Estimation of crack opening area for leak before break analysis of nuclear reactor system

被引:8
作者
Ghosh, B. [1 ]
Bandyopadhyay, S. K. [1 ]
Lele, H. G. [1 ]
Ghosh, A. K. [1 ]
机构
[1] Bhabha Atom Res Ctr, Reactor Safety Div, Bombay 85, Maharashtra, India
关键词
CYLINDRICAL-SHELL; PIPES; TENSION;
D O I
10.1016/j.nucengdes.2008.08.025
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The crack opening area has been estimated by various models for leak before break analysis of nuclear reactor systems. A number of linear elastic fracture mechanics models have been employed. A model has been derived based on Forman et al. [Forman, R.G., Hickman, J.C., Shivakumar, V., 1985. Stress intensity factors for circumferential through cracks in hollow cylinders subjected to combined tension and bending loads. Eng. Frac. Mech. 21, 563-571] model for stress intensity factors. The linear elastic fracture models entail the use of plasticity corrections. The convergence behaviour of the iterative implementation for plasticity correction has been studied. An elasto-plastic fracture mechanics model has also been adopted for comparative study undertaken here. The range of applicability of the models has been reviewed. (C) 2008 Published by Elsevier B.V.
引用
收藏
页码:327 / 337
页数:11
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