Department of Nuclear EngineeringAs the design life of nuclear power plants approaches, continued operation of nuclear power plants is emerging as a problem. For long-term operations, it is imperative that the safety should be guaranteed first. To this end, we need to be able to understand the underlying mechanisms of material degradation to predict the degradation of the components of nuclear power plants. The nickel based alloys are pivotal structural materials used in nuclear industry because of corrosion resistance and mechanical properties that tolerate harsh and extreme environments. However, nickel based alloys undergo stress corrosion cracking (SCC) in high-temperature high-pressure environments. Stress corrosion cracking is a gene...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1987.Bibliogra...
La prévision de la durée de vie des composants des centrales REP, en particulier les générateurs de ...
The exposure in high-temperature water (300–360°C) of Alloy 600 is known to induce not only generali...
Ni–Fe–Cr alloys are expected to be a candidate material for the generation IV nuclear reactors that ...
International audienceThis overview of stress corrosion cracking (SCC) of nickel base alloys in pres...
Stress corrosion cracking (SCC) of Ni-Fe-Cr alloys and weld metals was investigated in simulated env...
International audienceTo date, nickel-base welds 182 and 82 used in pressurised water reactors have ...
International audienceThe stress corrosion cracking behaviour of two nickel base superalloys (A718 a...
Nickel is the main component in nickel-based superalloys which are known for their superior corrosio...
International audienceCorrosion and material sciences face challenges which involved and still need ...
International audienceOxidation of Alloy 690 in PWR primary water conditions has been investigated, ...
Les métaux déposés base nickel sont utilisés pour assembler des composants du circuit primaire des c...
Two Ni-Fe-Cr ternary alloys have been oxidized in simulated pressurized water reactor primary water ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1987.Bibliogra...
La prévision de la durée de vie des composants des centrales REP, en particulier les générateurs de ...
The exposure in high-temperature water (300–360°C) of Alloy 600 is known to induce not only generali...
Ni–Fe–Cr alloys are expected to be a candidate material for the generation IV nuclear reactors that ...
International audienceThis overview of stress corrosion cracking (SCC) of nickel base alloys in pres...
Stress corrosion cracking (SCC) of Ni-Fe-Cr alloys and weld metals was investigated in simulated env...
International audienceTo date, nickel-base welds 182 and 82 used in pressurised water reactors have ...
International audienceThe stress corrosion cracking behaviour of two nickel base superalloys (A718 a...
Nickel is the main component in nickel-based superalloys which are known for their superior corrosio...
International audienceCorrosion and material sciences face challenges which involved and still need ...
International audienceOxidation of Alloy 690 in PWR primary water conditions has been investigated, ...
Les métaux déposés base nickel sont utilisés pour assembler des composants du circuit primaire des c...
Two Ni-Fe-Cr ternary alloys have been oxidized in simulated pressurized water reactor primary water ...
Thesis (Ph. D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1987.Bibliogra...
La prévision de la durée de vie des composants des centrales REP, en particulier les générateurs de ...
The exposure in high-temperature water (300–360°C) of Alloy 600 is known to induce not only generali...