In this chapter, the effects of neutron irradiation on zirconium alloys are described. Irradiation effects on the microstructure are first discussed, describing damage creation, point-defect evolution leading to loop formation and also secondary-phase evolution and alloying elements redistribution under irradiation. Then, in the second part, irradiation effects on postirradiation mechanical behavior and deformation mechanisms, especially during tensile test and also after postirradiation thermal treatment or postirradiation creep tests, are given. Finally, the in-reactor deformation behavior, growth, and irradiation creep, as well as the related deformation mechanisms, are analyzed
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
This work is based on our reaction-diffusion model of radiation growth of Zr-based materials propose...
The effects of fast flux (E greater than or equal to 1 MeV) neutrons on zirconium and dilute zirconi...
International audienceNeutron radiation induces important changes in the mechanical behavior of recr...
International audienceNeutron radiation induces important changes in the mechanical behavior of recr...
International audienceNeutron radiation induces important changes in the mechanical behavior of recr...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel claddi...
Au sein des Réacteurs à Eau Pressurisée, le flux de neutrons entraîne une modification des propriété...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
This work is based on our reaction-diffusion model of radiation growth of Zr-based materials propose...
The effects of fast flux (E greater than or equal to 1 MeV) neutrons on zirconium and dilute zirconi...
International audienceNeutron radiation induces important changes in the mechanical behavior of recr...
International audienceNeutron radiation induces important changes in the mechanical behavior of recr...
International audienceNeutron radiation induces important changes in the mechanical behavior of recr...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel claddi...
Au sein des Réacteurs à Eau Pressurisée, le flux de neutrons entraîne une modification des propriété...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
Symposium held in Manchester, United KingdomInternational audienceZirconium alloys, used in the nucl...
This work is based on our reaction-diffusion model of radiation growth of Zr-based materials propose...