Publications

Publications

Journal articles:

  1. C. Xu, W-Y. Chen, Y. Chen, Y. Yang, “Microstructural evolution of NF709 austenitic stainless steel under in-situ ion irradiations at room temperature, 300, 400, 500 and 600 °C”, J. Nucl. Mater. 509, 644 (2018). https://doi.org/10.1016/j.jnucmat.2018.07.044
  2. C. Xu, X. Zhang, Y. Chen, M. Li, J-S Park, P. Kenesei, J. Almer and Y. Yang, “In-situ High-Energy X-ray Characterization of Neutron Irradiated HT-UPS Stainless Steel under Tensile Deformation”, Acta Materialia, 156, 330 (2018), https://doi.org/10.1016/j.actamat.2018.07.008
  3. C. Xu, W-Y Chen, X. Zhang, Y. Wu, M. Li and Y. Yang, “Effects of Neutron Irradiation and Post-irradiation Annealing on the Microstructure of HT-UPS Stainless Steel”, Journal of Nuclear Materials, 507, 188 (2018), https://doi.org/10.1016/j.jnucmat.2018.04.043
  4. S. Huang, W-Y. Lo and Y. Yang, “Vanadium carbide by MOCVD for mitigating the fuel cladding chemical interaction”, Fusion Engineering and Design, 125, 556 (2017) https://doi.org/10.1016/j.fusengdes.2017.04.118
  5. E. Aydogan, et al., “Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions”, J. Nucl. Mater. 487, 96 (2017) https://doi.org/10.1016/j.jnucmat.2017.02.006.
  6. B.K.Kim, L. Tan, C. Xu, Y. Yang, X. Zhang, M. Li, “Microstructural Evolution of NF709 (20Cr-25Ni-1.5MoNbTiN) under neutron irradiation”, J. Nucl. Mater. 470, 229 (2016) http://dx.doi.org/10.1016/j.jnucmat.2015.12.037
  7. Y. Chen, B. Alexandreanu, K. Natesan, Z. Li, Y. Yang, A. S. Rao, “Cracking behavior of thermally aged and irradiated CF-8 cast austenitic stainless steel”, J. Nucl. Mater. 466, 560 (2015)  http://dx.doi.org/10.1016/j.jnucmat.2015.08.047
  8. Z. Li, Wei-Yang Lo, Y. Chen, J. Pakarinen, Y. Wu, T. Allen and Y. Yang, “Irradiation response of delta ferrite in as-cast and thermally aged cast stainless steel”, J. Nucl. Mater. 466, 201 (2015) http://dx.doi.org/10.1016/j.jnucmat.2015.08.006
  9. J. Gigax, E. Aydogan, T. Chen, L. Shao, Y. Wu, W. Y. Lo, Y. Yang, and F. A. Garner, “The influence of ion beam rastering on the swelling of self-ion irradiated pure ion at 450ºC”, J. Nucl. Mater. 465, 343 (2015) http://dx.doi.org/10.1016/j.jnucmat.2015.05.025
  10. W.-Y. Lo, N. Silva, R. Winmann-Smith, and Y. Yang, “Effects of Cr on the interdiffusion between Ce and Fe-Cr alloys”, J. Nucl. Mater. 458, 264 (2015) http://dx.doi.org/10.1016/j.jnucmat.2014.12.035
  11. C. Sun, S. Zhang, C.C. Wei, Y. Wu, L. Shao, Y. Yang, KT. Hartwig, S. Maloy, S. Zinkle, T. Allen, H. Wang, X. Zhang, “Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments”, Sci. Rep. 5, 7801 (2015) http://www.nature.com/articles/srep07801
  12. W-Y Lo, and Y. Yang, “Vanadium Diffusion Coating on HT-9 Cladding For Mitigating the Fuel Cladding Chemical Interactions”, J. Nucl. Mater. 451, 137 (2014) http://dx.doi.org/10.1016/j.jnucmat.2014.03.052
  13. M. Song, Y. Wu, D. Chen, X. Wang, C. Sun, K. Yu, Y. Chen, L. Shao, Y. Yang, KT Hartwig, X. Zhang, “Response of equal channel angular extrusion processed ultrafine-grained T91 steel subjected to high temperature heavy ion irradiation”, Acta Mater. 74, 285 (2014) http://dx.doi.org/10.1016/j.actamat.2014.04.034
  14. Y. Yang, W-Y Lo, C. Dickerson, T. Allen, “Stoichiometry effect on the irradiation response in the microstructure of zirconium carbides”, J. Nucl. Mater. 454, 130 (2014) http://dx.doi.org/10.1016/j.jnucmat.2014.07.071
  15. T. Allen, D. Kaoumi, J. P. Wharry, Z. Jiao, C. Topbasi, A. Kohnert, L. Barnard, A. Certain, K. Field, G. Was, D. Morgan, A. Motta, B. Wirth, Y. Yang,  “Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature” J. Mater. Research. 30, 1246, 2015 https://www.cambridge.org/core/services/aop-cambridge-core/content/view/S0884291415000990
  16. C. Sun, J. Ma, Y. Yang, K. Hartwig, S. Maloy, H. Wang, X. Zhang, “Temperature and Grain Size Dependent Plastic Instability and Strain Rate Sensitivity of Ultrafine Grained Austenitic Fe-14Cr-16Ni alloy”, Mater. Sci. Eng. A. 597, 415 (2014) http://dx.doi.org/10.1016/j.msea.2014.01.003
  17. C. Dickerson, Y. Yang, T. Allen, “Defects and microstructural evolution of proton irradiated titanium carbide”, J. Nucl. Mater. 424, 62 (2012) http://dx.doi.org/10.1016/j.jnucmat.2012.02.005

 

Refereed Conference Proceedings

  1. Li, Z. Chen Y. Rao A. S., Yang, Y. (2018), 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
  2. Y. Chen, C. Xu(g), X. Zhang, W-Y Chen, J.-S. Park, J. Almer, M. Li, Z. Li(g), Y. Yang, A. S. Rao, B. Alexandreanu, and K. 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
  3. W.-Y. Lo, S. Huang, N. Strombom, Y. Yang, “Low-Temperature Chemical Vapor Deposition of Vanadium Carbide for Mitigating the FCCI”, Trans. American Nucl. Society, 111, 583 (2014) 
  4. N. Silva,  Y. Yang, “Hydrogen Migration, Precipitation and Re-orientation in Nuclear Spent Fuel Cladding in Dry Storage”, Trans. American Nucl. Society, 110, 900 (2014)
  5. E. Beyer, J. Tulenko, Y. Yang, G. Fuchs, J. Stubbins, J. Eapen, K. Murty, “Low temperature creep of used nuclear fuel during long term dry storage”, Proceeding of 14th International High-level Radioactive Waste Management Conference, IHLRWMC 2013: Integrating Storage, Transportation, and Disposal, 2, 657 (2013).
  6. Y. Yang, Y. R. Chen, Y. Huang, T. Allen, A. Rao, “Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C”, Proceeding of 15th Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst., 2137 (2012)
  7. Y. Chen, B. Alexandreanu, Y. Yang, W. J. Shack, K. Natesan, E. E. Gruber, A.S. Rao, “Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment”, Proceeding of 15th Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst., 1169 (2012)