1. ASME.: ASME boiler and pressure vessel Code, Section III, NB 3200, Design, New York (2013)
2. RCC-M.: Design and construction rules for mechanical components of PWR nuclear islands (2016)
3. Fang, Y., Wang, Q., Chu, Q., et al.: Analysis and evaluation methodology of effect of light water reactor coolant environment on fatigue life of class 1 components. Atomic Energy Sci. Technol. 47(11), 2114–2119 (2013)
4. Chopra, O.K., Shack, W.J.: The effect of lwr coolant environments on the fatigue life of reactor materials. In: ASME Pressure Vessels and Piping Conference, vol 47527, pp 191–204 (2006)
5. Mehta, H.S., Gosselin, S.R.: An environmental factor approach to account for reactor water effects in light water reactor pressure vessel and piping fatigue evaluations. Am. Soc. Mech. Eng., New York, NY (United States) (1996)