Strain-controlled fatigue tests have been conducted in impure helium, simulating the primary-circuit coolant of a high temperature gas-cooled reactor to ascertain the influence of strain rate ( ε=4 × 10-3 to 2 × 10-5 s-1), hold condition at peak strains (tension-only, compression-only and tension-plus-compression holds) and hold time (up to 120 min) on the low cycle fatigue behaviour of Inconel 617. A strain range of 0.6% and a temperature of 950°C were employed for all the tests. Microstructural changes which occurred during fatigue deformation were evaluated and damage mechanisms which influence fatigue life identified. A small reduction in fatigue life was found with decreasing ε. Irrespective of the position of...
In this study, we comparatively investigate the low cycle fatigue behavior of Alloy 617 (INCONEL 617...
The effect of strain range and temperature on the low-cycle fatigue behaviour and microstructure cha...
Advanced materials are a critical element in the development of advanced sodium-cooled fast reactors...
Strain-controlled fatigue tests have been conducted in impure helium, simulating the primary-circuit...
Alloy 617 is the one of the leading candidate materials for Intermediate Heat eXchangers (IHX) of a ...
Strain-controlled continuous fatigue and creep–fatigue tests were carried out at 700 °C and 800 °C o...
Our research on fatigue performance of stainless steel and transferability of laboratory data to nuc...
International audienceCyclic tests with or without tensile holding periods were conducted in air at ...
It is well known in energy systems that the creep lifetime of high temperature alloys is significant...
The current study was an attempt to evaluate the high cycle fatigue strength of Incoloy 800H in a Hi...
In PVP2011-57942 we reported improved endurance in fatigue tests with intermediate annealing to roug...
Improved endurance in fatigue tests with intermediate holds and annealing to roughly simulate steady...
The superimposition of time-dependent damage on fatigue, otherwise, known as creep-fatigue interacti...
Isothermal low-cycle fatigue tests on Inconel 625 were conducted at 650 and 815\ub0C under continuou...
The service conditions expected for the GEN IV reactors pose significant challenges to structural ma...
In this study, we comparatively investigate the low cycle fatigue behavior of Alloy 617 (INCONEL 617...
The effect of strain range and temperature on the low-cycle fatigue behaviour and microstructure cha...
Advanced materials are a critical element in the development of advanced sodium-cooled fast reactors...
Strain-controlled fatigue tests have been conducted in impure helium, simulating the primary-circuit...
Alloy 617 is the one of the leading candidate materials for Intermediate Heat eXchangers (IHX) of a ...
Strain-controlled continuous fatigue and creep–fatigue tests were carried out at 700 °C and 800 °C o...
Our research on fatigue performance of stainless steel and transferability of laboratory data to nuc...
International audienceCyclic tests with or without tensile holding periods were conducted in air at ...
It is well known in energy systems that the creep lifetime of high temperature alloys is significant...
The current study was an attempt to evaluate the high cycle fatigue strength of Incoloy 800H in a Hi...
In PVP2011-57942 we reported improved endurance in fatigue tests with intermediate annealing to roug...
Improved endurance in fatigue tests with intermediate holds and annealing to roughly simulate steady...
The superimposition of time-dependent damage on fatigue, otherwise, known as creep-fatigue interacti...
Isothermal low-cycle fatigue tests on Inconel 625 were conducted at 650 and 815\ub0C under continuou...
The service conditions expected for the GEN IV reactors pose significant challenges to structural ma...
In this study, we comparatively investigate the low cycle fatigue behavior of Alloy 617 (INCONEL 617...
The effect of strain range and temperature on the low-cycle fatigue behaviour and microstructure cha...
Advanced materials are a critical element in the development of advanced sodium-cooled fast reactors...