Ni-based superalloys, such as alloy 263, have excellent creep strength at high temperatures due to precipitation of gamma prime. Therefore they are candidate materials for thick section components as well as tubing in advanced ultra-supercritical (A-USC) power plants where temperatures exceed 700 °C. Because of the lower thermal expansion coefficient the Ni-based superalloys are less prone to thermal fatigue damage than the austenitic stainless steels. A series of creep-fatigue (CF) and low cycle fatigue (LCF) tests have been performed in order to study the effect of the test temperature, hold time, total strain range and a pre-creep exposure of 178MPa / 3000h / 750ºC on the creep-fatigue life of alloy 263. All LCF and CF tests were per-for...
Abstract: The creep properties derived from stress relaxation tests are compared to those from creep...
The service life of Generation IV nuclear reactors is seeking to increase to 60+ years. With increas...
The Very High Temperature Reactor (VHTR) is one of the Gen-IV reactor design concepts which embody a...
Ni-based superalloys, such as alloy 263, have excellent creep strength at high temperatures due to p...
Ni-based superalloys, such as alloy 263, have excellent creep strength at high temperatures due to p...
In this paper the creep-fatigue (CF) and low cycle fatigue (LCF) properties of alloy 263 are conside...
Strain-controlled continuous fatigue and creep–fatigue tests were carried out at 700 °C and 800 °C o...
This paper presents the high-temperature creep-fatigue testing of a Ni-based superalloy of Alloy 617...
Most engineering components used in gas/steam turbines are exposed to a range of complex loading con...
The Very High Temperature Reactor (VHTR) is one of the Gen-IV reactor design concepts which embody a...
AbstractLow cycle fatigue (LCF) and fatigue-creep tests were conducted under different dwell conditi...
Ni-base superalloys are employed as structural materials for the most critical hot gas path componen...
The thesis is focused on clarifying fatigue damage mechanisms and fatigue-creep damage mechanisms of...
The study deals with the interaction of creep and high cycle fatigue of cast polycrystalline nickel-...
In gas turbine engines for aerospace propulsion, the assessment of the fatigue damage mechanisms due...
Abstract: The creep properties derived from stress relaxation tests are compared to those from creep...
The service life of Generation IV nuclear reactors is seeking to increase to 60+ years. With increas...
The Very High Temperature Reactor (VHTR) is one of the Gen-IV reactor design concepts which embody a...
Ni-based superalloys, such as alloy 263, have excellent creep strength at high temperatures due to p...
Ni-based superalloys, such as alloy 263, have excellent creep strength at high temperatures due to p...
In this paper the creep-fatigue (CF) and low cycle fatigue (LCF) properties of alloy 263 are conside...
Strain-controlled continuous fatigue and creep–fatigue tests were carried out at 700 °C and 800 °C o...
This paper presents the high-temperature creep-fatigue testing of a Ni-based superalloy of Alloy 617...
Most engineering components used in gas/steam turbines are exposed to a range of complex loading con...
The Very High Temperature Reactor (VHTR) is one of the Gen-IV reactor design concepts which embody a...
AbstractLow cycle fatigue (LCF) and fatigue-creep tests were conducted under different dwell conditi...
Ni-base superalloys are employed as structural materials for the most critical hot gas path componen...
The thesis is focused on clarifying fatigue damage mechanisms and fatigue-creep damage mechanisms of...
The study deals with the interaction of creep and high cycle fatigue of cast polycrystalline nickel-...
In gas turbine engines for aerospace propulsion, the assessment of the fatigue damage mechanisms due...
Abstract: The creep properties derived from stress relaxation tests are compared to those from creep...
The service life of Generation IV nuclear reactors is seeking to increase to 60+ years. With increas...
The Very High Temperature Reactor (VHTR) is one of the Gen-IV reactor design concepts which embody a...