DOI QR코드

DOI QR Code

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

Abstract

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.

Keywords

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

References

  1. Link, T. M., Koss, Don and Motta, Thompson, 1998, 'Failure of Zircaloy under Transverse Plane-Strain Deformation,' Nuclear Eng. and Design, Vol. 186, pp. 379-394 https://doi.org/10.1016/S0029-5493(98)00284-2
  2. ASTM E8, 1995, 'Standard Test Methods for Tension Testing of Metallic Materials,' pp. 56-136
  3. Arsene, Sylvie and Bai, Jinbo, 1996, 'New Approach to Measuring Transverse Properties of Structural Tubing by a Ring Test,' J. of Testing & Evaluation, Vol. 24, No. 6, pp. 386-391 https://doi.org/10.1520/JTE11461J
  4. Arsene, Sylvie and Bai, Jinbo, 1998, 'New Approach to Measuring Transverse Properties of Structural Tubing by a Ring Test - Experimental Investigation,' J. of Testing & Evaluation, Vol. 26, No. 1, pp. 26-30 https://doi.org/10.1520/JTE11966J
  5. Yi, Jae-Kyung and Lee, Byong-Whi, 1987, 'Out-of-pile Test for Yielding Behavior of PWR Fuel Cladding Material,' J. of the Korea Nuclear Society, Vol. 19, No. 1, pp. 22-33
  6. Kuroda, Masatoshi and etc., 2001, 'Analysis of the Fracture Behavior of Hydrided Fuel Cladding by Fracture Mechanics,' Nuclear Eng. and Design, Vol. 203, pp. 183-194 https://doi.org/10.1016/S0029-5493(00)00323-X
  7. Lemoine, Francette, 1997, 'High Burnup Fuel Behavior Related to Fission Gas Effects under Reactivity Initiated Accidents (RIA) Conditions,' J. of Nuclear Materials, Vol. 248, pp. 238-248 https://doi.org/10.1016/S0022-3115(97)00157-8