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Development of Security and Safety Fuel for Pu-Burner HTGR: Part 5 — Test and Characterization for ZrC Coating

[+] Author Affiliations
Shohei Ueta, Jun Aihara, Minoru Goto, Yukio Tachibana

Japan Atomic Energy Agency, Oarai, Japan

Koji Okamoto

University of Tokyo, Tokai, Japan

Paper No. ICONE25-67530, pp. V005T05A047; 4 pages
doi:10.1115/ICONE25-67530
From:
  • 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
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5783-0
  • Copyright © 2017 by ASME

abstract

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.

Copyright © 2017 by ASME

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