1. ASME Boiler and Pressure Vessel Code, Section III, Appendix G, The American Society of Mechanical Engineers, New York, 1989.
2. Bueckner, H. F., 1970, “A Novel Principle for the Computation of Stress Intensity Factors,”Z. Angewandte Mathemat, Mechan, Vol. 50, No. 9, pp. 529–546.
3. Bloom, J. M., 1983, “Procedure for the Assessment of Structural Integrity of Nuclear Pressure Vessels,”ASME Journal of Pressure Vessel Technoogy, Vol. 105.
4. Bloom, J. M., 1985, “Extensions of the Failure Assessment Diagram Approach Semi-Elliptical Flaw in Pressurized Cylinder,”ASME Journal of Pressure Vessel Technology, Vol. 107.
5. Bloom, J. M. and Malik, S. N., 1982, “A Procedure for the Assessment of Nuclear Pressure Vessels and Piπng Contaning Defects,” EPRI Topical Report NP-2431, Research Project 1237-2, Palo Alto, Calif.