1. Alternative reference fracture toughness for development of P–T limit curves, Section XI, Division 1;ASME Boiler and Pressure Vessel Code, Code Case N-640,1999
2. Chinshan nuclear power station Unit 2 reactor vessel surveillance materials testing and fracture toughness analysis. INER-A0089;Chu,1999
3. The sensitivity of pressurized thermal shock analysis results to alternative models for weld flaw distributions;Dickson,2003
4. Review of proposed methodology for a risk-informed relaxation to ASME section XI–Appendix G;Dickson,2010
5. Fracture Analysis of Vessels-Oak Ridge FAVOR, v12.1, Computer Code: User's Guide. ORNL/TM-2012/566;Dickson,2012