1. Aging and Life Extension of Major Light Water Reactor Components;Shah,1993
2. Fatigue behavior of SA533–B1 steels;Huang,2001
3. J.Y. Huang, C.Y. Chen, K.F. Chien, R.C. Kuo, P.K. Liaw, J.G. Huang, in: Proceedings of the Julia Weertman Symposium, TMS Fall Meeting, October 31–November 4, 1999, pp. 373–384.
4. H.P. Seifert, S. Ritter, J. Heldt, Strain induced corrosion cracking of low-alloy reactor pressure vessel steels under BWR conditions, in: F.P. Ford, G.S. Was, J.L. Nelson (Eds.), Proceedings of the 10th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2001.
5. H.P. Seifert, S. Ritter, J. Hickling, Environmentally-assisted cracking of low-alloy RPV and piping steels under LWR conditions, in: G.S. Was, L. Nelson, P. King (Eds.), Proceedings of the 11th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, 2003, pp. 73–89.