Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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INTERACTION STUDIES OF CERAMIC VACUUM PLASMA SPRAYING FOR THE MELTING CRUCIBLE MATERIALS

  • Kim, Jong Hwan (Quantum Energy Chemical Engineering, University of Science and Technology) ;
  • Kim, Hyung Tae (Next Generation Fuel Division, Korea Atomic Energy Research Institute) ;
  • Woo, Yoon Myung (Next Generation Fuel Division, Korea Atomic Energy Research Institute) ;
  • Kim, Ki Hwan (Next Generation Fuel Division, Korea Atomic Energy Research Institute) ;
  • Lee, Chan Bock (Next Generation Fuel Division, Korea Atomic Energy Research Institute) ;
  • Fielding, R.S. (Nuclear Fuel and Materials Division, Idaho National Laboratory)
  • Received : 2013.02.05
  • Accepted : 2013.04.24
  • Published : 2013.10.25
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Abstract

Candidate coating materials for re-usable metallic nuclear fuel crucibles, TaC, TiC, ZrC, $ZrO_2$, and $Y_2O_3$, were plasmasprayed onto a niobium substrate. The microstructure of the plasma-sprayed coatings and thermal cycling behavior were characterized, and U-Zr melt interaction studies were carried out. The TaC and $Y_2O_3$ coating layers had a uniform thickness, and high density with only a few small closed pores showing good consolidation, while the ZrC, TiC, and $ZrO_2$ coatings were not well consolidated with a considerable amount of porosity. Thermal cycling tests showed that the adhesion of the TiC, ZrC, and $ZrO_2$ coating layers with niobium was relatively weak compared to the TaC and $Y_2O_3$ coatings. The TaC and $Y_2O_3$ coatings had better cycling characteristics with no interconnected cracks. In the interaction studies, ZrC and $ZrO_2$ coated rods showed significant degradations after exposure to U-10 wt.% Zr melt at $1600^{\circ}C$ for 15 min., but TaC, TiC, and $Y_2O_3$ coatings showed good compatibility with U-Zr melt.

Keywords

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