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링 시험편을 이용한 피복관의 고온 인장특성 평가

Evaluation of the Tensile Properties of Fuel Cladding at High Temperatures Using a Ring Specimen

  • 배봉국 (성균관대학교 기계공학부) ;
  • 구재민 (성균관대학교 기계공학부) ;
  • 석창성 (성균관대학교 기계공학부)
  • 발행 : 2005.04.01

초록

In this study, the ring tensile test at high temperature was suggested to evaluate the hoop tensile properties of small tube such as the cladding in the nuclear reactor Using the Arsene's ring model, the ring tensile test was performed and the test data were calibrated. From the result of the ring test with strain gauge and the numerical analysis with 1/8 model, LCRR(load-displacement conversion relationship of ring specimen) was determined. We could obtain the hoop tensile properties by means of applying the LCRR to the calibrated data of the ring tensile test. A few difference was observed in view of the shape of fractured surface and the fracture mechanism between at the high temperature and at the room temperature.

키워드

참고문헌

  1. KAERI, 1999, Development of Advanced LWR Fuel Cladding
  2. Arsene, Sylvie and Bai, Jinbo, 1998, 'A New Approach to Measuring Transverse Properties of Structural Tubing by a Ring Test - Experimental Investigation,' Journal of Testing and Evaluation, JTEVA, Vol. 26, No. 1, January, pp. 26-30 https://doi.org/10.1520/JTE11966J
  3. Bae, B. K., Koo, J. M. and Seok, C. S., 2003, 'A Study on the Method of Evaluating the Tensile Property of Ring Specimen Having Gauge Length,' Proc. KSME fall, pp. 167-172
  4. Bae, B. K., Kim, H. I., Lee, Y. M., Koo, J. M. and Seok, C. S., 2004, 'Analysis for the Effect of Friction Coefficient in Ring Tensile Test,' Proc. KSPE spring, p. 88
  5. Lee, K. W., Kim, S. K., Kim, K. T. and Hong, S. I., 2001, 'Ductility and Strain Rate Sensitivity of Zircaloy-4 Nuclear Fuel Claddings,' Jr. of Nuclear Materials, 295, pp. 21-26 https://doi.org/10.1016/S0022-3115(01)00509-8
  6. Link, T. M., Koss, D.A. and Motta, A.T., 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
  7. Pierron, O.N., Koss, D.A. and Motta, A.T., 2003, 'Tensile Specimen Geometry and the Constitutive Behavior of Zircaloy-4,' Journal of Nuclear Materials, Vol. 312, pp. 257-261 https://doi.org/10.1016/S0022-3115(02)01554-4
  8. Oh, D. J., Ahn, S. B. and Hong, K. P., 2003, 'New Fracture Toughness Test Method of Zircaloy-4 Nuclear Fuel Cladding,' Jr. of KSME, Vol. 27, No.5, pp. 823-832 https://doi.org/10.3795/KSME-A.2003.27.5.823
  9. Cho, Y. R., Jeong, H. Y. and Kim, I. B., 1990, 'A Study on the High Temperature Tensile Properties of Hydrided Zircaloy-4,' Jr. of KISE, Vol. 23, No.1, pp. 44-51
  10. Kallstrom, K. and Svenzon, M., 1973, 'Dynamic Strain Aging in Zircaloy and its Dependence on Cold Work, Recrystallization and Grain Size,' Scandinavian Jr. of Metallurgy, Vol. 2, pp. 55-58
  11. Ramachandran, V. and Reed-Hill, R.E., 1970, 'Dynamic Strain Aging and Ductility Minima in Zirconium,' Metallurgical Trans., Vol. 1, pp. 2106-2109
  12. Rheem, K. S. and Park, W. K., 1976, 'Strain Ageing in Zircaloy-4,' Jr. of Korean Nuclear Society, Vol. 8, No. 1, pp. 19-27