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Enhancement of J estimation for typical nuclear pipes with a circumferential surface crack under tensile load
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  • Enhancement of J estimation for typical nuclear pipes with a circumferential surface crack under tensile load
  • Enhancement of J estimation for typical nuclear pipes with a circumferential surface crack under tensile load
저자명
Cho. Doo-Ho,Woo. Seung-Wan,Chang. Yoon-Suk,Choi. Jae-Boong,Kim. Young-Jin,Jhung. Myung-Jo,Choi. Young-Hwan
간행물명
Journal of mechanical science and technology
권/호정보
2010년|24권 3호|pp.681-686 (6 pages)
발행정보
대한기계학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

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 $H_1$ values can be used for elastic-plastic fracture analyses of thin-walled pipes with a circumferential surface crack subjected to tensile loading.