Abstract
A modern Chinese ferritic/martensitic steel SIMP, is a new perspective nuclear structural material for the spallation target in accelerator driven sub-critical system. In this work, aimed at exploring the radiation resistance properties of this material, we investigate the differences between simultaneous Fe and He ions irradiation and He implantation of SIMP steel pre-irradiated by Fe self-ions. The irradiations were performed at 300 °C. The radiation-induced hardening was evaluated by nano-indentation, while the lattice disorder was investigated by transmission electron microscopy. Clear differences were found in the material microstructure after the two kinds of the ion irradiation performed. Helium cavities were observed in the co-irradiated SIMP steel, but not the case of He implantation with Fe pre-irradiation. In the same time, the size and density of Frank loops were different in the two different irradiation conditions. The reason for the different observed lattice disorders is discussed.
Highlights
Nuclear energy is a leading source of low-carbon electricity in the world
We investigated the microstructure of SIMP steel irradiated by
The hardness values between the Fe irradiation and Fe pre-irradiation + He implantation have little difference, which indicates that the He implantation does not introduce pronounce hardness
Summary
Nuclear energy is a leading source of low-carbon electricity in the world. Together with renewables, it provides an essential role in the global energy transition. In ADS operation surroundings, SIMP steel suffers from synergistic influence of neutron irradiation, LBE corrosion and high temperature. Cr–1.5 W–0.5 Mn–0.2 V–0.1 C, wt.%) at RT They argued significant irradiation hardening via He ions irradiation to fluences of 0.7–1.0 × 1017 ions/cm at room temperature (RT), and less contribution of the subsequent Fe ions irradiation to a fluence of 5.0 × 1015 ions/cm at RT. Dislocation loops are concerned, because clusters of self-interstitial atoms and interstitialtype dislocation loops are of the main microstructural damage features at intermediate temperatures (room temperature to 300 ◦ C) These defects act as obstacles for dislocation movement, resulting in irradiation hardening and the increase in ductile-to-brittle transition temperature (DBTT)
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