Review of work related to ‘leak-before-break’ assessment
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[1] M. L. Vanderglas. Experiences using three-dimensional finite element analysis for leak-before-break assessment , 1990 .
[2] Kunio Hasegawa,et al. Fracture behavior of cracked type 304 stainless steel pipes under tensile and thermal loadings , 1985 .
[3] Yukio Takahashi,et al. Research activities on fracture mechanics for nuclear piping in Japan , 1987 .
[4] Akram Zahoor,et al. Evaluation of J-integral estimation scheme for flawed throughwall pipes , 1987 .
[5] A. Pini,et al. Fracture behaviour of stainless steel pipes containing circumferential cracks at room temperature and 280°C , 1990 .
[6] Kunio Hasegawa,et al. Consideration of allowable flaw size for pressurized pipes , 1985 .
[7] M. J. Kozluk,et al. Demonstrating leak-before-break for CANDU heat transport piping , 1988 .
[8] Kunio Hasegawa,et al. Stable Growth and Instability of Circumferential Cracks in Type 304 Stainless Steel Pipes Under Tensile Load , 1984 .
[9] P. P. Milella. Outline of nuclear piping research conducted in Italy , 1987 .
[10] D. M. Parks. A stiffness derivative finite element technique for determination of crack tip stress intensity factors , 1974 .
[11] W. L. Server,et al. Leak-before-break: An integrated approach for high energy piping , 1988 .
[12] M. J. Kozluk,et al. A leak-before-break strategy for CANDU primary piping systems , 1986 .
[13] Genki Yagawa,et al. Three-Dimensional Fully Plastic Solutions for Plates and Cylinders With Through-Wall Cracks , 1985 .
[14] Kumar,et al. Engineering approach for elastic-plastic fracture analysis , 1981 .
[15] Ad Bakker,et al. An analysis of the numerical path dependence of the J-integral , 1983 .
[16] K. R. Wichman,et al. Development of USNRC standard review plan 3.6.3 for leak-before-break applications to nuclear power plants , 1990 .
[17] T. Takahashi,et al. Leak-before-break experiments on heat-treated Zr-2·5 wt% Nb pressure tubes , 1990 .
[18] B. Mukherjee,et al. The curve leak-before-break test program on material for the darlington nuclear generating station , 1988 .
[19] T. K. Hellen. On the method of virtual crack extensions , 1975 .