To develop the security and safety fuel (3S-TRISO fuel) for Pu-burner high temperature gas-cooled reactor (HTGR), R&D on zirconium carbide (ZrC) directly coated on yttria stabilized zirconia (YSZ) has been started in the Japanese fiscal year 2015. As results of the direct coating test of ZrC on the dummy YSZ particle, ZrC layers with 18–21 microns of thicknesses have been obtained with 0.1 kg of particle loading weight. No deterioration of YSZ exposed by source gases of ZrC bromide process was observed by Scanning Transmission Electron Microscope (STEM) observation.
- Nuclear Engineering Division
Development of Security and Safety Fuel for Pu-Burner HTGR: Part 5 — Test and Characterization for ZrC Coating
- Views Icon Views
- Share Icon Share
- Search Site
Ueta, S, Aihara, J, Goto, M, Tachibana, Y, & Okamoto, K. "Development of Security and Safety Fuel for Pu-Burner HTGR: Part 5 — Test and Characterization for ZrC Coating." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Shanghai, China. July 2–6, 2017. V005T05A047. ASME. https://doi.org/10.1115/ICONE25-67530
Download citation file: