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Dive into the research topics where Wei Ying Chen is active.

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Featured researches published by Wei Ying Chen.


Philosophical Magazine | 2013

Characterization of dislocation loops in CeO2 irradiated with high energy Krypton and Xenon

Wei Ying Chen; Jianguo Wen; M. A. Kirk; Yinbin Miao; Bei Ye; Brian R. Kleinfeldt; Aaron Oaks; James F. Stubbins

In order to fully characterize the structure of dislocation loops in CeO2, ion irradiations have been performed at 800 °C on CeO2 single-crystal thin films individually using 1 MeV Kr ions and 150 keV Xe ions, both to a dose of 5 × 1014 ions/cm2. Post-irradiation TEM examination, diffraction contrast imaging and high-resolution transmission electron microscopy (HRTEM), has confirmed that the irradiation-induced dislocation loops in CeO2 were Frank loops, having an interstitial nature with {1 1 1} habit planes and a 1/3 Burgers vector. Dislocation loops were confirmed to be a stacking fault in nature through TEM observations of the interference fringes inside the loop periphery.


Environmental Degradation of Materials in Nuclear Power Systems | 2017

Crack Growth Rate and Fracture Toughness of CF3 Cast Stainless Steels at ~3 DPA

Y. Chen; Wei Ying Chen; Bogdan Alexandreanu; K. Natesan; A. S. Rao

Cast austenitic stainless steels (CASS) used in reactor core internals are subject to high-temperature coolant and energetic neutron irradiation during power operations. Due to both thermal aging and irradiation embrittlement, the long-term performance of CASS materials is of concern. To assess the cracking behavior of irradiated CASS alloys, crack growth rate (CGR) and fracture toughness J-R curve tests were performed on two CF3 alloys. Miniature compact tension specimens were irradiated to ~3 dpa, and were tested at ~315 °C in simulated LWR coolant environments with low corrosion potentials. No elevated cracking susceptibility was observed at this dose in the test environments. The power exponents of the 3 dpa J-R curves were much lower than that of unirradiated or irradiated specimens at lower doses, indicating a significant decline in fracture resistance. A preliminary microstructural study revealed irradiation-induced microstructural changes in both austenite and ferrite, suggesting an embrittlement mechanism involving both phases at this dose level.


Environmental Degradation of Materials in Nuclear Power Systems | 2017

Microstructure and Deformation Behavior of Thermally Aged Cast Austenitic Stainless Steels

Y. Chen; Chi Xu; Xuan Zhang; Wei Ying Chen; Jun-Sang Park; Jonathan Almer; Meimei Li; Z. Li; Yong Yang; A. S. Rao; Bogdan Alexandreanu; K. Natesan

Cast austenitic stainless steels (CASS) consist of a dual-phase microstructure of delta ferrite and austenite. The ferrite phase is critical for the service performance of CASS alloys, but can also undergo significant microstructural changes at elevated temperatures, leading to severe embrittlement. To understand thermal aging embrittlement, fracture toughness J-R curve tests were performed on unaged and aged CF8 specimens at 315 ℃. The microstructure of CF8 was also examined before and after thermal aging with transmission electron microscopy and atom probe tomography. While no microstructural change was observed in the austenite after thermal aging, a high density of G-phase precipitates and a phase separation of alpha/alpha prime were detected in ferrite. To study the deformation behavior, tensile tests were performed at room temperature with in situ wide-angle X-ray scattering measurements. The differences in lattice strains between ferrite and austenite were much higher in the aged than in the unaged samples, suggesting a higher degree of incompatible deformation between ferrite and austenite in the aged samples.


Materials Characterization | 2015

The interfacial orientation relationship of oxide nanoparticles in a hafnium-containing oxide dispersion-strengthened austenitic stainless steel

Yinbin Miao; Kun Mo; Bai Cui; Wei Ying Chen; M.K. Miller; Kathy A. Powers; Virginia McCreary; David R. Gross; Jonathan Almer; I.M. Robertson; James F. Stubbins


Journal of Nuclear Materials | 2015

Atom probe study of irradiation-enhanced α' precipitation in neutron-irradiated Fe–Cr model alloys

Wei Ying Chen; Yinbin Miao; Yaqiao Wu; Carolyn A. Tomchik; Kun Mo; Jian Gan; Maria A. Okuniewski; S.A. Maloy; James F. Stubbins


Journal of Nuclear Materials | 2014

The evolution mechanism of the dislocation loops in irradiated lanthanum doped cerium oxide

Yinbin Miao; Dilpuneet S. Aidhy; Wei Ying Chen; Kun Mo; Aaron Oaks; D. Wolf; James F. Stubbins


Journal of Nuclear Materials | 2011

Kinetic Monte Carlo model of defect transport and irradiation effects in La-doped CeO2

Aaron Oaks; Di Yun; Bei Ye; Wei Ying Chen; James F. Stubbins


Journal of Nuclear Materials | 2011

Kr and Xe irradiations in lanthanum (La) doped ceria: Study at the high dose regime

Di Yun; Aaron Oaks; Wei Ying Chen; M. A. Kirk; J. Rest; Zinetula Z. Insopov; Abdellatif M. Yacout; James F. Stubbins


Nuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms | 2012

Fission gas transport and its interactions with irradiation-induced defects in lanthanum doped ceria

Di Yun; Bei Ye; Aaron Oaks; Wei Ying Chen; M. A. Kirk; J. Rest; Abdellatif M. Yacout; James F. Stubbins


Journal of Nuclear Materials | 2013

Irradiation effects in UO2 and CeO2

Bei Ye; Aaron Oaks; Mark A. Kirk; Di Yun; Wei Ying Chen; Benjamin Holtzman; James F. Stubbins

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Yinbin Miao

Argonne National Laboratory

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Kun Mo

Argonne National Laboratory

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Di Yun

Argonne National Laboratory

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M. A. Kirk

Argonne National Laboratory

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J. Rest

Argonne National Laboratory

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Jian Gan

Idaho National Laboratory

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K. Natesan

Argonne National Laboratory

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