1. American Society of Mechanical Engineers, 2015, ASME Boiler and Pressure Vessel Code Section XI Rules for In-service Inspection of Nuclear Power Plant Components, BPVC-XI-2015, New York.
2. Brückner A. and Munz D., 1982, Curve Fitting to Defect Size Distributions for the Calculation of Failure Probabilities, Nuclear Engineering and Design 74, pp.75-78.
3. Harris D. O. and Dedhia D. D., 1998, WinPRAISE 98 PRAISE Code in Windows, Technical Report TR-98-4-1, Engineering Mechanics Technology inc.
4. Harris D. O., Lim E. Y. and Dedhia D. D., 1981, Probability of Pipe Fracture in the Primary Coolant Loop of a PWR Plant, NUREG/CR -2189.
5. Itoh H., Kato D., Osakabe K., Nishikawa H. and Onizawa K., 2010, User's Manuals of Probabilistic Fracture Mechanics Analysis Code for Aged Piping, PASCAL-SP, JAEA-Data/Code 2009-025.(in Japanese)