Skip to main content
Herbert Wertheim College of Engineering

Publications

Journal Articles

  1. Y. Lu, Y. Chen, J. Terry, Y. Yang, “Understand the thermal aging effect on mechanical response of a duplex stainless steel by in-situ synchrotron Wide-Angle X-ray Scattering” Accepted to Metallurgical and Materials Transactions A, 2026
  2. Kookyun Jeong, and Yong Yang, “Low-Temperature MOCVD Deposition of Vanadium Carbide on F/M Steel for Mitigating Fuel Cladding Chemical Interaction”, Nuclear Science and Engineering, 199 (2025), 817-828.
  3. Zhenyu. Fu, Lingfeng He, Isabella. J. van Rooyen, and Yong Yang, Comparison of microstructural and micro-chemical evolutions in the irradiated fuel kernels of AGR-1 and AGR-2 TRISO fuel particle, Progress in Nuclear Energy, 176 (2024), 105361.
  4. Zhenyu Fu, Yong Yang, Isabella J. Van Rooyen, Subhashish Meher and Boopathy Kombaiah, “Microstructural and Micro-Chemical Evolutions in Irradiated UCO Fuel Kernels of AGR-1 and AGR-2 TRISO Fuel Particles”, Journal of Physics: Conf. Ser. 2048 (2021) 012006.
  5. Yu Lu, Appajosula Rao, Yiren Chen, and Yong Yang, Evolution of δ ferrite in a CF3 cast stainless steel upon neutron irradiation to 3, 5, 10, 20, and 40 dpa, Journal of Nuclear Materials, 549, (2021), 152865.
  6. Zhenyu Fu, Isabella J. van Rooyen, Mukesh Bachhav, Yong Yang, “Microstructure and Fission Products in the UCO kernel of an AGR-1 TRISO fuel Particle after Post Irradiation Safety Testing”, Journal of Nuclear Materials, 528 (2020), 151884.
  7. Niels Gautaerts, Rémi Delville, Erich Stergar, Janne Pakarinen, Marc Verwerft, Yong Yang, Christina Hofer, Ronald Schnitzer, Steffen Lamm, Peter Felfer, Dominique Schryver, “The role of Ti and TiC nanoprecipitaes in radiation resistant austenitic steel: A nanoscale study”, Acta Materialia, 197 (2020), 184-197.
  8. Chi Xu, Yu Lu, Zhenyu Fu, Yong Yang, “In-situ TEM Characterization of the Tensile Deformation of Ion-irradiated HT-UPS Steel at RT and 400℃”, Journal of Nuclear Materials 529 (2020), 1511911.
  9. Shaosong Huang, Wei-Yang. Lo, and Yong Yang, “Vanadium carbide by MOCVD for mitigating the fuel cladding chemical interaction”, 125, Fusion Engineering and Design, (2017), 556-561.
  10. Wei-Yang Lo, Nicolas. Silva, Yuedong. Wu, Robert. Winmann-Smith and Yong Yang, “Effects of Cr on the interdiffusion between Ce and Fe-Cr alloys”, Journal of Nuclear Materials, 458, (2015), 264.

Conference Proceedings

  1. C. Adkins, D. Salvato, T. Yao, and Y. Yang, Experiments Supportng Effective Thermal Conductivity Calculation of Irradiated U-Zr Fuel, Transactions of the American Society, 128, 2023, 380-382
  2. I. J. van Rooyen, Z. FuG, Y. Yang, T. G. Holesinger, and M. Bachhav, “Microstructure and Fission Product Distribution Examination in the UCO Kernel of TRISO Fuel Particles”, Proceeding of HTR2018, Warsaw, Poland, Oct 8-10, 2018, Paper #3012.
  3. Yiren Chen, Chi Xu(G), Xuan Zhang, Wei-Ying Chen, Jun-sang. Park, Jonathan Almer,Meimei Li,Zhangbo Li(G),Yong Yang,Appajosula S. Rao, Bogdan Alexandreanu,and Ken. Natesan, (2018) Microstructure and Deformation Behavior of Thermally Aged Cast Austenitic Stainless Steels, In: Jackson J., Paraventi D., Wright M. (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems –Water Reactors, pp 625-641, EDM 2017. The Minerals, Metals & Materials Series. Springer, Cham
  4. Li, Z (G). Chen Y. Rao A. S., Yang, Y, Effects of Thermal Aging and Low Dose Neutron Irradiation on the Ferrite Phase in a 308L Weld, In: Jackson J., Paraventi D., Wright M. (eds), Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems –Water Reactors, pp 689-702, EDM 2017. The Minerals, Metals & Materials Series. Springer, Cham
  5. C. Xu(g), M. Li, M. Kirk, P. Baldo, and Y. Yang, “Microstructural Evolution of NF709 Steel under In-Situ Ion Irradiations at Room Temperatures at 600C”, Accepted to the Transaction of the American Nuclear Society 2017 Summer Meeting.
  6. Yong Yang and Zhangbo. Li(G), “Irradiation Response of the Ferrite Phase in CF3 Cast Stainless Steel”, Transactions of the American Nuclear Society, v116, p 390-391, 2017, Transactions of the American Nuclear Society, ANS 2017.
  7. Chi Xu(G), Xuan Zhang, Meimei Li, Jun-sang Park, Peter Kenesei, Jonathan Almer, Yong Yang, In-situ High Energy X-ray Characterization of Tensile Deformation of Advanced Austenitic Stainless Steels, ANS Transaction Vol. 114,
  8. Y. Chen, W-Y. Chen, A.S.Rao, Z. Li(g), Y. Yang, B. Alexandreanu, K. Natesan, Fracture resistance of CASS austenitic stainless steels, ICON24, Accepted. 2016.
  9. K. Jeong(g), S. S. Huang, and Y. Yang. 2015. Innovative coating of vanadium carbide on the F/M stainless steel for mitigating fuel cladding chemical interaction. Transactions of the American Nuclear Society. Accepted.
  10. Z. Li(g), Y. Chen, and Y. Yang. 2015. Comparison Between Thermal Aging and Low Dose Neutron Irradiation Effects on Ferrites in a Duplex Structure Stainless Steel. Transactions of the American Nuclear Society. Accepted
  11. Y. Chen, B. Alexandreanu, W. Chen, Z. Li(g), Y. Yang, K. Natesan and A. S. Rao. Crack growth rate and fracture toughness J-R curve tests on irradiated cast austenitic stainless steels.  2015. 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors August 9-13, 2015, Ottawa, Ontario, Canada