学术期刊 (* 通讯作者)

1. L. Joyce, R. Umretiya, H. Qu, Z. Shang, Y. Xie*, Oxidation behavior of PM-C26M FeCrAl alloy in low-temperature steam 400 – 900 °C, Nuclear Materials and Energy 43 (2025) 101953. https://doi.org/10.1016/j.nme.2025.101953
   

2. O. Lastres, Y. Xu*, Y. Xie*, A neutronics-fuel coupling model for the simulation of constituent redistribution in U–Zr fuel, Progress in Nuclear Energy 177 (2024) 105467. https://doi.org/10.1016/j.pnucene.2024.105467

3. Y. Xie*, E. Medvedovski, L. Joyce, D. Simonton, E. Frishholz, Assessing aluminized and boronized thermal diffusion coating in molten salt and sodium, Surface and Coatings Technology 487 (2024) 130973. https://doi.org/10.1016/j.surfcoat.2024.130973

4. L. Joyce, P. Wang, R. Umretiya, A. Hoffman, Y. Xie*, Oxide layers in Ni-doped FeCrAl alloy in 320 C radioactive hydrogenated water, Journal of Nuclear Materials 593 (2024) 154987. https://doi.org/10.1016/j.jnucmat.2024.154987

5. Y. Xie*, Tellurium Corrosion of Type 304/304L Stainless Steel, Iron, Chromium, and Nickel in High-Temperature Liquid Sodium, Materials 16 (2023), 6798. https://doi.org/10.3390/ma16206798

6. L. Joyce, Y. Xie*, A rapid sintering method for uranium mononitride surrogate pellet, Ceramics 5 (2022) 1009-1018. https://doi.org/10.3390/ceramics5040072.

7. B. Bettes, Y. Xie*, Synthesis and processing of transparent polycrystalline doped yttrium aluminum garnet: a review, Materials Research Letter 11 (2023) 1-20. https://doi.org/10.1080/21663831.2022.2109441

8. Y. Xie*, S.C. Vogel, M.T. Benson, J.M. Harp, Phase evolution of U–Zr system in a thermal cycling neutron diffraction experiment: as-cast U–35Zr and U–50Zr, Journal of Nuclear Materials 564 (2022) 153681. https://doi.org/10.1016/j.jnucmat.2022.153681

9. B. Bettes, Y. Xie*, C.-H. Shiau, C. Sun, Chemical interactions between neodymium and advanced stainless steels, Journal of Nuclear Materials 559 (2022) 153451. https://doi.org/10.1016/j.jnucmat.2021.153451

10. W. Zhuo, H. Wu, Y. Xie, M.T. Benson, J. Zhang, Solid-state phase transitions of two quaternary metallic fuel alloys (U-2.5Mo-2.5Ti-5.0Zr and U-1.5Mo-1.5T-7.0Zr in wt.%), Journal of Nuclear Materials 555 (2021) 153134. https://doi.org/10.1016/j.jnucmat.2021.153134

11. M.T. Benson, J.M. Harp, Y. Xie, T. Yao, K.R. Tolman, K.E. Wright, J.A. King, A.I. Hawari, Q. Cai, Out-of-pile and post-irradiated examination of lanthanide and lanthanide-palladium interactions for metallic fuel, Journal of Nuclear Materials 2020 (544) 152727. https://doi.org/10.1016/j.jnucmat.2020.152727

12. Y. Xie*, S.C. Vogel, J.M. Harp, M.T. Benson, L. Capriotti, Microstructure evolution of U-Zr system in a thermal cycling neutron diffraction experiment: extruded U-10Zr (wt. %), Journal of Nuclear Materials 544 (2021) 152665. https://doi.org/10.1016/j.jnucmat.2020.152665

13. W. Zhuo, Y. Xie, M.T. Benson, J. Ge, R.D. Mariani, J. Zhang, XRD and SEM/EDS characterization of two quaternary fuel alloys (U-2.5Mo-2.5Ti-5.0Zr and U-1.5Mo-1.5Ti-7.0Zr in wt. %) for fast reactors, Materials Characterization 170 (2020) 110696. https://doi.org/10.1016/j.matchar.2020.110696

14. R. Khanal, N. Jerred, M.T. Benson, Y. Xie, R.D. Mariani, I. Charit, S. Choudhury, Interactions and Immobilization of Lanthanides with Dopants in Uranium-based Metallic Fuels, Journal of Nuclear Materials 540 (2020) 152372. https://doi.org/10.1016/j.jnucmat.2020.152372

15. Y. Xie, M.T. Benson, Microstructure and diffusion behavior of uranium fuel with minor additives, Journal of Nuclear Materials 535 (2020) 152200. https://doi.org/10.1016/j.jnucmat.2020.152200

16. A. Ronne, L. He, D. Dolzhnikov, Y. Xie, M. Ge, P, Halstenberg, Y. Wang, B. Manard, X. Xiao, W.-K. Lee, K. Sasaki, S. Dai, S. Mahurin, Y. Chen-Wiegart, Revealing 3D morphological and chemical evolution mechanisms of metals in molten salt by multimodal microscopy, ACS Applied Materials & Interfaces 12 (2020) 17321-17333. https://doi.org/10.1021/acsami.9b19099

17. W. Zhuo, Y. Xie, M.T. Benson, H. Wu, R.D. Mariani, J. Zhang, Experimental assessment of antimony (Sb) in pure uranium for immobilizing fission product lanthanides, Journal of Nuclear Materials 534 (2020) 152135. https://doi.org/10.1016/j.jnucmat.2020.152135

18. W. Zhuo, Y. Xie, M.T. Benson, R.D. Mariani, J. Zhang, Experimental investigation of FCCI using diffusion couple test between UZr fuel with Sb additive and cladding, Nuclear Science and Engineering 194 (2020) 462-476. https://doi.org/10.1080/00295639.2020.1713656

19. C. Jiang*, Y. Xie*, Efficient computational search for lanthanide-binding additive dopants for advanced U-Zr based fuels, Materialia 10 (2020) 100653. https://doi.org/10.1016/j.mtla.2020.100653

20. M.H. Cullison, C. Zhen, J.J. Olson-Gross, Y. Xie, M.T. Benson, T. Chen, Microstructure study of U-35wt.%Zr alloy after quick annealing at 650 ºC, Journal of Materials Research 35 (2020) 1095-1102. https://doi.org/10.1557/jmr.2020.21

21. Y. Xie, M.T. Benson, L. He, J.A. King, R.D. Mariani, D.J. Murray, Diffusion behaviors between metallic fuel alloys with Pd addition and Fe, Journal of Nuclear Materials 525 (2019) 111-124. https://doi.org/10.1016/j.jnucmat.2019.07.028

22. M.T. Benson, Y. Xie, L. He, K.R. Tolman, J.A. King, R.D. Mariani, B.J. Hernandez, D.J. Murray, B.D. Miller, Microstructural characterization of annealed U-20Pu-10Zr-3.86Pd and U-20Pu-10Zr-3.86Pd-4.3Ln, Journal of Nuclear Materials 518 (2019) 287-297. https://doi.org/10.1016/j.jnucmat.2019.03.014

23. Y. Xie, J. Zhang, Michael Benson, Robert Mariani, Diffusion behavior of lanthanide-additive compounds (Ce4Sb3, Ce2Sb, and CeTe) against HT9 and Fe, Materials Characterization 150 (2019) 107-117. https://doi.org/10.1016/j.matchar.2019.02.012

24. Y. Xie, J. Zhang, M.T. Benson, J.A. King, R.D. Mariani, Assessment of Te as a U-Zr fuel additive to mitigate fuel-cladding chemical interactions, Journal of Nuclear Materials 513 (2019) 175-184. https://doi.org/10.1016/j.jnucmat.2018.10.050

25. Y. Xie, A. Leong, J. Zhang, J.J. Leavitt, Aluminum alloy corrosion in boron-containing alkaline solutions, Materials and Corrosion 70 (2019) 810-819. https://doi.org/10.1002/maco.201810599

26. Y. Xie, J. Zhang, X. Li, J.P. Isler, M.T. Benson, R.D. Mariani, C. Unal, Lanthanide migration and immobilization in metallic fuels, Progress in Nuclear Energy 109 (2018) 233-238. https://doi.org/10.1016/j.pnucene.2018.08.019

27. S. Guo, B. Dsouza, Y. Xie, A. Leong, J. Leavitt, J. Zhang, Aluminum corrosion in reactor containment environment following a loss of coolant accident (LOCA): high-temperature flow loop tests, Corrosion Science 151 (2019) 122-131. https://doi.org/10.1016/j.corsci.2019.02.021

28. Y. Xie, J. Zhang, M.T. Benson, R.D. Mariani, Thermodynamic stability studies of Ce-Sb compounds with Fe, Journal of Nuclear Materials 499 (2018) 440-445. https://doi.org/10.1016/j.jnucmat.2017.12.008

29. Y. Xie, J. Zhang, T. Aldemir, R. Denning, Multi-state Markov model of pitting corrosion in stainless steel exposed to chloride-containing environment, Reliability Engineering & System Safety 172 (2018) 239-248. https://doi.org/10.1016/j.ress.2017.12.015

30. M.T. Benson, Y. Xie, J.A. King, K.R. Tolman, R.D. Mariani, I. Charit, J. Zhang, M.P. Short, S. Choudhury, R. Khanal, N. Jerred, Characterization of U-10Zr-2Sn-2Sb and U-10Zr-2Sn-2Sb-4Ln to assess Sn+Sb as a mixed additive system to bind lanthanides, Journal of Nuclear Materials 510 (2018) 210-218. https://doi.org/10.1016/j.jnucmat.2018.08.017

31. Y. Xie, M.T. Benson, J.A. King, R.D. Mariani, J. Zhang, Characterization of U-Zr Fuel with alloying additive Sb for stabilizing fission product lanthanides, Journal of Nuclear Materials 498 (2018) 332-340. https://doi.org/10.1016/j.jnucmat.2017.10.039

32. Y. Xie, S. Guo, A. Leong, J. Zhang, Y. Zhu, Corrosion behavior of stainless steel exposed to highly concentrated chloride solutions, Corrosion Engineering, Science and Technology (2017) 52, 283-293. https://doi.org/10.1080/1478422X.2016.1275418

33. S. Guo, J.J. Leavitt, X. Zhou, Y. Xie, S. Tietze, Y. Zhu, A. Lawver, E. Lahti, J. Zhang, Effects of flow, Si inhibition, and concurrent corrosion of dissimilar metals on the corrosion of aluminium in the environment following a loss-of-coolant accident, Corrosion Science 128 (2017) 100-109. https://doi.org/10.1016/j.corsci.2017.09.012

34. Y. Xie, J. Zhang, Corrosion and deposition on the secondary circuit of steam generators, Journal of Nuclear Science and Technology 53 (2016) 1455-1466. https://doi.org/10.1080/00223131.2016.1152923

35. Y. Xie, Y. Wu, J. Burns, J. Zhang, Characterization of stress corrosion cracks in Ni-based weld alloys 52, 52M and 152 grown in high-temperature water, Materials Characterization 112 (2016) 87-97. https://doi.org/10.1016/j.matchar.2015.12.005

36. Y. Xie, J. Zhang, Chloride-induced stress corrosion cracking of used nuclear fuel welded SS canisters: A review, Journal of Nuclear Materials 466 (2015) 85-93. https://doi.org/10.1016/j.jnucmat.2015.07.043

书籍或章节

1. Y. Xie, J. Zhang. Chapter 6: Spent fuel interim dry storage system and chloride-induced stress corrosion cracking. In: Used Nuclear Fuel and Waste Management (J. Zhang Ed.), pp.177-237, World Scientific Publishing, 2017. https://doi.org/10.1142/11017

技术报告

1. M.P. Short, S. McAlpine, M. Tonks, A. Rezwan, J. Zhang, A. Leong, Y. Xie, J. Rausch, J. Salkin, M. Bachav, U. Ehrnsten, S. Penttila, S. Peltonen, P. Nevasmaa, R. Pohja, H. Hannien, T. Sarikka, R. Qiang, NEUP Final Report: Multilayer Composite Fuel Cladding and Core Internals for LWR Performance Enhancement and Severe Accident Tolerance, DOE/NEUP-15-8347, 2019.

2. M.T. Benson, Y. Xie, J.A. King, U-Pu-Zr-Pd alloy research and development activities: nuclear technology research and development. U.S. Department of Energy, Advanced Fuels Campaign, INL/EXT-19-54480, 2019.

会议论文

1. S. Vogel, Y. Xie, L. Capriotti, M. Benson, W. Williams, S. Rudin, J. Harp, Crystal structure evolution in U-2wt.%Zr using neutron diffraction with particular focus on β-uranium, Abstract in: TMS 2023 Annual Meeting and Exhibition, San Diego, California, Mar 19-23, 2023.

2. L. Joyce, Y. Xie*, An Efficient and Oxidation-preventive Method for UN Surrogate Pellets Fabrication, Abstract in: TMS 2023 Annual Meeting and Exhibition, San Diego, California, Mar 19-23, 2023.

3. Y. Xie*, Lanthanides Migration and Chemical Interaction with U-Zr Fuel Cladding, Abstract in: TMS 2023 Annual Meeting and Exhibition, San Diego, California, Mar 19-23, 2023.

4. Y. Xie*, S. Vogel, M. Benson, J. Harp, Microstructure and Phase Evolutions of U-Zr System in Thermal Cycling Neutron Diffraction Experiments, Abstract in: TMS 2023 Annual Meeting and Exhibition, San Diego, California, Mar 19-23, 2023.

5. L. He, K. Bawane, P. Xiu, T. Yao, C. Jiang, M. Khafizov, M. Jin, Y. Xie, L. Shao, Microstructural Evolution in Ceramic Nuclear Fuels and Their Surrogates under Irradiation, Abstract in the symposium of Ceramics for a New Generation of Nuclear Energy Systems and Applications, MS&T22: Materials Science & Technology, Pittsburgh, PA, October 9-12, 2022.

6. L. Joyce, Y. Xie*, Fabrication of CeN (UN fuel surrogate) using pressureless fast heating system, Transactions in: 2022 ANS Annual Meeting, Anaheim, CA, June 12-16, 2022.

7. B. Bettes, Y. Xie*, Fabrication of uranium doped yttrium aluminum garnets. Abstract in: TMS 2022 Annual Meeting & Exhibition, Anaheim, California, Feb 27-Mar 3, 2022.

8. B. Bettes, Y. Xie*, Effects of steel composition and grain size on diffusion with neodymium. Abstract in: TMS 2022 Annual Meeting & Exhibition, Anaheim, California, Feb 27-Mar 3, 2022.

9. Y. Xie*, M. Jin, Calculations of CISCC for UNF canisters thorugh physics-guided machine learning framework, Transactions in: 2021 ANS Annual Meeting, Virtual, June 14-16, 2021. Transactions of American Nuclear Society (124), 2021, 82-85.

10. S.C. Vogel, Y. Xie, L. Capriotti, M. Benson, J. Harp, Microstructure and crystal structure studies in the U-Zr system, Transactions in TMS 2021 Annual Meeting, Virtual, March 15-18, 2021.

11. A. Ronne, Y. Xie, P. Halstenberg, M. Ge, X. Xiao, Y. Wang, W.-K. Lee, L. He, S.M. Mahurin, K. Chen-Wiegart, Multimodal characterization of the morphological and chemical evolution of Ni and Ni-20Cr microwires in purified molten KCl-MgCl2, Transactions in: TMS 2020 Annual Meeting & Exhibition, San Diego, CA, Februray 23-27, 2020.

12. L. He, A. Ronne, S. Gill, K. Sasaki, Y. Xie, Y. Wang, P. Halstenberg, D. Dolzhnikov, K. Chen-Wiegart, S. Mahurin, Advanced characterization of corrosion behavior of metals in molten cholirde salts, Transactions in: TMS 2020 Annual Meeting & Exhibition, San Diego, CA, Februray 23-27, 2020.

13. A. Leong, J. Zhang, Y. Xie, Corrosion of Fe-12Cr-2Si alloy in high temperature steam enviornments, Transactions in: 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Boston, MA, August 18-22, 2019.

14. M.T. Benson, Y. Xie, J.A. King, D. Murray, L. He, I. Charit, S. Choudhury, J. Zhang, Investigation of antimony as a fuel additive to control FCCI in a transmutation fuel, Transactions in: 2019 Global/Top Fuel, Seattle, WA, September 22-26, 2019.

15. Y. Xie, M.T. Benson, L. He, J.A. King, Diffusion behaviors between Fe and Pd-containing metallic fuel, Transactions in: 2019 ANS Annual Meeting, Minneapolis, MN, June 9-13, 2019. Transactions of the American Nuclear Society 120 (2019) 412-413.

16. W. Zhuo, M.T. Benson, Y. Xie, R.D. Mariani, J. Zhang, Characterization of annealed U-10Zr fuel with additive antimony for immobilizing fission product lanthanides, Transactions in: 2019 ANS Annual Meeting, Minneapolis, MN, June 9-13, 2019. Transactions of the American Nuclear Society 120 (2019) 407-409.

17. J. Zhang, Y. Xie, Assessment of Sb and Te as U-Zr fuel additive to mitigate fuel-cladding chemical interaction, Proceedings in: NuMat 2018: The Nuclear Materials Conference, Seattle, Washington, October 14-18, 2018.

18. Y. Xie, J. Zhang, Thermodynamic modeling of Fe-Ce-Sb ternary phase diagram, Transactions in: 2017 ANS Winter Meeting and Nuclear Technology Expo, Washington, DC, October 29-November 2, 2017. Transactions of the American Nuclear Society 117 (2017) 557-558.

19. Y. Xie, J. Zhang, Chloride-induced stress corrosion cracking characteristics of the used nuclear fuel canister material, Transactions in: 2016 ANS Winter Meeting and Nuclear Technology Expo, Las Vegas, NV, November 6-10, 2016. Transactions of the American Nuclear Society 115 (2016) 442-443.

20. Y. Xie, J. Zhang, Pitting corrosion studies of used nuclear fuel canisters, Proceedings in: NuMat 2018: The Nuclear Materials Conference, Monpellier, France, November 7-10, 2016.

21. Y. Xie, J. Zhang, High temperature and pressure stress corrosion cracking system, Transactions in: 2013 ANS Winter Meeting and Technology Expo, Washington, DC, November 10-14, 2013. Transactions of the American Nuclear Society 109 (2013) 592-593.