Extensive plastic deformation in the metal underneath the oxide scale in autoclave tested Zircaloy-2 was studied using transmission electron microscopy (TEM). It was concluded that the plastic deformation is created by creep during oxidation, and is not caused by surface treatment, sample preparation or cooling from autoclave temperatures. Evidence of large strains was found in the form of dislocation tangles, dis- location patches and sub-grain formation, and also indications of twinning were found. The heavily deformed layer is around a few lm thick and no obvious difference could be seen between alloys with different strength or different oxide thickness
International audienceCreep damage investigation was carried out in wrought nickel-based superalloy ...
International audienceThe creep behaviour of pre-oxidized and pre-hydrided Zircaloy-4 was investigat...
AbstractAs a cladding material used to encapsulate nuclear fuel pellets, zirconium alloys are the pr...
Extensive plastic deformation in the metal underneath the oxide scale in autoclave tested Zircaloy-2...
The metal/oxide interface region in Zircaloy-2 oxidized in autoclave was studied with transmission e...
Oxidation tests were conducted at 450 degrees C in air for Zircaloy-2 and modified alloys. The resul...
SIGLELD:3106.076(CEGB-RD/B/N--4976) / BLDSC - British Library Document Supply CentreGBUnited Kingdo
The present study deals with deformation behaviour of textured Zircaloy 2 with two dominant orientat...
The uniaxial stress-strain behavior of Zircaloy-2 and -4, Zircaloy-oxygen alloys with a uniform oxyg...
Two varieties of Zircaloy-2, with different second phase particle (SPP) size distributions and diffe...
Zirconium alloys are widely used in nuclear reactors as fuel cladding tubes because of their low the...
The oxide scale growth in high temperature oxidation leads to generation of stresses in the oxide/me...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
The uniaxial stress-strain behavior of Zircaloy-2 and -4, Zircaloy-oxygen alloys with a uniform oxyg...
Two varieties of Zircaloy-2, with different second phase particle (SPP) size distributions and diffe...
International audienceCreep damage investigation was carried out in wrought nickel-based superalloy ...
International audienceThe creep behaviour of pre-oxidized and pre-hydrided Zircaloy-4 was investigat...
AbstractAs a cladding material used to encapsulate nuclear fuel pellets, zirconium alloys are the pr...
Extensive plastic deformation in the metal underneath the oxide scale in autoclave tested Zircaloy-2...
The metal/oxide interface region in Zircaloy-2 oxidized in autoclave was studied with transmission e...
Oxidation tests were conducted at 450 degrees C in air for Zircaloy-2 and modified alloys. The resul...
SIGLELD:3106.076(CEGB-RD/B/N--4976) / BLDSC - British Library Document Supply CentreGBUnited Kingdo
The present study deals with deformation behaviour of textured Zircaloy 2 with two dominant orientat...
The uniaxial stress-strain behavior of Zircaloy-2 and -4, Zircaloy-oxygen alloys with a uniform oxyg...
Two varieties of Zircaloy-2, with different second phase particle (SPP) size distributions and diffe...
Zirconium alloys are widely used in nuclear reactors as fuel cladding tubes because of their low the...
The oxide scale growth in high temperature oxidation leads to generation of stresses in the oxide/me...
AbstractPressurised and boiling water reactors contain zirconium alloys, which are used as nuclear f...
The uniaxial stress-strain behavior of Zircaloy-2 and -4, Zircaloy-oxygen alloys with a uniform oxyg...
Two varieties of Zircaloy-2, with different second phase particle (SPP) size distributions and diffe...
International audienceCreep damage investigation was carried out in wrought nickel-based superalloy ...
International audienceThe creep behaviour of pre-oxidized and pre-hydrided Zircaloy-4 was investigat...
AbstractAs a cladding material used to encapsulate nuclear fuel pellets, zirconium alloys are the pr...