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  1. M. H. Elhareef, Y. Abouhussien, Z. Wu, M. Fratoni, E. Davidson, T. Fei, and K. Harris, “A Reactor Transient Benchmark for Molten Salt Reactor Experiment Pump Transient Tests,” Nuclear Science and Engineering, 199(12), 2143-2171 (May 2025). (Paper)(DOI)
  2. M. H. Elhareef and Z. Wu, “A New Approach to Predict Pump Transient Phenomena in Molten Salt Reactor Experiment (MSRE) by Missing Data Identification and Regeneration,” Nuclear Engineering and Design, 424, 113292 (2024). (Paper) (DOI)
  3. Z. Wu,  C. Pochron, M. G. M. Pop, and N. Mann, “Neutronic Analysis of the Conceptual Molten Uranium Breeder Reactor (MUBR) Using MCNP and SCALE Tools,” Nuclear Technology, 211(2), 225-240 (April 2024). (Paper) (DOI)
  4. M. H. Elhareef,  Z. Wu, and M. Fratoni, “A Consistent One-Dimensional Multigroup Diffusion Model for Molten Salt Reactor Neutronics Calculations,” Journal of Nuclear Engineering, 4(4), 654-667 (October 2023). (Paper) (DOI)
  5. Z. Wu, C. Lu, and T. Liu, “Demonstrating Computational Equivalence between Continuous and Discrete Adjoint Methods by Calculating Time-dependent Adjoint Solutions with Neutron Diffusion Models,” Nuclear Science and Engineering, 197(6), 1213-1238  (2023). (Paper) (DOI)
  6. M. H. Elhareef and Z. Wu, “Physics-Informed Neural Network Method and Application to Nuclear Reactor Calculations: A Pilot Study,” Nuclear Science and Engineering, 197(4), 601-622 (2023). (Paper) (DOI)
  7. Z. Wu and J. C. Newman III, “Application of Complex-step Derivative Method for k-Eigenvalue Sensitivity Calculation in Neutron Transport Models,” Annals of Nuclear Energy, 151, 107975 (February 2021). (Paper) (DOI)
  8. C. Lu and Z. Wu, “A Preliminary Study on the Use of Linear Regression Method for Multigroup Cross Section Interpretation,” Nuclear Science and Engineering, 195(4), 437-452 (November 2020). (Paper) (DOI)
  9. C. Lu and Z. Wu, “Sensitivity Analysis of the 1-D Thermal Stratification Model via Forward and Adjoint Methods,” Trans. Am. Nucl. Soc., 123, 1605-1607 (2020). (Paper) (DOI) ANS Virtual Winter Meeting, November 16-19 (2020). (Presentation)
  10. C. Lu, Z. Wu, and X. Wu, “Enhancing the 1-D SFR Thermal Stratification Model via Advanced Inverse Uncertainty Quantification Methods,” Nuclear Technology, 207(5), 692-710 (2021). (Paper) (DOI)
  11. Z. Wu, J. Liang, X. Peng and H. S. Abdel-Kalik, “GPT-free Sensitivity Analysis for Monte Carlo Models,” Nuclear Technology, 205(7), 912-927 (2019). (Paper) (DOI)
  12. Z. Wu, R. E. Williams, J. M. Rowe, T. H. Newton, and S. O’Kelly, “Neutronics and Safety Studies on a Research Reactor Concept for an Advanced Neutron Source,” Nuclear Technology, 199(1), 67-82 (2017). (Paper) (DOI)
  13. Z. Wu, W. S. Yang, S. Shi, and M. Ishii, “A Core Design for a Small Modular Boiling Water Reactor with Long-Life Core,” Nuclear Technology, 193(3), 364-374 (2016). (Paper) (DOI)
  14. Z. Wu and R. E. Williams, “Reactor Power Distribution Calculation in Research Reactors Using MCNP,” Trans. Am. Nucl. Soc., 113, 1171-1174 (2015). (Paper) ANS Winter Meeting, Washington D.C., November 8-12 (2015). (Presentation)
  15. Z. Wu, Q. Zhang and H. S. Abdel-Khalik, “Hybrid Monte Carlo-Deterministic Methods for Reactor Analysis,” Nuclear Technology, 180(3), 372-382 (2012). (Paper) (DOI)
  16. Z. Wu and M. L. Adams, “Advances in Inverse Transport Methods”, Proceedings of 18th International Conference on Nuclear Engineering, 2, ICONE18-29881, 713-719 (2010).(Paper)  ICONE-18, Xi’an, China, May 17-21 (2010). (Presentation) (Poster)
  17. Z. Wu and M. L. Adams, “Variable Change Technique Applied in Constrained Inverse Transport Applications”, Trans. Am. Nucl. Soc., 102, 209-212 (2010). (Paper) ANS  Annual Meeting, San Diego, CA, Jun. 13-17 (2010). (Presentation)