대한기계학회논문집A (Transactions of the Korean Society of Mechanical Engineers A)

  • 제25권9호
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  • Pages.1350-1358
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  • 2001
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  • 1226-4873(pISSN)
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  • 2288-5226(eISSN)
대한기계학회 (The Korean Society of Mechanical Engineers)
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Evaluation of Load-Carrying Capacities for Cracked Pipes

  • 발행 : 2001.09.01
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초록

During the last decade, a number of experiments and numerical analyses had been performed in conjunction with the development of simplified analytical methods to estimate the fracture behavior of cracked piping in nuclear power plant. However, the necessity of further investigation for the analytical methods was issued because of the discrepancies with the experimental data. The objective of this paper is to find out the optimum methods to evaluate the load-carrying capacities for cracked pipes. To do this, numerous analytical and finite element analyses were carried out for various pipe and crack geometries and materials. These results were synthesized for crack shapes and can be used as basic data for leak before analyses and risk informed inspections.

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참고문헌

  1. Wilkowski, G.M., Ahmad, J., Barnes, C.R., Broek, D., Kramer, G., Landow, M., Marschall, C.W., Maxey, W., Nakagaki, M., Scott, P.M., Papaspyropoulos, V., Pasupathi, V. and Popelar, C., 1984, 'Degraded Piping Program- Phase II,' NUREG/CR-4082, Vol. 1-Vol. 8
  2. Wilkowski, G. M., Ahmad, J., Brust, F., Ghadiali, N., Krishnaswamy, P., Landow, M., Marschall, C. W., Scott, P.M. and Vieth, P., 1994, 'Short Cracks in Piping and Piping Welds,' NUREG/CR-4599, Vol. 1, No. 1-Vol. 4, No. 1
  3. Scott, P. M., Wilson, M., Olson, R., Marschall, C. W., Schmidt, R. and Wilkowski, G. M., 1991, 'International Piping Integrity Research Group Program,' Final Report, NUREG/CR-6233
  4. Hopper, A., Wilkowski, G. M., Scott, P. M., Olson, R., Rudland, D., Kilinski, T., Mohan, R., Ghadiali, N. and Paul, D., 1996, 'International Piping Integrity Research Group (IPIRG-2) Program,' Final Report, NUREG/CR-6452
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  7. Kurihara, R., Ueda, S. and Sturm, D., 1988, 'Estimation of the Ductile Unstable Fracture of Pipe with a Circumferential Surface Crack Subjected to Bending,' Nuclear Engineering and Design, Vol. 106, pp. 265-273
  8. Choi, Y. H., Chung, Y. K., Park, Y. W., Lee, J. B. and Willkowski, G. M., 1997, 'Development of New Z-Factors for the Evaluation of a Surface Crack in Nuclear Pipings,' Transactions of the 14th International Conference on SMiRT, Vol. 4, pp. 603-610
  9. Battelle, 1998, 'Pipe Fracture Encyclopedia,' Vol. 1-Vol. 4, Internal Communication
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