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Enhancement of J estimation for typical nuclear pipes with a circumferential surface crack under tensile load D. Cho/S. Woo/Y. Chang/J. Choi/Y. Kim/M. Jhung/Y. Choi
The Journal of Mechanical Science and Technology, vol. 24, no. 3, pp.681-686, 2010
Abstract : This paper is to report enhancement of engineering J estimation for semi-elliptical surface cracks under tensile load. Firstly, limitation
of the sole solution suggested by Zahoor is shown for reliable structural integrity assessment of thin-walled nuclear pipes. An improved
solution is then developed based on extensive 3D FE analyses employing deformation plasticity theory for typical nuclear piping materials.
It takes over the structure of the existing solution but provides new tabulated plastic influence functions to cover a wide range of pipe
geometry and crack shape. Furthermore, to facilitate easy prediction of the plastic influence function, an alternative simple equation is
also developed by using a statistical response surface method. The proposed H1 values can be used for elastic-plastic fracture analyses of
thin-walled pipes with a circumferential surface crack subjected to tensile loading.
Keyword :
J-integral; Plastic influence function; Response surface method; Stress intensity factor; Thin-walled nuclear pipe
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