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Development of a Three-Dimensional Green’s Function and Its Application to the Fatigue Evaluation of Reactor Pressure Vessel

[+] Author Affiliations
M. Y. Ahn, J. C. Kim, Y. S. Chang, J. B. Choi, Y. J. Kim

Sungkyunkwan University, Suwon, Korea

M. J. Jhung, Y. H. Choi

Korea Institute of Nuclear Safety, Daejeon, Korea

Paper No. PVP2006-ICPVT-11-94056, pp. 527-532; 6 pages
doi:10.1115/PVP2006-ICPVT-11-94056
From:
  • ASME 2006 Pressure Vessels and Piping/ICPVT-11 Conference
  • Volume 2: Computer Technology
  • Vancouver, BC, Canada, July 23–27, 2006
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4753-5 | eISBN: 0-7918-3782-3
  • Copyright © 2006 by ASME

abstract

The design of major nuclear components for the prevention of fatigue failure has been achieved on the basis of ASME codes, which are usually very conservative. However, it is necessary to make it more accurate for the continued operation beyond the design life. In this paper, 3-dimensional stress and fatigue analyses reflecting entire geometry have been carried out. The number of operating transient data obtained from a monitoring system were filtered and analyzed. Then, Green’s function which transfers temperature gradient into the corresponding thermal stress is proposed and applied to critical locations of a reactor pressure vessel. The validity of proposed Green’s function is approved by comparing the result with corresponding 3-D finite element analysis results. Also, the amount of conservatism included in design transients in comparison with real transients is analyzed. The results for 3-D finite element analysis are also compared with corresponding 2-D finite element analysis results, and a considerable amount of difference was observed in terms of fatigue life. Therefore, it is expected that the proposed evaluation scheme adopting real operating data and Green’s function can provide more accurate fatigue life evaluation for a reactor pressure vessel.

Copyright © 2006 by ASME

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