Solute segregation in the carbon-depleted (CDZ) heat-affected zone of dissimilar metal welds (DMW) designed for nuclear power plant EPR TM reactors has been investigated by atom probe tomography (APT) and related to the mechanical properties (toughness test). The analysis of grain boundaries (GBs) by APT allowed the quantification of the P segregation and other solute elements, in all the analyzed samples, before and after long-term ageing heat treatments. The post-weld stress-relief heat treatment applied to the samples before the ageing heat treatments leads to important GBs segregation levels. Following thermal ageing treatments allow a relative increase of GB segregation. P segregation increases with the various thermal ageing condition...
Atom probe field ion microscopy (APFIM) investigations of the microstructure of unaged (as-fabricate...
International audienceIn ferrite/austenite dissimilar metal welds, carbon can diffuse from the ferri...
The mechanical properties of reactor pressure vessel (RPV) steels are known to degrade during operat...
In this study, microstructural and mechanical characterizations were performed to investigate the ef...
To investigate the effect of long-term thermal aging on the fusion boundary region between low-alloy...
In Pressurised Water Reactors, the reactor pressure vessel (RPV) is considered a life limiting compo...
Radiation induced clustering and precipitation affect the mechanical properties of the reactor press...
Dissimilar metal welds (DMWs) are a key design feature in nuclear power systems, typically involving...
In order to investigate the long-term thermal aging effects on the type-II boundary region in Alloy ...
Lath boundaries in a maraging stainless steel of composition 13Cr-8Ni-2Mo-2Cu-1Ti-0.7Al-0.3Mn-0.2Si-...
A narrow-gap SA508/Alloy 52 dissimilar metal weld (DMW) mock-up, fully representative of an actual n...
Radiation induced clustering affects the mechanical properties, that is the ductile to brittle trans...
In this study, the metallurgical analysis and mechanical property measurement have been performed to...
International audienceIntergranular segregation in a Fe-P-C model alloy after thermal ageing at 650°...
Reactor pressure vessel steel welds are affected by irradiation during operation. The irradiation re...
Atom probe field ion microscopy (APFIM) investigations of the microstructure of unaged (as-fabricate...
International audienceIn ferrite/austenite dissimilar metal welds, carbon can diffuse from the ferri...
The mechanical properties of reactor pressure vessel (RPV) steels are known to degrade during operat...
In this study, microstructural and mechanical characterizations were performed to investigate the ef...
To investigate the effect of long-term thermal aging on the fusion boundary region between low-alloy...
In Pressurised Water Reactors, the reactor pressure vessel (RPV) is considered a life limiting compo...
Radiation induced clustering and precipitation affect the mechanical properties of the reactor press...
Dissimilar metal welds (DMWs) are a key design feature in nuclear power systems, typically involving...
In order to investigate the long-term thermal aging effects on the type-II boundary region in Alloy ...
Lath boundaries in a maraging stainless steel of composition 13Cr-8Ni-2Mo-2Cu-1Ti-0.7Al-0.3Mn-0.2Si-...
A narrow-gap SA508/Alloy 52 dissimilar metal weld (DMW) mock-up, fully representative of an actual n...
Radiation induced clustering affects the mechanical properties, that is the ductile to brittle trans...
In this study, the metallurgical analysis and mechanical property measurement have been performed to...
International audienceIntergranular segregation in a Fe-P-C model alloy after thermal ageing at 650°...
Reactor pressure vessel steel welds are affected by irradiation during operation. The irradiation re...
Atom probe field ion microscopy (APFIM) investigations of the microstructure of unaged (as-fabricate...
International audienceIn ferrite/austenite dissimilar metal welds, carbon can diffuse from the ferri...
The mechanical properties of reactor pressure vessel (RPV) steels are known to degrade during operat...