2015
DOI: 10.1016/j.jnucmat.2015.08.047
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Cracking behavior of thermally aged and irradiated CF-8 cast austenitic stainless steel

Abstract: 2016-11-02T18:49:00

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Cited by 23 publications
(4 citation statements)
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“…Cast duplex stainless steel (CDSS), widely used in pressure water reactors (PWRs) as the primary circuit piping and the reactor coolant pump casing, is sensitive to thermal aging embrittlement after long-term service [1][2][3][4][5][6]. This embrittlement causes a degradation in the mechanical properties of CDSS, such as impact toughness, tensile properties, and fatigue properties [7][8][9][10][11][12][13].…”
Section: Introductionmentioning
confidence: 99%
“…Cast duplex stainless steel (CDSS), widely used in pressure water reactors (PWRs) as the primary circuit piping and the reactor coolant pump casing, is sensitive to thermal aging embrittlement after long-term service [1][2][3][4][5][6]. This embrittlement causes a degradation in the mechanical properties of CDSS, such as impact toughness, tensile properties, and fatigue properties [7][8][9][10][11][12][13].…”
Section: Introductionmentioning
confidence: 99%
“…In addition, the SCC susceptibility is related with the content of δ-ferrite. Abundant δ-ferrite phase can decrease the SCC susceptibility effectively [18]. The stress corrosion crack can be retarded by the δ/γ interface, which results in high corrosion cracking resistance [19].…”
Section: Microstructurementioning
confidence: 99%
“…Z3CN20.09M duplex stainless steel (DSS) is used in primary coolant pipes of pressurized water reactors (PWR), which consisted of ∼15 vol% ferrite and ∼85 vol% austenite phases . Thermal aging often occurred in the DSS due to the precipitation of Cr‐rich α′ phase and G phase in the ferrite phase when the steel is served at temperature between 200 °C and 550 °C for a long time, deteriorating not only the mechanical but also corrosion properties of the DSS .…”
Section: Introductionmentioning
confidence: 99%