AbstractCreep behavior of U−6%Zr alloy was studied in the temperature range 550−650°C using impression creep technique. Creep curves at 575°C for various stresses are not smooth and exhibited some waviness. Sometimes creep curves show a sudden penetration of the punch which is followed by decrease in impression depth with time. The punching stress versus creep rate data for the above temperature also show a random behaviour. A detailed microstructural investigation was carried out with the help of SEM and EDX to understand this phenomenon. At creep testing temperature, δ-UZr2 phase continuously forms and it takes very long time to complete the reaction. Hence, the reason for waviness may be due to the formation of δ-phase coming out from th...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
International audienceASTRID is a fast-reactor prototype for the 4th generation of nuclear power pla...
Investigate creep behavior of Zr-based cladding tubes with attention to basic creep mechanisms and t...
Low-stress creep behaviour of a two-phase Zr-2.5%Nb alloy, differently heat treated, has been invest...
Tensile creep behavior of the Zr-2.5Nb alloy has been studied through tests under constant load (str...
In this work, a crystallographic thermal creep model is proposed for Zr alloys that accounts for the...
International audienceZirconium alloys are widely used in the nuclear industry. Several components, ...
The creep behavior of Zr-2.5Nb alloy has been studied in the temperature range of 350–450 °C and str...
Zirconium alloy tubing is used in pressurized water nuclear reactors in order to prevent fissile mat...
Three phase Mo-9Si-8B (at.%) alloys are a prominent example for a potential new high temperature str...
This paper presents experimental data regarding creep behaviour of a Zr-1 wt% Nb alloy at elevated (...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
Alloy 617, a nickel‑based alloy, is a leading candidate for application in next‑generation nuclear p...
Uranium-10 wt % zirconium (U-10Zr) is a fuel alloy that has been used in the Experimental Breeder Re...
In order to examine the impact of anisotropy in creep deformation of the zirconium alloy clad in pre...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
International audienceASTRID is a fast-reactor prototype for the 4th generation of nuclear power pla...
Investigate creep behavior of Zr-based cladding tubes with attention to basic creep mechanisms and t...
Low-stress creep behaviour of a two-phase Zr-2.5%Nb alloy, differently heat treated, has been invest...
Tensile creep behavior of the Zr-2.5Nb alloy has been studied through tests under constant load (str...
In this work, a crystallographic thermal creep model is proposed for Zr alloys that accounts for the...
International audienceZirconium alloys are widely used in the nuclear industry. Several components, ...
The creep behavior of Zr-2.5Nb alloy has been studied in the temperature range of 350–450 °C and str...
Zirconium alloy tubing is used in pressurized water nuclear reactors in order to prevent fissile mat...
Three phase Mo-9Si-8B (at.%) alloys are a prominent example for a potential new high temperature str...
This paper presents experimental data regarding creep behaviour of a Zr-1 wt% Nb alloy at elevated (...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
Alloy 617, a nickel‑based alloy, is a leading candidate for application in next‑generation nuclear p...
Uranium-10 wt % zirconium (U-10Zr) is a fuel alloy that has been used in the Experimental Breeder Re...
In order to examine the impact of anisotropy in creep deformation of the zirconium alloy clad in pre...
The creep model for Zircaloy-4 has been improved by including the metallurgical effect of Zircaloy c...
International audienceASTRID is a fast-reactor prototype for the 4th generation of nuclear power pla...
Investigate creep behavior of Zr-based cladding tubes with attention to basic creep mechanisms and t...