A Study on the Mechanical Properties of Nuclear Fuel Cladding Materials

원자로용 핵연료 피복재의 인장특성에 관한 연구

  • 배봉국 (성균관대학교 대학원 기계공학부) ;
  • 송춘호 (성균관대학교 산업설비안전성평가 연구센터) ;
  • 석창성 (성균관대학교 기계공학부)
  • Published : 2003.02.01


The fuel of light water reactor is used for several years under high temperature and pressure, so it needs to be clad with high corrosion resistance material. The cladding materials must have the characteristics of low absorption of a neutron and high corrosion resistance. Zircaloy-2 in Boiling Water Reactor, Zircaloy-4 in Pressurized Water Reactor have been used as cladding materials and Zirlo has been developed as the material for preventing the corrosion. If the fracture of the cladding tube occurs during operation, it will cause the economic loss to shut down and replace the system. So it is needed to evaluate the integrity of the cladding materials. In this paper, the tensile characteristics of the cladding materials were investigated for the basic research of fracture characteristics. Also the residual stress was analyzed to compare the tube type(original type) specimen and the flattened type specimen.


Zircaloy;Zirlo;Nuclear Fuel Cladding;Tensile Test;Mini-Specimen


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