1. American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. Rules for Inservice Inspection of Nuclear Power Plant Components, Boiler and Pressure Vessel Code Section XI,1989
2. Stress intensity factor solution for continuous surface flaws in reactor pressure vessels;Buchalet,1976
3. ANSYS Engineering Analysis System User’s Information Manual and Theoretical Manual;DeSalvo,1991
4. Theoretical justification of the association of a critical net-section stress with fracture initiation at a crack tip;Smith;Int. J. Pressure Vessels Piping,1980
5. Weld Overlay Shrinkage Effect Assessment Report For Second Nuclear Power Station Unit 1993 Outage,1993