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Journal Articles

${it In situ}$ WB-STEM observation of dislocation loop behavior in reactor pressure vessel steel during post-irradiation annealing

Du, Y.*; Yoshida, Kenta*; Shimada, Yusuke*; Toyama, Takeshi*; Inoue, Koji*; Arakawa, Kazuto*; Suzudo, Tomoaki; Milan, K. J.*; Gerard, R.*; Onuki, Somei*; et al.

Materialia, 12, p.100778_1 - 100778_10, 2020/08

In order to ensure the integrity of the reactor pressure vessel in the long term, it is necessary to understand the effects of irradiation on the materials. In this study, irradiation-induced dislocation loops were observed in neutron-irradiated reactor pressure vessel specimens during annealing using our newly developed WB-STEM. It was confirmed that the proportion of $$<100>$$ loops increased with increasing annealing temperature. We also succeeded in observing the phenomenon that two $$frac{1}{2}$$$$<111>$$ loops collide into a $$<100>$$ loop. Moreover, a phenomenon in which dislocation loops decorate dislocations was also observed, and the mechanism was successfully explained by molecular dynamics simulation.

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In-situ weak-beam scanning transmission electron microscopy for quantitative dislocation analysis in nuclear materials during post-irradiation annealing

Yoshida, Kenta*; Du, Y.*; Shimada, Yusuke*; Suzudo, Tomoaki; Toyama, Takeshi*; Inoue, Koji*; Arakawa, Kazuto*; Milan, K. J.*; Gerard, R.*; Nagai, Yasuyoshi*

no journal, , 

We developed a weak-beam scanning transmission electron microscopy (WB-STEM) by installing a novel beam selector, annular detector, a high-speed CCD camera and imaging filter in a camera chamber of an aberration corrected electron microscope. In-situ observation confirmed that the newly-developed WB-STEM has improved the ability to observe the dynamic behavior of dislocation loops. In addition, we performed a numerical simulation of dislocation loop behavior using molecular dynamics, and confirmed that the experimental results were well explained by the theoretical analysis. Therefore, this WB-STEM is expected to be useful for understanding the embrittlement mechanism of nuclear materials such as reactor pressure vessel (RPV) steels.

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