Quantifying dislocation-type defects in post irradiation examination via transfer learning
The quantitative analysis of dislocation-type defects in irradiated materials is critical to materials characterization in the nuclear energy industry. The conventional approach of an instrument scientist manually identifying any dislocation defects is both time-consuming and subjective, thereby potentially introducing inconsistencies in the quantification. This work approaches dislocation-type defect identification and segmentation using a standard open-source […]
Catalyzed oxidation of IG-110 nuclear graphite by simulated fission products Ag and Pd nanoparticles
To evaluate the stability of nuclear materials in high temperature gas reactors under air ingress conditions, catalytic oxidation of IG-110 graphite by two simulated fission products, metallic Pd and Ag, was studied in oxidative atmosphere and at temperatures up to 1000ºC using an integrated furnace, mass spectroscopy and infrared spectroscopy system. Transmission electron microscopy and […]
Catalyzed oxidation of nuclear graphite by simulated fission products Sr, Eu, and I
The influence of three fission products Sr, Eu, and I on the oxidation of IG-110 nuclear graphite was studied in the temperature range of 400 to 1000 °C. Sr and Eu were introduced as chlorides, and I was introduced as NaI. The temperature dependence of both CO2 and CO production during the graphite oxidation measured […]