TY - JOUR
T1 - Investigation of thermal aging effects on the tensile properties of Alloy 617 by in-situ synchrotron wide-angle X-ray scattering
AU - Liu, Xiang
AU - Mo, Kun
AU - Miao, Yinbin
AU - Lan, Kuan Che
AU - Zhang, Guangming
AU - Chen, Wei Ying
AU - Tomchik, Carolyn
AU - Seibert, Rachel
AU - Terry, Jeff
AU - Stubbins, James F.
N1 - Publisher Copyright:
© 2015 Elsevier B.V.
PY - 2016/1/10
Y1 - 2016/1/10
N2 - The nickel-base Alloy 617 has been considered as the lead candidate structural material for the intermediate heat exchanger (IHX) of the Very-High-Temperature Reactor (VHTR). In order to assess the long-term performance of Alloy 617, thermal aging experiments up to 10,000. h in duration were performed at 1000. °C. Subsequently, in-situ synchrotron wide-angle X-ray scattering (WAXS) tensile tests were carried out at ambient temperature. M23C6 carbides were identified as the primary precipitates, while a smaller amount of M6C was also observed. The aging effects were quantified in several aspects: (1) macroscopic tensile properties, (2) volume fraction of the M23C6 phase, (3) the lattice strain evolution of both the matrix and the M23C6 precipitates, and (4) the dislocation density evolution during plastic deformation. The property-microstructure relationship is described with a focus on the evolution of the M23C6 phase. For aging up to 3000. h, the yield strength (YS) and ultimate tensile strength (UTS) showed little variation, with average values being 454. MPa and 787. MPa, respectively. At 10,000. h, the YS and UTS reduced to 380. MPa and 720. MPa, respectively. The reduction in YS and UTS is mainly due to the coarsening of the M23C6 precipitates. After long term aging, the volume fraction of the M23C6 phase reached a plateau and its maximum internal stress was reduced, implying that under large internal stresses the carbides were more susceptible to fracture or decohesion from the matrix. Finally, the calculated dislocation densities were in good agreement with transmission electron microscopy (TEM) measurements. The square roots of the dislocation densities and the true stresses displayed typical linear behavior and no significant change was observed in the alloys in different aging conditions.
AB - The nickel-base Alloy 617 has been considered as the lead candidate structural material for the intermediate heat exchanger (IHX) of the Very-High-Temperature Reactor (VHTR). In order to assess the long-term performance of Alloy 617, thermal aging experiments up to 10,000. h in duration were performed at 1000. °C. Subsequently, in-situ synchrotron wide-angle X-ray scattering (WAXS) tensile tests were carried out at ambient temperature. M23C6 carbides were identified as the primary precipitates, while a smaller amount of M6C was also observed. The aging effects were quantified in several aspects: (1) macroscopic tensile properties, (2) volume fraction of the M23C6 phase, (3) the lattice strain evolution of both the matrix and the M23C6 precipitates, and (4) the dislocation density evolution during plastic deformation. The property-microstructure relationship is described with a focus on the evolution of the M23C6 phase. For aging up to 3000. h, the yield strength (YS) and ultimate tensile strength (UTS) showed little variation, with average values being 454. MPa and 787. MPa, respectively. At 10,000. h, the YS and UTS reduced to 380. MPa and 720. MPa, respectively. The reduction in YS and UTS is mainly due to the coarsening of the M23C6 precipitates. After long term aging, the volume fraction of the M23C6 phase reached a plateau and its maximum internal stress was reduced, implying that under large internal stresses the carbides were more susceptible to fracture or decohesion from the matrix. Finally, the calculated dislocation densities were in good agreement with transmission electron microscopy (TEM) measurements. The square roots of the dislocation densities and the true stresses displayed typical linear behavior and no significant change was observed in the alloys in different aging conditions.
KW - Alloy 617
KW - High-temperature thermal aging
KW - M23C6 carbide
KW - Wide-angle X-ray scattering
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U2 - 10.1016/j.msea.2015.10.098
DO - 10.1016/j.msea.2015.10.098
M3 - Article
AN - SCOPUS:84945930068
SN - 0921-5093
VL - 651
SP - 55
EP - 62
JO - Materials Science and Engineering: A
JF - Materials Science and Engineering: A
ER -