Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to promote an ordering reaction causing lattice contraction. It may affect the long-term primary water stress corrosion cracking (PWSCC) resistance of pressurized water reactor (PWR) components. Four conditions of Alloy 690 (solution annealed, cold-rolled and/or heat-treated) were aged between 350 and 550 °C for 10 000 h and characterized. Although no direct observation of ordering was made, variations in hardness and lattice parameter were attributed to the formation of short-range ordering (SRO) in all conditions with a peak level at 420 °C, consistent with the literature. Prior heat treatment induced ordering before thermal ageing. At higher tem...
SCC susceptibility of Alloy 600 in deaerated water at 360 C (statically loaded U-bend specimens) is ...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...
Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to pro...
Alloy 690 is used in critical components of nuclear power systems. It has a high intergranular stres...
Thermal ageing promotes intergranular carbide precipitation and atomic ordering reaction in most com...
In modern pressurized water reactors (PWR), the substitution of nickel-base Alloy 600 and its associ...
Alloy 690 was developed to improve the corrosion resistance of components in nuclear power systems s...
Thermally treated nickel-based Alloy 690 is the material of choice for the steam generator tubes of ...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
The intergranular carbide precipitation behavior and its effect on the tensile properties were inves...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal ...
Alloy 690 is a high-chromium nickel-base alloy used in various primary coolant system components and...
Alloy 625 is widely used for petrochemical, marine and aerospace applications owing to its outstandi...
SCC susceptibility of Alloy 600 in deaerated water at 360 C (statically loaded U-bend specimens) is ...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...
Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to pro...
Alloy 690 is used in critical components of nuclear power systems. It has a high intergranular stres...
Thermal ageing promotes intergranular carbide precipitation and atomic ordering reaction in most com...
In modern pressurized water reactors (PWR), the substitution of nickel-base Alloy 600 and its associ...
Alloy 690 was developed to improve the corrosion resistance of components in nuclear power systems s...
Thermally treated nickel-based Alloy 690 is the material of choice for the steam generator tubes of ...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
The intergranular carbide precipitation behavior and its effect on the tensile properties were inves...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal ...
Alloy 690 is a high-chromium nickel-base alloy used in various primary coolant system components and...
Alloy 625 is widely used for petrochemical, marine and aerospace applications owing to its outstandi...
SCC susceptibility of Alloy 600 in deaerated water at 360 C (statically loaded U-bend specimens) is ...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...