Intergranular stress corrosion cracking (IGSCC) of two commercial alloy 600 conditions (600LT, 600HT) and controlled- purity Ni-18Cr-9Fe alloys (CDMA, CDTT) were investigated using constant extension rate tensile (CERT) tests in primary water (0.01M LiOH+0.01M H{sub 3}BO{sub 3}) with 1 bar hydrogen overpressure at 360{degrees}C and 320{degrees}C. Heat treatments produced two types of microstructures in both commercial and controlled-purity alloys: one dominated by grain boundary carbides (600HT and CDTT) and one dominated by intragranular carbides (600LT and CDMA). CERT tests were conducted over a range of strain rates and at two temperatures with interruptions at specific strains to determine the crack depth distributions. Results show tha...
The nature of intergranular stress corrosion cracking (SCC) of alloy X-750 was characterized in low-...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
This work aims to study the stress corrosion crack growth behavior of cold-rolled Alloy 690 in the p...
The objective of this work is to provide a better understanding of the role of grain boundary chemis...
SCC susceptibility of Alloy 600 in deaerated water at 360 C (statically loaded U-bend specimens) is ...
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to...
The primary water stress corrosion cracking (PWSCC) of Alloy 600 in a PWR has been reported in the c...
The primary water stress corrosion cracking (PWSCC) of Alloy 600 in a PWR has been reported in the c...
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to...
The roles of carbon and grain boundary carbides on the creep and cracking behaviors of controlled pu...
Cold-work has been associated with the occurrence of intergranular cracking of stainless steels empl...
Nickel base alloys 600 and 690 have found widespread applications in nuclear reactor steam generator...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...
The susceptibility to stress corrosion cracking (SCC) of hot-rolled AZ31 Mg alloy sheets with differ...
The mitigating effect introduced by intergranular Cr carbides on the stress corrosion cracking propa...
The nature of intergranular stress corrosion cracking (SCC) of alloy X-750 was characterized in low-...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
This work aims to study the stress corrosion crack growth behavior of cold-rolled Alloy 690 in the p...
The objective of this work is to provide a better understanding of the role of grain boundary chemis...
SCC susceptibility of Alloy 600 in deaerated water at 360 C (statically loaded U-bend specimens) is ...
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to...
The primary water stress corrosion cracking (PWSCC) of Alloy 600 in a PWR has been reported in the c...
The primary water stress corrosion cracking (PWSCC) of Alloy 600 in a PWR has been reported in the c...
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to...
The roles of carbon and grain boundary carbides on the creep and cracking behaviors of controlled pu...
Cold-work has been associated with the occurrence of intergranular cracking of stainless steels empl...
Nickel base alloys 600 and 690 have found widespread applications in nuclear reactor steam generator...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...
The susceptibility to stress corrosion cracking (SCC) of hot-rolled AZ31 Mg alloy sheets with differ...
The mitigating effect introduced by intergranular Cr carbides on the stress corrosion cracking propa...
The nature of intergranular stress corrosion cracking (SCC) of alloy X-750 was characterized in low-...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
This work aims to study the stress corrosion crack growth behavior of cold-rolled Alloy 690 in the p...