AbstractIn this paper results of the characterization by SEM and TEM of Zr-1wt% Nb-0, 05wt% Fe with 200ppm of hydrogen are presented, as well as the results of tensile tests at 300°C and room temperature to determine the pre-irradiation yield stress and ductility. The results are compared with hydrided Zr-2,5wt% Nb with the same heat treatments
Zirconium alloys have greater applicability in the nuclear industry are used in the manufacture of t...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
AbstractIn this paper results of the characterization by SEM and TEM of Zr-1wt% Nb-0, 05wt% Fe with ...
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and...
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and...
<div><p>The purpose of this study was to investigate the kinetics of hydrogen absorption and hydride...
Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water...
Zirconium based alloys are commonly used as material for fuel claddings in the light water reactors....
Due to their low thermal neutron capture cross-section, adequate mechanical strength and high corros...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
Zircaloy-4 is a zirconium alloy that will be used for construction of many of the core components in...
Influence of hydrogen content on the impact toughness of Zr-2.5% Nb alloy was examined by carrying o...
International audienceThe influence of a hydrogen concentration gradient at the crack-tip and hydrid...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
Zirconium alloys have greater applicability in the nuclear industry are used in the manufacture of t...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
AbstractIn this paper results of the characterization by SEM and TEM of Zr-1wt% Nb-0, 05wt% Fe with ...
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and...
Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and...
<div><p>The purpose of this study was to investigate the kinetics of hydrogen absorption and hydride...
Zirconium alloys are being commonly used as a material of choice for nuclear fuel claddings in water...
Zirconium based alloys are commonly used as material for fuel claddings in the light water reactors....
Due to their low thermal neutron capture cross-section, adequate mechanical strength and high corros...
Spent nuclear fuel claddings discharged from water reactors contain hydrogen up to 800 wppm dependin...
Zircaloy-4 is a zirconium alloy that will be used for construction of many of the core components in...
Influence of hydrogen content on the impact toughness of Zr-2.5% Nb alloy was examined by carrying o...
International audienceThe influence of a hydrogen concentration gradient at the crack-tip and hydrid...
A series of simulated reactivity-initiated accident (RIA) tests on irradiated fully recrystallized b...
Zirconium alloys have greater applicability in the nuclear industry are used in the manufacture of t...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...
International audienceThe anisotropic plastic behavior and the fracture of as-received and hydrided ...