Publications

Publications

Recent Publications:

  1. Y. Chen, B. Alexandreanu, K. Natesan, Z. Li(g), Y. Yang, A. S. Rao. 2015 Cracking behavior of thermally aged and irradiated CF-8 cast austenitic stainless steel. Journal of Nuclear Materials. In press.
  2. Z. Li(g), W.-Y. Lo(g), Y. Chen, J. Pakarinen, Y. Wu, T. Allen and Y. Yang. 2015. Irradiation response of delta ferrite in as-cast and thermally aged cast stainless steel. Journal of Nuclear Materials. 466: 201-207
  3. Gigax, E. Aydogan, T. Chen, L. Shao, Y. Wu(g), W. Y. Lo(g), Y. Yang, and F. A. Garner. 2015. The influence of ion beam rastering on the swelling of self-ion irradiated pure ion at 450ºC. Journal of Nuclear Materials. 465: 343-348
  4. 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. 2015. Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature. Journal of Mater. Research. 30: 1246-1274
  5. W.-Y. Lo(g), N. Silva(g), R. Winmann-Smith(&), and Y. Yang, 2015. Effects of Cr on the interdiffusion between Ce and Fe-Cr alloys. Journal of Nuclear Materials. 458: 264-271
  6. C. Sun, S. Zhang, C.C. Wei, Y. Wu(g), L. Shao, Y. Yang, KT. Hartwig, S. Maloy, S. Zinkle, T. Allen, H. Wang, X. Zhang. 2015. Superior radiation-resistant nanoengineered austenitic 304L stainless steel for applications in extreme radiation environments. Scientific Report, 5
  7. Wei-yang Lo(g) and Yong Yang. 2014 Vanadium Diffusion Coating on HT-9 Cladding For Mitigating the Fuel Cladding Chemical Interactions. Journal of Nuclear Materials. 451(1): 137-142
  8. M. Song, Y. Wu(g), D. Chen, X. Wang, C. Sun, K. Yu, Y. Chen, L. Shao, Y. Yang, KT Hartwig, X. Zhang. 2014 Response of equal channel angular extrusion processed ultrafine-grained T91 steel subjected to high temperature heavy ion irradiation. Acta Materialia, 74: 285-295
  9. Y. Yang, W-Y Lo(g), C. Dickerson, T. Allen. 2014. Stoichiometry effect on the irradiation response in the microstructure of zirconium carbides. Journal of Nuclear Materials. 454: 130-135
  10. C. Sun, J. Ma, Y. Yang, K. Hartwig, S. Maloy, H. Wang, X. Zhang. 2014. Temperature and Grain Size Dependent Plastic Instability and Strain Rate Sensitivity of Ultrafine Grained Austenitic Fe-14Cr-16Ni alloy. Materials Science and Engineering A. 597: 2014: 415-421
  11. Dickerson, Y. Yang, and Todd Allen. 2012. Defects and microstructural evolution of proton irradiated titanium carbide. Journal of Nuclear Materials. 424: 62-68

Referred conference papers:

  1. 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.
  2. 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
  3. W-Y Lo(g), S. Huang(p), N. Strombom(g) and Yong Yang. 2014. Low-Temperature Chemical Vapor Deposition of Vanadium Carbide for Mitigating the FCCI. Transactions of the American Nuclear Society, 111: 583-583
  4. Silva(g), Y. Yang. 2014. Hydrogen Migration, Precipitation and Re-orientation in Nuclear Spent Fuel Cladding in Dry Storage. Transactions of the American Nuclear Society, 110: 900-900
  5. C.E. Beyer, J. Tulenko, Y. Yang, G. Fuchs, J. Stubbins, J. Eapen, K. Murty. 2013. Low temperature creep of used nuclear fuel during long term dry storage. 14th International High-level Radioactive Waste Management Conference, IHLRWMC 2013: Integrating Storage, Transportation, and Disposal, 2: 657-665
  6. Y. Yang, Y. R. Chen, Y. Huang, T. Allen, A. Rao. 2012. 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., 2137-2148
  7. Y. Chen, B. Alexandreanu, Y. Yang, W. J. Shack, K. Natesan, E. E. Gruber, A.S. Rao, 2012. Crack Growth Behavior of Irradiated Type 316 SS in Low Dissolved Oxygen Environment, Proceeding of 15th Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst., 1169-1182