1. Fracture behavior of straight pipe and elbow with local all thinning;Ahn;Nucl. Eng. Des.,2002
2. ASME B&PV Code Sec. III, Nuclear Components. 1998ed.;American Society of Mechanical Engineer (ASME),1998
3. ASME B&PV Code Sec. XI, Rules for Inservice Inspection of Nuclear Power Plant Components. 1998ed.;American Society of Mechanical Engineer (ASME),1998
4. ASME B&PV Sec. XI, Div.1, ASME Code Case N-597-rev.2, Requirement for Analytical Evaluation of Pipe Wall Thinning;American Society of Mechanical Engineer (ASME),2003
5. Flow-Accelerated Corrosion in Power Plant;Chexal,1998