International audienceOxidation of Alloy 690 in PWR primary water conditions has been investigated, considering particularly the role played by subsurface structural defects. To simulate a defective surface state, Xe implantation has been set up on samples. Corrosion experiments were thereafter performed in a corrosion loop simulating the PWR medium with durations between 24 h and 1000 h. Microstructural observations and NRA measurements underlined the role played by defects on the crystallinity of the continuous oxide spinel layer, on the nucleation of Cr2O3 nodules and on the oxidation rate. The higher defects concentration seemed to modify the oxygen diffusion in the oxide scale
The exposure in high-temperature water (300–360°C) of Alloy 600 is known to induce not only generali...
International audienceTo date, nickel-base welds 182 and 82 used in pressurised water reactors have ...
La prévision de la durée de vie des composants des centrales REP, en particulier les générateurs de ...
International audienceOxidation of Alloy 690 in PWR primary water conditions has been investigated, ...
Two Ni-Fe-Cr ternary alloys have been oxidized in simulated pressurized water reactor primary water ...
International audienceThe oxide film formed on nickel-based alloys in Pressurized Water Reactors (PW...
International audienceOxidation mechanism of Alloy 690 has been investigated in Pressurised Water Re...
International audienceThe generalised corrosion of Ni-base alloys exposed to pressurized water react...
International audiencehe oxide film formed on nickel-based alloys in pressurized water reactors (PWR...
Ni–Fe–Cr alloys are expected to be a candidate material for the generation IV nuclear reactors that ...
To get a better understanding of oxidation behavior of Ni-base alloys in PWR primary water, a numeri...
In France, nickel base alloys, such as alloy 600 and alloy 690, are the materials constituting steam...
International audienceThis overview of stress corrosion cracking (SCC) of nickel base alloys in pres...
The exposure in high-temperature water (300–360°C) of Alloy 600 is known to induce not only generali...
International audienceTo date, nickel-base welds 182 and 82 used in pressurised water reactors have ...
La prévision de la durée de vie des composants des centrales REP, en particulier les générateurs de ...
International audienceOxidation of Alloy 690 in PWR primary water conditions has been investigated, ...
Two Ni-Fe-Cr ternary alloys have been oxidized in simulated pressurized water reactor primary water ...
International audienceThe oxide film formed on nickel-based alloys in Pressurized Water Reactors (PW...
International audienceOxidation mechanism of Alloy 690 has been investigated in Pressurised Water Re...
International audienceThe generalised corrosion of Ni-base alloys exposed to pressurized water react...
International audiencehe oxide film formed on nickel-based alloys in pressurized water reactors (PWR...
Ni–Fe–Cr alloys are expected to be a candidate material for the generation IV nuclear reactors that ...
To get a better understanding of oxidation behavior of Ni-base alloys in PWR primary water, a numeri...
In France, nickel base alloys, such as alloy 600 and alloy 690, are the materials constituting steam...
International audienceThis overview of stress corrosion cracking (SCC) of nickel base alloys in pres...
The exposure in high-temperature water (300–360°C) of Alloy 600 is known to induce not only generali...
International audienceTo date, nickel-base welds 182 and 82 used in pressurised water reactors have ...
La prévision de la durée de vie des composants des centrales REP, en particulier les générateurs de ...