗
55. Radiation tolerance of neutron-irradiated model Fe-Cr-Al alloys10.1016/j.jnucmat.2015.06.023 ↗
56. On the swelling resistance of ferritic steel
57. Shape of prismatic dislocation loops in anisotropic α-Fe10.1080/09500830903199012 ↗
58. Advanced machine learning analysis of radiation hardening in reduced-activation ferritic/martensitic steels10.1016/j.commatsci.2025.113773 ↗