International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stress corrosion cracking behaviour in simulated Pressurized Water Reactor (PWR) primary water has been investigated. A-286 microstructure was characterized by transmission electron microscopy for ageing heat treatments at 670 °C and 720 °C for durations ranging from 5 h to 100 h. Spherical $\gamma$′ phase with mean diameters ranging from 4.6 to 9.6 nm and densities ranging from 8.5 × 10$^{22}$ m$^{−3}$ to 2 × 10$^{23}$ m$^{−3}$ were measured. Results suggest that both the $\gamma$′ phase mean diameter and density quickly saturate with time for ageing heat treatment at 720 °C while the $\gamma$′ mean diameter increases significantly up to 100 h fo...
In present study, effects of thermal aging and triaxial stress were investigated in terms of primary...
Over the last thirty years, stress corrosion cracking in PWR primary water (PWSCC) has been observed...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
In modern pressurized water reactors (PWR), the substitution of nickel-base Alloy 600 and its associ...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
Alloy 690 is used in critical components of nuclear power systems. It has a high intergranular stres...
Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal ...
Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to pro...
Thermal aging and consequent embrittlement of materials are ongoing issues in cast and duplex stainl...
International audienceStress corrosion cracking (SCC) of wrought alloy 600 and parent weld metals (a...
Thermal ageing promotes intergranular carbide precipitation and atomic ordering reaction in most com...
The negative influence of δ phase on the intergranular stress corrosion cracking (IGSCC) resistance ...
Alloy 690 was developed to improve the corrosion resistance of components in nuclear power systems s...
In present study, effects of thermal aging and triaxial stress were investigated in terms of primary...
Over the last thirty years, stress corrosion cracking in PWR primary water (PWSCC) has been observed...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
International audienceThe influence of ageing heat treatment on alloy A-286 microstructure and stres...
In modern pressurized water reactors (PWR), the substitution of nickel-base Alloy 600 and its associ...
The stress corrosion cracking (SCC) of three Alloy 600 has been studied in the simulated primary wat...
Alloy 690 is used in critical components of nuclear power systems. It has a high intergranular stres...
Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal ...
Thermal ageing of Alloy 690 triggers an intergranular (IG) carbide precipitation and is known to pro...
Thermal aging and consequent embrittlement of materials are ongoing issues in cast and duplex stainl...
International audienceStress corrosion cracking (SCC) of wrought alloy 600 and parent weld metals (a...
Thermal ageing promotes intergranular carbide precipitation and atomic ordering reaction in most com...
The negative influence of δ phase on the intergranular stress corrosion cracking (IGSCC) resistance ...
Alloy 690 was developed to improve the corrosion resistance of components in nuclear power systems s...
In present study, effects of thermal aging and triaxial stress were investigated in terms of primary...
Over the last thirty years, stress corrosion cracking in PWR primary water (PWSCC) has been observed...
Austenitic alloys have been extensively used in the nuclear industry as structural components due to...