Radiation-induced segregation on defect clusters in single-phase concentrated solid-solution alloys
Source abstract
Abstract
A group of single-phase concentrated solid-solution alloys (SP-CSAs), including NiFe, NiCoFe, NiCoFeCr, as well as a high entropy alloy NiCoFeCrMn, was irradiated with 3 MeV Ni2+ ions at 773 K to a fluence of 5 1016 ions/cm2 for the study of radiation response with increasing compositional complexity. Advanced transmission electron microscopy (TEM) with electron energy loss spectroscopy (EELS) was used to characterize the dislocation loop distribution and radiation-induced segregation (RIS) on defect clusters in the SP-CSAs. The results show that a higher fraction of faulted loops exists in the more compositionally complex alloys, which indicate that increasing compositional complexity can extend the incubation period and delay loop growth. The RIS behaviors of each element in the SP-CSAs were observed as follows: Ni and Co tend to enrich, but Cr, Fe and Mn prefer to deplete near the defect clusters. RIS level can be significantly suppressed by increasing compositional complexity due to the sluggish atom diffusion. According to molecular static (MS) simulations, disk like segregations may form near the faulted dislocation loops in the SP-CSAs. Segregated elements tend to distribute around the whole faulted loop as a disk rather than only around the edge of the loop.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: High Entropy Alloys Studies · High-Temperature Coating Behaviors · High Temperature Alloys and Creep
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (25)
Show source-provided references
1. A fracture-resistant high-entropy alloy for cryogenic applications10.1126/science.1254581 ↗
2. Deviation from high-entropy configurations in the atomic distributions of a multi-principal-element alloy10.1038/ncomms6964 ↗
3. Metastable high-entropy dual-phase alloys overcome the strength–ductility trade-off
4. Relative effects of enthalpy and entropy on the phase stability of equiatomic high-entropy alloys10.1016/j.actamat.2013.01.042 ↗
5. Influence of chemical disorder on energy dissipation and defect evolution in concentrated solid solution alloys10.1038/ncomms9736 ↗
6. Direct observation of defect range and evolution in ion-irradiated single crystalline Ni and Ni binary alloys
7. Effects of compositional complexity on the ion-irradiation induced swelling and hardening in Ni-containing equiatomic alloys10.1016/j.scriptamat.2016.03.030 ↗
8. Mechanism of radiation damage reduction in equiatomic multicomponent single phase alloys10.1103/PhysRevLett.116.135504 ↗
9. Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation10.1016/j.actamat.2016.05.007 ↗
10. Point defect evolution in Ni, NiFe and NiCr alloys from atomistic simulations and irradiation experiments10.1016/j.actamat.2015.08.007 ↗
11. Ion irradiation induced defect evolution in Ni and Ni-based FCC equiatomic binary alloys10.1016/j.jnucmat.2015.09.009 ↗
12. Enhancing radiation tolerance by controlling defect mobility and migration pathways in multicomponent single-phase alloys10.1038/ncomms13564 ↗
13. Anisotropic radiation-induced segregation in 316L austenitic stainless steel with grain boundary character10.1016/j.actamat.2013.11.060 ↗
14. Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels10.1016/j.actamat.2010.10.055 ↗
15. Swelling and radiation-induced segregation in austentic alloys10.1016/j.jnucmat.2005.02.008 ↗
16. Irradiation-induced grain boundary chromium microchemistry in high alloy ferritic steels10.1016/j.scriptamat.2008.01.004 ↗
17. Cookson · 1995
18. Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates10.1016/j.jnucmat.2015.10.041 ↗
19. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
20. Interatomic potential for studying ageing under irradiation in stainless steels: the FeNiCr model alloy10.1088/0965-0393/21/8/085004 ↗
21. Interatomic potential to study plasticity in stainless steels: the FeNiCr model alloy10.1088/0965-0393/19/8/085008 ↗
22. Jenkins · 2000
23. Television pickup tubes and the problem of vision
24. Features of structure-phase transformations and segregation processes under irradiation of austenitic and ferritic-martensitic steels10.1016/0022-3115(94)90031-0 ↗
25. Assessment of radiation-induced segregation mechanisms in austenitic and ferritic-martensitic alloys10.1016/j.jnucmat.2011.01.031 ↗