2011
DOI: 10.1016/j.jnucmat.2011.01.035
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Effects of hydrogen water chemistry on corrosion fatigue behavior of cold-worked 304L stainless steel in simulated BWR coolant environments

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Cited by 12 publications
(1 citation statement)
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“…Austenite stainless steels (SSs) have been widely used in pressurized water reactor (PWR) nuclear power plants due to their outstanding corrosion resistance, stability, and mechanical properties [1][2][3][4]. Austenite stainless steels such as 304L and 316L SSs are often used as the primary coolant pipe in PWR servicing in high-temperature and high-pressure water environments and at a complex stress state [5][6][7]. It often suffers constant tensile stress during stable operation and cyclic fatigue stress during startup, shutdown, and the instability condition of nuclear power plants.…”
Section: Introductionmentioning
confidence: 99%
“…Austenite stainless steels (SSs) have been widely used in pressurized water reactor (PWR) nuclear power plants due to their outstanding corrosion resistance, stability, and mechanical properties [1][2][3][4]. Austenite stainless steels such as 304L and 316L SSs are often used as the primary coolant pipe in PWR servicing in high-temperature and high-pressure water environments and at a complex stress state [5][6][7]. It often suffers constant tensile stress during stable operation and cyclic fatigue stress during startup, shutdown, and the instability condition of nuclear power plants.…”
Section: Introductionmentioning
confidence: 99%