1. Experience and assessment of stress corrosion cracking in L-grade stainless steel BWR internals
2. H. M. Chung, J. H. Park, W. E. Ruther, J. E. Sanecki, R. V. Strain, and N. J. Zaluzec, in Proc. 8th Intl. Symp. on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, S. M. Bruemmer, ed., American Nuclear Society, 1997, p. 846-856
3. J. M. Cookson, G. S. Was, and P. L. Andresen, in Proc. 7th Intl. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. NACE International, Houston, 1995, p. 1109
4. Irradiation-assisted stress corrosion cracking of austenitic stainless steels: recent progress and new approaches
5. H. M. Chung, J. E. Sanecki, and F. A. Garner, in Effects of Radiation on Materials: 18th International Symposium. ASTM STP 1325, R. K. Nanstad et al., eds., American Society for Testing and Materials, 1999, p. 647