Abstract We are undertaking a systematic study at Argonne National Laboratory to evaluate the uniaxial creep behavior of V-Cr-Ti alloys in a vacuum environment as a function of temperature in the range of 650-800°C and at applied stress levels of 75-380 MPa. Creep strain in the specimens is measured by a linear-variable-differential transducer, which is attached between the fixed and movable pull rods of the creep assembly. Strain is measured at sufficiently frequent intervals during testing to define the creep strain/time curve. A linear least-squares analysis function is used to ensure consistent extraction of minimum creep rate, onset of tertiary creep, and creep strain at the onset of tertiary creep. Creep test data, obtained at 650, 70...
International audienceWe present in this paper the creep behavior of Ti-6Al-4V from 450°C to 600°C u...
The fact that Gamma titanium aluminides (γ-TiAl) offer strong potential for replacing conventional t...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
We are undertaking a systematic study at Argonne National Laboratory to evaluate the uniaxial creep ...
Pressurized thermal creep tubes of highly purified V-4Cr-4Ti, the NIFS-Heat2 alloy have been examin...
Vanadium-base alloys are potential candidates for applications such as the first wall and other stru...
A study of irradiation creep in vanadium-base alloys is underway with experiments in the Advanced Te...
The results of experimental studies of high-temperature creep and long-term strength under condition...
One of the important criteria for selection titanium alloys for discs and blades of turbine engine c...
Microstructural examinations have been performed on irradiation-creep and thermal-creep pressurized ...
The present study mainly aims at investigating the creep response of a Ti-6Al-4V alloy produced by a...
Creep results on 2.25Cr-1Mo were obtained at 600 °C, 650 °C and 700 °C at five stress levels, under ...
Creep results on 2.25Cr-1Mo were obtained at 600 °C, 650 °C and 700 °C at five stress le...
The creep behavior at an ambient temperature of typical h.c.p., b.c.c. and f.c.c. metals and alloys ...
Creep results on 2.25Cr-1Mo were obtained at 600 °C, 650 °C and 700 °C at five stress levels, under ...
International audienceWe present in this paper the creep behavior of Ti-6Al-4V from 450°C to 600°C u...
The fact that Gamma titanium aluminides (γ-TiAl) offer strong potential for replacing conventional t...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
We are undertaking a systematic study at Argonne National Laboratory to evaluate the uniaxial creep ...
Pressurized thermal creep tubes of highly purified V-4Cr-4Ti, the NIFS-Heat2 alloy have been examin...
Vanadium-base alloys are potential candidates for applications such as the first wall and other stru...
A study of irradiation creep in vanadium-base alloys is underway with experiments in the Advanced Te...
The results of experimental studies of high-temperature creep and long-term strength under condition...
One of the important criteria for selection titanium alloys for discs and blades of turbine engine c...
Microstructural examinations have been performed on irradiation-creep and thermal-creep pressurized ...
The present study mainly aims at investigating the creep response of a Ti-6Al-4V alloy produced by a...
Creep results on 2.25Cr-1Mo were obtained at 600 °C, 650 °C and 700 °C at five stress levels, under ...
Creep results on 2.25Cr-1Mo were obtained at 600 °C, 650 °C and 700 °C at five stress le...
The creep behavior at an ambient temperature of typical h.c.p., b.c.c. and f.c.c. metals and alloys ...
Creep results on 2.25Cr-1Mo were obtained at 600 °C, 650 °C and 700 °C at five stress levels, under ...
International audienceWe present in this paper the creep behavior of Ti-6Al-4V from 450°C to 600°C u...
The fact that Gamma titanium aluminides (γ-TiAl) offer strong potential for replacing conventional t...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...