FEA Study on Hoop Stress of Multilayered SiC Composite Tube for Nuclear Fuel Cladding

핵연료 피복관용 다중층 SiC 복합체 튜브의 Hoop Stress 전산모사 연구

  • Lee, Hyeon-Geun (Nuclear Materials Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Daejong (Nuclear Materials Development Division, Korea Atomic Energy Research Institute) ;
  • Park, Ji Yeon (Nuclear Materials Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Weon-Ju (Nuclear Materials Development Division, Korea Atomic Energy Research Institute)
  • 이현근 (한국원자력연구원 원자력소재개발부) ;
  • 김대종 (한국원자력연구원 원자력소재개발부) ;
  • 박지연 (한국원자력연구원 원자력소재개발부) ;
  • 김원주 (한국원자력연구원 원자력소재개발부)
  • Received : 2014.07.31
  • Accepted : 2014.09.11
  • Published : 2014.09.30


Silicon carbide-based ceramics and their composites have been studied for application to fusion and advanced fission energy systems. For fission reactors, $SiC_f$/SiC composites can be applied to core structural materials. Multilayered SiC composite fuel cladding, owing to its superior high temperature strength and low hydrogen generation under severe accident conditions, is a candidate for the replacement of zirconium alloy cladding. The SiC composite cladding has to retain its mechanical properties and original structure under the inner pressure caused by fission products; as such it can be applied as a cladding in fission reactor. A hoop strength test using an expandable polyurethane plug was designed in order to evaluate the mechanical properties of the fuel cladding. In this paper, a hoop strength test of the multilayered SiC composite tube for nuclear fuel cladding was simulated using FEA. The stress caused by the plug was distributed nonuniformly because of the friction coefficient difference between the inner surface of the tube and the plug. Hoop stress and shear stress at the tube was evaluated and the relationship between the concentrated stress at the inner layer of the tube and the fracture behavior of the tube was investigated.


Supported by : 한국연구재단


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