PSI - Issue 14

Rajwinder Singh et al. / Procedia Structural Integrity 14 (2019) 930–936 Author name / Structural Integrity Procedia 00 (2018) 000–000

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low alloy steels for advanced pressure vessel materials. International Journal of Pressure Vessels and Piping 131, 60–66. Lee, S.G., Kim, I.S., 2001. Strain rate effects on the fatigue crack growth of SA508 Cl.3 Reactor Pressure Vessel Steel in high-temperature water environment. Journal of Pressure Vessel Technology 123, 173–178. Mager, T.R., Moon, D.M., Landes, J.D., 1977. Fatigue crack growth characteristics of A533 Grade B Class I plate in an environment of high-temperature primary grade nuclear reactor water. Journal of Pressure Vessel Technology, Please add Vol. No., 238–247. Newman, J.C., Phillips, E.P., Swain, M.H., 1999. Fatigue-life prediction methodology using small-crack theory. International Journal of Fatigue 21, 109–119. Singh, R., Singh, A., Arora, A., K. Singh, P., K. Mahajan, D., Hénaff, G., 2018. On the transition of short cracks into long fatigue cracks in reactor pressure vessel steels. MATEC Web Conf. 165, 13001. Strubbia, R., Hereñú, S., Alvarez-Armas, L., Krupp, U., 2014. Short fatigue cracks nucleation and growth in lean duplex stainless steel LDX 2101. Materials Science & Engineering A 615, 169–174. Wu, X.Q., Kim, I.S., 2003. Effects of strain rate and temperature on tensile behavior of hydrogen-charged SA508 Cl.3 pressure vessel steel. Materials Science and Engineering A 348, 309–318.