journal article·2021-02

On the irradiation tolerance of nano-grained Ni–Mo–Cr alloy: 1 MeV He+ irradiation experiment

Zhenbo Zhu, Hefei Huang, Ondrej Muránsky, Jizhao Liu, Zhiyong Zhu, Yi Huang

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Abstract

The irradiation damage behavior is surveyed in the nano-grained GH3535 condition irradiated by He ion to various dose. The evolution of defects and hardness changes are characterized by transmission electron microscopy and nanoindentation respectively to explore the irradiation tolerance of the nano-grained GH3535 condition, with the annealed GH3535 condition as reference material. The results show that though both the average size and number density of He bubbles increase with an increase in the irradiation dose, the smaller volume fraction is found in the nano-grained GH3535 condition compared with the annealed GH3535 condition under the same irradiation condition. This indicates that the nano-grained GH3535 condition possess better irradiation swelling resistance than the annealed GH3535 condition. However, the increase in the hardness of the nano-grained GH3535 condition is more significant than in the annealed GH3535 condition under the same irradiation dose. This suggests stronger irradiation-induced hardening of the nano-grained alloy comparing to coarse-grained alloy, due to the impeding effect caused by grain boundaries decorated with He bubbles. This study provides insight into the design of irradiation-tolerant nickel-based alloys for nuclear industry applications.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Advanced materials and composites

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

References (45)

Show source-provided references
1. The molten salt reactor (MSR) in generation IV: overview and perspectives10.1016/j.pnucene.2014.02.014 ↗
2. Molten salt reactors: a new beginning for an old idea10.1016/j.nucengdes.2009.12.033 ↗
3. Xenon ion irradiation induced hardening in inconel 617 containing experiment and numerical calculation10.1016/j.jnucmat.2019.07.032 ↗
4. Molten salts for safe, low waste and proliferation resistant treatment of radwaste in accelerator driven and critical systems
5. Preliminary fluoride salt-cooled high temperature reactor (FHR) materials and components white paper
6. Ultrastrong steel with exceptional thermal stability and radiation tolerance10.1038/s41467-018-07712-x ↗
7. Formation mechanism and the role of nanoparticles in Fe-Cr ODS steels developed for radiation tolerance10.1103/PhysRevB.82.184103 ↗
8. Effect of grain boundary character on sink efficiency10.1016/j.actamat.2012.08.009 ↗
9. He ion irradiation response of a gradient T91 steel10.1016/j.actamat.2020.06.019 ↗
10. The role of grain size in He bubble formation: implications for swelling resistance10.1016/j.jnucmat.2016.12.003 ↗
11. Grain size threshold for enhanced irradiation resistance in nanocrystalline and ultrafine tungsten10.1080/21663831.2017.1292326 ↗
12. Examining the influence of grain size on radiation tolerance in the nanocrystalline regime10.1063/1.5016822 ↗
13. Irradiation damage of single crystal, coarse-grained, and nanograined copper under helium bombardment at 450 °C10.1557/jmr.2013.283 ↗
14. Helium transport, fate and management in nanostructured ferritic alloys: in situ helium implanter studies10.1016/j.jnucmat.2011.01.064 ↗
15. Calculated grain size-dependent vacancy supersaturation and its effect on void formation10.1080/14786437408222075 ↗
16. Radiation damage near grain boundaries10.1080/14786430310001600222 ↗
17. Nanocrystallization of steels by severe plastic deformation10.2320/matertrans.44.1900 ↗
18. Nanostructuring of metals by severe plastic deformation for advanced properties10.1038/nmat1180 ↗
19. Grain size effects on He bubbles distribution and evolution10.1016/j.jnucmat.2014.11.036 ↗
20. Radiation damage in helium ion irradiated nanocrystalline Fe10.1016/j.jnucmat.2011.10.052 ↗
21. Effect of grain size on mechanical property and corrosion resistance of the Ni-based alloy 69010.1016/j.jmst.2017.12.017 ↗
22. Microstructural evolution and hardening of GH3535 alloy under energetic Xe ion irradiation at room temperature and 650 °C10.1016/j.jnucmat.2017.12.006 ↗
23. helium irradiation induced ultra-high strength nanotwinned Cu with nanovoids10.1016/j.actamat.2019.07.003 ↗
24. SRIM—The stopping and range of ions in matter
25. Analysis of displacement damage and defect production under cascade damage conditions10.1016/0022-3115(93)90140-T ↗
26. Features of primary damage by high energy displacement cascades in concentrated Ni-based alloys10.1063/1.4942533 ↗
27. Irradiation resistance of a thermally stable nanocrystalline Fe-1 at.% Zr alloy10.1016/j.matlet.2018.12.018 ↗
28. Was · 2016
29. Mitigation of He embrittlement and swelling in nickel by dispersed SiC nanoparticles10.1016/j.matdes.2015.10.147 ↗
30. Defects evolution and hardening in the Hastelloy N alloy by subsequent Xe and He ions irradiation10.1016/j.jnucmat.2019.02.022 ↗
31. In situ TEM observation of the evolution of helium bubbles in Hastelloy N alloy during annealing10.1016/j.jnucmat.2020.152184 ↗
32. A promising new class of irradiation tolerant materials: Ti2ZrHfV0.5Mo0.2 high-entropy alloy10.1016/j.jmst.2018.09.034 ↗
33. helium-induced damage behavior in high temperature nickel-based alloys with different chemical composition10.1016/j.jnucmat.2020.152419 ↗
34. helium accumulation in metals during irradiation–where do we stand?10.1016/j.jnucmat.2003.09.001 ↗
35. Equation of state and melting properties of He4 from measurements to 20 kbar10.1103/PhysRevB.21.5137 ↗
36. Indentation size effects in crystalline materials: a law for strain gradient plasticity10.1016/S0022-5096(97)00086-0 ↗
37. A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques10.1016/j.fusengdes.2011.03.073 ↗
38. TEM, XRD and nanoindentation characterization of Xenon ion irradiation damage in austenitic stainless steels10.1016/j.jnucmat.2014.07.033 ↗
39. Evolution of the microstructure during annealing of ultrafine-grained Ni with different Mo contents10.1016/j.matchar.2017.05.034 ↗
40. Influence of Mo alloying on the thermal stability and hardness of ultrafine-grained Ni processed by high-pressure torsion10.1016/j.jmrt.2017.05.009 ↗
41. Exceptionally high strength and good ductility in an ultrafine-grained 316L steel processed by severe plastic deformation and subsequent annealing10.1016/j.matlet.2017.12.040 ↗
42. High temperature thermal stability of nanocrystalline 316L stainless steel processed by high-pressure torsion10.1016/j.msea.2016.11.066 ↗
43. Ion irradiation induced disappearance of dislocations in a nickel-based alloy10.1016/j.nimb.2016.04.030 ↗
44. Tensile deformation of fcc Ni as described by an EAM potential10.1080/14786430903299329 ↗
45. Atomistic studies of hydrogen effects on grain boundary structure and deformation response in FCC Ni10.1016/j.commatsci.2016.05.014 ↗