Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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THERMAL SHOCK FRACTURE OF SILICON CARBIDE AND ITS APPLICATION TO LWR FUEL CLADDING PERFORMANCE DURING REFLOOD

  • Lee, Youho (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology (MIT)) ;
  • Mckrell, Thomas J. (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology (MIT)) ;
  • Kazimi, Mujid S. (Department of Nuclear Science and Engineering, Massachusetts Institute of Technology (MIT))
  • Received : 2013.09.12
  • Accepted : 2013.09.24
  • Published : 2013.11.25
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Abstract

SiC has been under investigation as a potential cladding for LWR fuel, due to its high melting point and drastically reduced chemical reactivity with liquid water, and steam at high temperatures. As SiC is a brittle material its behavior during the reflood phase of a Loss of Coolant Accident (LOCA) is another important aspect of SiC that must be examined as part of the feasibility assessment for its application to LWR fuel rods. In this study, an experimental assessment of thermal shock performance of a monolithic alpha phase SiC tube was conducted by quenching the material from high temperature (up to $1200^{\circ}C$) into room temperature water. Post-quenching assessment was carried out by a Scanning Electron Microscopy (SEM) image analysis to characterize fractures in the material. This paper assesses the effects of pre-existing pores on SiC cladding brittle fracture and crack development/propagation during the reflood phase. Proper extension of these guidelines to an SiC/SiC ceramic matrix composite (CMC) cladding design is discussed.

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References

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