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HomeNanotechnologyNanoindentation Evaluation of Irradiated A508-3 Metal

Nanoindentation Evaluation of Irradiated A508-3 Metal

The microstructural adjustments induced by irradiation result in adjustments in mechanical properties. An article printed within the Journal of Nuclear Supplies mentioned the adjustments in mechanical properties of A508-3 metal after irradiating it with iron (Fe+3) ions.​​​​​​​​​​​​​​

Nanoindentation Analysis of Irradiated A508-3 Steel​​​​​​​

​​​​​​​Examine: Nanoindentation experiment and crystal plasticity research on the mechanical conduct of Fe-ion-irradiated A508-3 metal. Picture Credit score: Allexxandar/

Right here, A508-3 metal samples have been irradiated with Fe+3 ions at 20, 100, and 300 levels Celsius with 0.1, 0.4, 2.0, and 5.0 displacements per atom utilizing the crystal plasticity finite component mannequin (CPFEM) and nanoindentation experiment. Making use of Nix–Gao mannequin helped receive the hardness (H0) from the measured knowledge, and the H0 of metal elevated with radiation harm in any respect temperatures.

The dislocation loop expedited the cell dislocation and retarded the motionless dislocation, resulting in bigger von Mises stresses of Fe ion irradiated metal samples with a flat form, and the realm of the von Mises stress shrunk with temperature. The current research demonstrated the deformation conduct of irradiated metal based mostly on microstructural and experimental evaluation.

Nanoindentation Technique for Estimation of Mechanical Properties in A508-3 Metal

Adjustments in mechanical properties are the implications of adjustments produced on the microstructure stage. Irradiation-induced microstructural evolution leads to the hardening of the metal by obstructing the motion of dislocations, thereby inflicting degradation of the fracture properties, such because the ductile-to-brittle transition temperature shift.

The irradiation-induced embrittlement of nuclear reactor strain vessel’s metal is a priority for the nuclear energy plants evaluation. A508-3 metal with 0.06 wt.% copper (Cu) is used for the strain vessel of many newly constructed nuclear energy crops in China. 

The extended irradiation of nuclear reactor strain vessel’s metal throughout nuclear fission response causes hardening/embrittlement as a result of defects within the matrix, together with dislocation loops, clusters, and the low Cu content material within the nuclear reactor strain vessel’s metal resulting in vacancy-solute atom complexes. 

Nonetheless, the irradiation-induced embrittlement conduct and mechanism of the A508-3 metal are unclear. Thus, varied strategies have been explored to analyze the affect of irradiation on defect evolution. Moreover, the micromechanical response of supplies was investigated by way of micropillar compression, nanoindentation, and in situ tensile assessments.

Among the many optimized strategies, nanoindentation was appropriate for speedy estimation of mechanical properties at micro- or nanoscales. Since nanoindentation alone can’t produce adequate data on mechanical response and microstructural evolution, it’s mixed with the CPFEM simulations. Thus, the nanoindentation and CPFEM mixed method overcomes the above drawbacks underneath various masses. 

Nanoindentation Experiment and CPFEM Examine on A508-3 Metal

CPFEM and nanoindentation have been extensively utilized in quite a few earlier research to find out varied structural facets and bodily properties of metals. Within the current research, Fe+3 ions of three.5 megaelectronvolts have been irradiated on A508-3 metal samples at temperatures 20, 100, and 300 levels Celsius with dislocations of 0.1, 0.4, 2.0, and 5.0 displacements per atom to judge their mechanical properties by way of nanoindentation adopted by simulations utilizing bodily CPFEM.

The nanoindentation helped receive particular values of irradiation hardening of A508-3 metal samples. The hardness–indentation-depth and cargo–indentation-depth curves have been obtained from CPFEM simulations.

Whereas the elastic modulus of A508-3 metal samples remained uninfluenced by the irradiation dose, the hardness of the samples elevated with rising harm ranges in any respect temperatures, indicating defects induced on the A508-3 metal samples by the irradiation of Fe+3 ions.

The microstructure evolution of A508-3 metal was investigated utilizing the CPFEM. The crystal anisotropy in numerous instructions indicated the impact of crystal orientation on stress distribution. The von Mises stress was noticed alongside [001], [110], and [111] instructions. Moreover the connection between experiment and simulation, this research helped derive the relationships between microscale and macroscale, selling the research of nuclear reactor strain vessels’ metal irradiation results.


To summarize, the mechanical properties of A508-3 metal irradiated with Fe+3 ions at varied displacements and temperatures have been investigated by nanoindentation experiment and CPFEM simulation. The obtained knowledge was enter into Nix–Gao mannequin to calculate H0 and attribute size (h*). The outcomes confirmed a rise in H0 with displacements per atom.

The elastic modulus of A508-3 metal was impartial of irradiation dose. Nonetheless, the hardness of the A508-3 metal elevated with irradiation harm in any respect temperatures, indicating the numerous affect of irradiation-induced defects on plastic conduct and dislocation gliding of the metal.

Cell and motionless dislocations and partial- and full-absorption dislocation loops have been 4 dominant hardening contributions to the classical crystal plasticity idea framework. The CPFEM helped simulate the hardness–indentation-depth and cargo–indentation-depth curves.

The macroscopic deformation conduct of Fe-ion-irradiated A508-3 metal was decided from microstructural evolution. Moreover, the von Mises stress was distributed alongside [001], [110], and [111] instructions. The dislocation loop accelerated the rise of cell dislocation and retarded the lower of motionless dislocation, leading to greater values of von Mises stress.


Lin, P., Nie, J., Liu, M. (2022) Nanoindentation experiment and crystal plasticity research on the mechanical conduct of Fe-ion-irradiated A508-3 metal. Journal of Nuclear Supplies

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