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Showing 1 to 10 of 10 for “"Alloy 617"”.
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High temperature creep-fatigue behavior of alloy 617 and alloy 230
… applications. Currently, Ni-based superalloy alloy 617 (Inconel 617) and alloy 230 (Haynes 230) are considered as the leading metallic candidate materials for applications in the VHTR because of their favorable mechanical properties at elevated temperatures. The major damage mechanism …
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Effect of oxygen potential on high temperature crack growth in alloy 617
… oxygen partial pressure on crack growth rates in Alloy 617 has been studied using both static and fatigue loading at 650°C. Tests were conducted at a constant stress intensity factor, K, for static loading conditions or constant AK for fatigue loading using a direct current potential drop …
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Behavior of alloy 617 at 650°C in low oxygen pressure environments
The behavior of alloy 617 at 650°C in low oxygen partial pressure environments has been studied under static loading. Of particular interest was the crack growth rate in these conditions. For that, tests were conducted at a constant stress intensity factor of 49.45 MPa'm (45 ksidinch) using a …
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High temperature aging study on long-term aged Alloy 617 and Alloy 230
Alloy 617 and Alloy 230 are lead structural materials for next generation nuclear power plant (NGNP). Both alloys possess good corrosion resistance and exceptional high-temperature strength. In order to gain a better understanding of the high-temperature degradation process of these materials, …
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Kinetic Property and SS 316/Alloy 617 Corrosion Study in Molten Chloride and Fluoride Salts
… studies of structural materials (SS 316H and Alloy 617), including static corrosion and galvanic corrosion, in molten MgCl2-NaCl-KCl and/or NaF-KF-UF4-UF3 salts in a temperature range of 600 to 800C. The study applied the semi-differential (SD) analysis method and innovative fitting method …
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Oxidation behavior of very high temperature reactor (VHTR) candidate materials: 316l stainless steel, Alloy 617, and Incoloy-800H
High temperature nuclear reactors require alloys to perform well at temperatures around 1000 to 1400 K. The oxidation behavior of three high temperature reactor candidate materials, 316 L stainless steel, alloy 617, and Incoloy 800-H under different conditions were investigated in the present work. …
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Calibration of empirical, semi-empirical, and physics-based material models for the prediction of creep and tensile behaviour of Alloy 617
… in predicting the creep and tensile behaviour of Alloy 617 across three studies of increasing model fidelity. The first study calibrates twelve empirical models and applies symbolic regression (SR) to discover constitutive expressions for elevated-temperature creep behaviour. In general, the …
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High temperature creep behavior of Inconel 617 and Haynes 230
… life of 60 years. Currently, Ni-based Inconel 617 (Alloy 617) and Haynes 230 (Alloy 230) are considered to be the leading metallic candidate materials for applications in the HTGR due to their favorable mechanical properties at high temperatures. In the present study, focus is placed on the …
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Surface degradation and creep of Inconel 617 and Haynes 230 at high temperatures
… an environmental degradation of high temperature alloys used for internals and heat exchangers. Depending on the impurity concentration and the temperature, the materials can undergo oxidation, carburization and decarburization, which can be detrimental to the mechanical behavior of the materials. …
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Microstructural evolution and mechanical behavior in nickel based alloys for very high temperature reactor
… resistance. Among candidate materials, Alloy 617 and Alloy 230 are considered the most promising structural materials for the VHTR. In order to gain a better understanding of material performance during a high-temperature and long-term service life, various material tests and experiments …