1. 1. T. Shoji (1983 ) Role of loading variables in environment enhanced crack growth for water cooled nuclear reactor pressure vessel steels . Proceedings of the IAEA Specialists' Meeting on Subcritical Crack Growth, NUREG/CP-0044, Vol. 2 , pp. 143 -172 .
2. 2. J. D. Atkinson, S. T. Cole, and J. E. Forrest (1983 ) Corrosion fatigue mechanisms in ferritic pressure vessel steels exposed to simulated PWR environments . Proceedings of the IAEA Specialists' Meeting on Subcritical Crack Growth, NUREG/CP-0044, Vol. 2 , pp. 173 -197 .
3. 3. T. A. Prater, and L. F. Coffin (1983 ) Crack growth studies on a carbon steel in oxygenated high pressure water at elevated temperatures . Proceedings of the IAEA Specialists' Meeting onSubcritical Crack GrowthNUREG/CP-0044, pp. 355 , 355 .
4. Corrosion Fatigue Crack Growth in Reactor Pressure Vessel Steels in PWR Primary Water
5. 5. Der Sluys W. A. Van, and R. Emanuelson (1986 ) Overview of data trends in cyclic crack growth results in LWR environments . 2nd IAEA Specialists' Meeting onSubcritical Crack Growth, NUREG/CP-0067, Vol. 2 , pp.199 -218 .