1. ASME, 1977, Boiler and Pressure Vessel Code, Section XI, Rules for Inspection of Nuclear Power Plant and Components, Division 1, Appendix A, The American Society of Mechanical Engineers, New York, pp. 175–188.
2. JWES, 1977, Method of Assessment for Flaws in Fusion Welded Joints with Respect to Brittle Fracture and Fatigue Crack Growth, WES 2805, The Japan Welding Engineering Society, Tokyo, pp. 18–19, and pp. E13-E40.
3. Ohta, A., Kosuge, M., Matsuoka, S., Takeuchi, E., Muramatsu, Y., and Nishijima, S., 1988, “Significance Effect of Thermal Stress on Fatigue Crack Propagation Properties,” Int. J. Fract., 38, pp. 207–216.
4. Ohta, A., Sasaki, E., Kamakura, M., Nihei, M., Kosuge, M., and Inagaki, M., 1981, “Effect of Residual Tensile Stress on Threshold Level for Fatigue Crack Propagation in Welded Joints of SM50B Steel,” Trans. Japan Weld. Soc.,12, pp. 31–38.
5. Ohta, A., Kosuge, M., Mawari, T., and Nishijima, S., 1988, “Fatigue Crack Propagation Properties of HT80 Steel Welded Joints Heat Treated for Relieving Residual Stress,” Trans. NRIM, 30, pp. 8–14.