Distinct He-induced damage evolution in nickel-based alloys irradiated at elevated temperatures
Source abstract
Abstract
The nickel-based alloy Inconel 617 and Alloy 800H have been envisaged as the leading candidate for the higher-temperature Molten Salt Reactors (MSRs) due to their superior high-temperature properties. To evaluate their potential applications, both alloys were irradiated by He ion at 750 and 850 °C with corresponding He ion fluence. Same irradiation tests were performed on Hastelloy N alloy to study its microstructure evolution at elevated irradiation temperature, as well as being the reference alloy to reveal candidate alloys irradiation tolerance. Transmission electron microscopy (TEM) reveals the depth distribution of irradiation induced He bubbles and Frank loops. The TEM graphs and quantitative analysis shows that when irradiated at 850 °C, the formation of precipitated clusters lead to denser and boarder distribution of He bubbles in Inconel 617, while the bubble-loop complexes form and contribute to larger volume fraction of He bubbles in Hastelloy N alloy. The nanoindentation technique is used to measure their mechanical changes, and the results show that the Alloy 800H has the lowest degree of irradiation induced hardening when irradiated at 850 °C, whereas that of all alloys irradiated at 750 °C are basically similar. Further, the yield strength increment is calculated and deviations between experimental and calculated values are caused by the formation of precipitated clusters in Inconel 617 and the selection of smaller obstacle strength in Hastelloy N alloy. By comparison, the Alloy 800H demonstrates a greater potential to function as the structural material for higher-temperature MSRs due to smaller volume fraction and better resistance to irradiation induced hardening.
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 (49)
Show source-provided references
1. The molten salt reactor (MSR) in generation IV: overview and perspectives10.1016/j.pnucene.2014.02.014 ↗
2. Xenon ion irradiation induced hardening in Inconel 617 containing experiment and numerical calculation10.1016/j.jnucmat.2019.07.032 ↗
3. Material performance in molten salts10.1016/B978-0-08-056033-5.00098-7 ↗
4. Effect of Irradiation on Ni-Inconel/Incoloy heterostructures in multimetallic layered composites10.1016/j.jnucmat.2021.152778 ↗
5. The effect of grain size and dislocation density on the tensile properties of Ni-SiCNP composites during annealing10.1007/s11665-016-1938-2 ↗
6. Considerations of alloy 617 application in the gen IV nuclear reactor systems: part I—mechanical property challenges
7. Considerations of alloy 617 application in the gen IV nuclear reactor systems: part II—metallurgical property challenges
8. Status of alloy 800 H in considerations for the gen IV nuclear energy systems10.1115/1.4025093 ↗
9. Muralidharan · 2011
10. Challenges to the use of ion irradiation for emulating reactor irradiation10.1557/jmr.2015.73 ↗
11. Irradiated microstructure of alloy 800H10.1016/j.jnucmat.2006.02.009 ↗
12. Characterization of faulted dislocation loops and cavities in ion irradiated alloy 800H10.1016/j.jnucmat.2017.11.012 ↗
13. Characterization of in-situ ion irradiated Fe-21Cr-32Ni austenitic model alloy and alloy 800H at low doses10.1016/j.jnucmat.2021.153149 ↗
14. Microstructural evolution of the 21Cr32Ni model alloy under irradiation10.1016/j.jnucmat.2018.07.060 ↗
15. Nanoindentation study on the creep characteristics and hardness of ion-irradiated alloys10.3390/ma13143132 ↗
16. Ion irradiation enhanced helium atoms Re-solution and the related hardening in Hastelloy N alloy10.1007/s12540-019-00427-8 ↗
17. In-situ TEM observation of the evolution of helium bubbles in Hastelloy N alloy during annealing10.1016/j.jnucmat.2020.152184 ↗
18. Coalescence mechanism of helium bubble during tensile deformation revealed by in-situ small-angle X-ray scattering10.1016/j.scriptamat.2018.08.050 ↗
19. A special coarsening mechanism for intergranular helium bubbles upon heating: a combined experimental and numerical study10.1016/j.scriptamat.2018.01.006 ↗
20. SEM characterization of microstructural evolution in helium-implanted Hastelloy N alloy10.1016/j.nimb.2017.03.148 ↗
21. Molten salts for safe, low waste and proliferation resistant treatment of radwaste in accelerator driven and critical systems
22. Helium-induced damage behavior in high temperature nickel-based alloys with different chemical composition10.1016/j.jnucmat.2020.152419 ↗
23. Synergistic effect of irradiation and molten salt corrosion: acceleration or deceleration?10.1016/j.corsci.2021.109434 ↗
24. Defects evolution and hardening in the Hastelloy N alloy by subsequent Xe and He ions irradiation10.1016/j.jnucmat.2019.02.022 ↗
25. Behaviors of bubble-loop complexes in He-irradiated CLAM steels at elevated temperatures10.1016/j.jnucmat.2019.151954 ↗
26. In-situ TEM observation of the evolution of helium bubbles & dislocation loops and their interaction in Pd during He+ irradiation10.1016/j.jmst.2021.01.069 ↗
27. Quantitative characterization of frank loops and their effects on the plastic degradation in heavy ion irradiated alloy 800H10.1016/j.msea.2021.142501 ↗
28. Evolution of dislocation loops in He ion irradiated nickel under different temperature10.1063/1.4963344 ↗
29. Indentation size effects in crystalline materials: a law for strain gradient plasticity10.1016/S0022-5096(97)00086-0 ↗
30. A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques10.1016/j.fusengdes.2011.03.073 ↗
31. Effects of the long-time thermal exposure on the microstructure and mechanical properties of laser weldings of Inconel 61710.1016/j.jmatprotec.2017.05.003 ↗
32. Microstructure and mechanical properties of alloy 617B10.1016/S1003-6326(15)63704-9 ↗
33. Improvement of helium swelling resistance of nickel-based alloy via proper SiCNP dispersion
34. Mitigation of He embrittlement and swelling in nickel by dispersed SiC nanoparticles10.1016/j.matdes.2015.10.147 ↗
35. Helium bubble formation in nickel during hot implantation10.1016/0022-3115(94)90086-8 ↗
36. Helium accumulation in metals during irradiation – where do we stand?10.1016/j.jnucmat.2003.09.001 ↗
37. The interaction between a dislocation loop and a gas bubble10.1080/01418618508237655 ↗
38. Bubble-loop complexes induced by helium irradiation and effect of pre-irradiation and post-irradiation of hydrogen in reduced-activation ferritic/martensitic steel10.1080/14786435.2018.1492159 ↗
39. Combined effect of injected interstitials and He implantation, and cavities inside dislocation loops in high purity Fe-Cr alloys10.1016/j.jnucmat.2019.03.043 ↗
40. Single- and dual-beam in-situ irradiations of high-purity iron in a transmission electron microscope: effects of heavy ion irradiation and helium injection10.1016/j.actamat.2013.10.052 ↗
41. Temperature dependence of He bubble evolution in UNS N10003 alloys under He ion irradiation10.1063/5.0064975 ↗
42. The interaction between a dislocation loop and a gas bubble10.1080/01418618508237655 ↗
43. Interaction between vacancies and interstitial solutes (C, N, and O) in alpha-Fe: from electronic structure to thermodynamics10.1103/PhysRevB.90.054112 ↗
44. Effect of C on vacancy migration in alpha-iron10.4028/www.scientific.net/SSP.139.157 ↗
45. Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation10.1016/j.actamat.2016.05.007 ↗
46. Atomistic simulation of the obstacle strengths of radiation-induced defects in an Fe–Ni–Cr austenitic stainless steel10.1088/1361-651X/ab40f9 ↗
47. Thermomechanical treatment for improved neutron irradiation resistance of austenitic alloy (Fe–21Cr–32Ni)10.1016/j.jnucmat.2013.01.333 ↗
48. Indentation size effect, geometrically necessary dislocations and pile-up effects in hardness testing of irradiated nickel10.1016/j.actamat.2021.116702 ↗
49. Radiation-induced helium nanobubbles enhance ductility in submicron-sized single-crystalline copper10.1021/acs.nanolett.6b00864 ↗