Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel cladding and guide tubes because they have excellent corrosion and radiation-resistant properties. In the reactor core, zirconium alloys are subjected to high-energy neutron fluence, causing radiation-induced dislocation and growth. To discern a possible correlation between radiation-induced dislocation and growth, characteristics of dislocation and growth in zirconium and its alloys are examined. The radiation-induced dislocation including <a> and <c> dislocation loops is reviewed in various temperature and fluence ranges, and their growth behavior is examined in the same way. To further a fundamental understanding, radiation-induced g...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
The objective of this study is irradiation growth modeling of polycrystal zirconium using the advanc...
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel claddi...
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel claddi...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
Due to their low neutron absorption cross-section and good corrosion properties, zirconium and its a...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
This work is based on our reaction-diffusion model of radiation growth of Zr-based materials propose...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
In this chapter, the effects of neutron irradiation on zirconium alloys are described. Irradiation e...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
The objective of this study is irradiation growth modeling of polycrystal zirconium using the advanc...
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel claddi...
Zirconium and zirconium alloys are widely used as nuclear reactor core materials such as fuel claddi...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
Due to their low neutron absorption cross-section and good corrosion properties, zirconium and its a...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
This work is based on our reaction-diffusion model of radiation growth of Zr-based materials propose...
Zirconium in the Nuclear Industry: 15th International Symposium. ASTM International, ASTM STPInterna...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
In this chapter, the effects of neutron irradiation on zirconium alloys are described. Irradiation e...
AbstractZirconium alloys are widely used in nuclear reactors as structural materials. During the ope...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
International audienceRecrystallized zirconium alloys are used as nuclear fuel cladding tubes of Pre...
The objective of this study is irradiation growth modeling of polycrystal zirconium using the advanc...