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Refereed Journal Articles

  1. 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)
  2. T. Liu, Z. Wu, M. Bensi, and Z. Ma, “A mechanistic model of a PWR-based nuclear power plant in response to external hazard-induced station blackout accidents,” Front. Energy Res., Volume 11 (2023). (DOI)
  3. 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)
  4. 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)
  5. C. Lu and Z. Wu, “A New Method to Efficiently Estimate the Equilibrium State of Pebble Bed Reactors,” Nuclear Technology, 208(10), 1577-1590 (October 2022). (Paper) (DOI)
  6. L. Carlson, J. Miller, and Z. Wu, “Implications of HALEU Fuel on the Design of SMRs and Micro-Reactors,” Nuclear Engineering and Design, 389, 111648 (April 2022). (Paper) (DOI)
  7. C. Lu and Z. Wu, “Uncertainty Quantification of the 1-D SFR Thermal Stratification Model via Latin Hypercube Sampling Monte Carlo Method,” Nuclear Technology, 208(1), 37-48 (January 2022). (Paper) (DOI)
  8. Y. Xie, Y. Wang, Y. Ma, and Z. Wu, “Neural Network Based Deep Learning Method for Multi-Dimensional Neutron Diffusion Problems with Novel Treatment to Boundary,” Journal of Nuclear Engineering, 2, 533-552 (December 2021). (Paper) (DOI)
  9. L. Tian, F. Zhang, Z. Wu, Z. Wang, F. Qiu, Q. Fang, Q. Chen, and L. Zhou, “A New Diffusion Effect Correction Method in Pulsed Neutron Capture Logging,” Journal of Petroleum Science and Engineering, 204, 108673 (2021). (Paper)  (DOI)
  10. T. Liu, Z. Wu, C. Lu, and R. P. Martin, “A Best Estimate Plus Uncertainty Safety Analysis Framework Based on RELAP5-3D and RAVEN Platform for Research Reactor Transient Analyses,” Progress in Nuclear Energy, 132, 103610 (February 2021). (Paper) (DOI)
  11. L. Carlson, Z. Wu, J. Olson, and L. Liu, “An Economic Cost Assessment on HALEU Fuels for Small Modular Reactors,” Science and Technology of Nuclear Installations, Vol, 2020, 8815715 (2020). (Paper) (DOI)
  12. 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)
  13. 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)
  14. C. Lu and Z. Wu, “Sensitivity Analysis of the 1-D SFR Thermal Stratification Model via Discrete Adjoint Sensitivity Method,” Nuclear Engineering and Design, 370, 110920 (2020). (Paper) (DOI)
  15. 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 (Oct. 2020). (Paper) (DOI)
  16. Z. Wu, C. Lu, S. Morgan, and S. Bilbao y Leon, and M. Bucknor, “A Status Review on the Thermal Stratification Modeling Methods for Sodium-cooled Fast Reactors,” Progress in Nuclear Energy, 125, 103369 (2020). (Paper) (DOI)
  17. C. Lu, Z. Wu, S. Morgan, J. Schneider, M. Anderson, L. Xu, E. Baglietto, M. Bucknor, M. Weathered, and S. Bilbao y Leon, “An Efficient 1-D Thermal Stratification Model for Pool-type Sodium-Cooled Fast Reactors,” Nuclear Technology, 206(10), 1465-1480 (March 2020). (Paper) (DOI)
  18. K. A. Britton and Z. Wu, “Reactor Physics Evaluation of the TRIGA LEU Fuel in the 20MW NIST Research Reactor,” Nuclear Engineering and Design, 360, 110469 (2020). (Paper) (DOI)
  19. D. J. Turkoglu, Z. Wu, R. E. Williams, and T. H. Newton, “Neutronic performance characteristics of different LEU fuels in a proposed NIST research reactor,” Annals of Nuclear Energy, 128, 209-215 (June 2019). (Paper) (DOI)
  20. 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)
  21. 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)
  22. 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)
  23. M. Ishii, S. Shi, W. S. Yang, Z. Wu, S. Rassame, and Y. Liu, “Novel Modular Natural Circulation BWR Design and Safety Evaluation,” Annals of Nuclear Energy, 85, 220-227 (2015). (Paper) (DOI)
  24. S. Shi, Z. Wu, Z. Li, J. P. Schlegel, C. S. Brooks, J. Eoh, Y. Yan, Y. Liu, W. S. Yang, and M. Ishii, “Experimental Study of Natural Circulation Instability with Void Reactivity Feedback during Startup Transients for a BWR-Type SMR,” Progress in Nuclear Energy, 83, 73-81 (2015). (Paper) (DOI)
  25. Z. Wu and H. S. Abdel-Khalik, “Hybrid Biasing Approaches for Global Variance Reduction,” Applied Radiation and Isotopes, 72, 83-88 (2013). (Paper) (DOI)
  26. 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)
  27. Q. Lin and Z. Wu, “Study on Data Processing Method for Double-detector Natural Gamma Ray Spectral Logging Tool,” Journal of Jianghan Petroleum Institute, China, 23(4) 28-30, (2001). (In Chinese) (Paper)

Refereed Full Conference Papers

  1. J. Faulkner, B. Petrovic, K. Ramey, Z. Wu, C. Lu, E. Losa, G. Chee, J. Gonzales, and I. Hill, “Recoverable Energy per Fission Discrepancies in NEA FHR Benchmark Depletion Studies,” the International Conference on Mathematics and Computation Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Ontario, Canada, August 13-17 (2023). (Paper) (Presentation)
  2. T. Liu, Z. Wu, M. Bensi, K. Goth, Z. Ma, and R. Schneider, “Assessment of Uncertainty in Scenario Development for External Hazard Probabilistic Risk Assessment for Nuclear Power Plants,” _the 18th International Probabilistic Safety Assessment and Analysis (PSA 2023), _Knoxville, TN, USA, July 15–20 (2023). (Paper) (Presentation)
  3. M. Bensi, Z. Wu, K. Groth, Z. Ma, R. Schneider, K. F. Najarkolaie, T. Liu, A. Al-Douri, and C. Levine, “Identification and Prioritization of Sources of Uncertainty in External Hazard Probabilistic Risk Assessment: Project Update,” _the 18th International Probabilistic Safety Assessment and Analysis (PSA 2023), _Knoxville, TN, USA, July 15–20 (2023). (Paper) (Presentation)
  4. B. Goddard, Z. Crouch, Z. Wu, and B. Impson, “PBR Pebble Sensitivity Analyses for Material Accountancy Purposes,” Proceedings of the INMM and ESARDA Joint Meeting, Vienna, Austria, May 22-26 (2023). (Paper)
  5. M. Bensi, K. Groth, Z. Wu, Z. Ma, R. Schneider, A. Al-Douri, S. Mohammadi, T. Liu, and C. Levine, “Identifying and Prioritizing Sources of Uncertainty in External Hazard Probabilistic Risk Assessment: Project Activities and Progress,” the 16th Probabilistic Safety Assessment and Management conference – PSAM 16,  June 26 – July 1, Honolulu, Hawaii (2022). (Paper) (Presentation)
  6. M. Bensi, S. Mohammadi, N. Ghosh, T. Liu, C. Levine, A. Al-Douri, R. Schneider, Z. Wu, K. Groth, and Z.  Ma, “Uncertainty in External Hazard Probabilistic Risk Assessment (PRA): A Structured Taxonomy,” the 16th Probabilistic Safety Assessment and Management conference – PSAM 16, June 26 – July 1, Honolulu, Hawaii (2022). (Paper) (Presentation)
  7. C. Lu and Z. Wu, “A Preconceptual Design of an Inverted Stable-Salt Reactor,” PHYSOR 2022 – Advancements in Reactor Physics To Leap Forward Reactor Operation and Deployment, Pittsburgh, PA, May 15-20 (2022). (Paper) (DOI) (Presentation)
  8. M. H. Elhareef and Z. Wu , “Extension of the PINN Diffusion Model to k-eigenvalue Problems,” PHYSOR 2022 – Advancements in Reactor Physics To Leap Forward Reactor Operation and Deployment, Pittsburgh, PA, May 15-20 (2022). (Paper) (DOI) (Presentation)
  9. R. Umretiya, T. Liu, Z. Wu, J. Rojas, D. Lee, M. Anderson, and R. B. Rebak, “Surface Characteristics of Three Accident Tolerant Fuel Cladding Materials and Their Potential Impact on Critical Heat Flux in LWRs,” the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium, March 6-11 (2022).  (Paper) (Presentation)
  10. B. Petrovic, K. Ramey, I. Hill, E. Losa, M. Elsawi, Z. Wu, C. Lu*, J. Gonzales, D. Novog, G. Chee, K. Huff, M. Margulis, N. Read, and E. Shwageraus, “Preliminary Results of the NEA FHR Benchmark Phase I-A and I-B (Fuel Element 2-D Benchmark),” the International Conference on Mathematics and Computation Methods Applied to Nuclear Science and Engineering (M&C 2021), Raleigh, NC, October 3-7 (2021). (Paper) (DOI) (Presentation)
  11. M. H. Elhareef, Z. Wu, and Y. Ma, “Physics-Informed Deep Learning Neural Network Solution to the Neutron Diffusion Model,” the International Conference on Mathematics and Computation Methods Applied to Nuclear Science and Engineering (M&C 2021), Raleigh, NC, October 3-7 (2021). (Paper) (DOI) (Presentation)
  12. T. Liu and Z. Wu, “Sensitivity and Uncertainty Information Incorporated Loss of Flow Accident Analyses for Research Reactors,” Proceedings of the 2020 28th Conference on Nuclear Engineering (ICONE-28), Anaheim, CA, USA, August 2-6 (2020). (Paper) (Presentation) (Best Video Presentation Award)
  13. D. Wang, T. Byambaakhuu, S. Schunert, and Z. Wu, “Solving the S_N Neutron Transport Equation Using High Order Lax–Friedrichs WENO Fast Sweeping Methods,” _the International Conference on Mathematics and Computation Methods applied to Nuclear Science and Engineering (M&C 2019), Portland, OR, August 25-29, on CD-ROM (2019). (Paper)
  14. Z. Wu, J. C. Newman III, and A. C. Taylor III, “Higher Order Accurate k-Eigenvalue Sensitivity Estimation Using the Complex-Step Derivative Method,” the International Conference on Mathematics and Computation Methods applied to Nuclear Science and Engineering (M&C 2019), Portland, OR, August 25-29 (2019). (Paper) (Presentation)
  15. T. Liu and Z. Wu, “Hypothetical Accident Analyses on the Conceptual NIST Reactor with a Split Core Using RELAP5-3D,” the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Portland, OR, August 18-23 (2019). (Paper) (Presentation)
  16. J. Schneider, M. H. Anderson, E. Baglietto, L. Xu, Z. Wu, S. W. Morgan, M. D. Bucknor, M. T. Weathered, S. Bilbao y Leon, “Thermal Stratification Analysis in a Pool-Type Geometry,” the 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Portland, OR, August 18-23 (2019). (Paper)
  17. K. A. Britton and Z. Wu, “An Equilibrium Core Assessment Of the NIST Reactor with GA LEU Fuel Elements,” Proceedings of the 27th International Conference on Nuclear Engineering (ICONE-27), Tsukuba, Ibaraki, Japan, May 19-24 (2019). (Paper)
  18. A. English and Z. Wu, “A Semi-Analytic Solution on The 1D S_N Transport Equation by Decoupling the In-scattering Operator,” _Proceedings of the 4th International Conference on Physics and Technology of Reactors and Applications (PHYTRA-4), Marrakech, Morocco, September 17-19 (2018). (Paper) (Presentation)
  19. K. A. Britton and Z. Wu, “A Neutronics Feasibility Study of the TRIGA LEU Fuel in the 20 MWt NIST Research Reactor,” Proceedings of the 26th International Conference on Nuclear Engineering (ICONE-26), London, England, July 22-26 (2018). (Paper) (Presentation)S. Morgan, S. Bilbao y Leon, Z. Wu, J. Schneider, M. Weathered, M. Anderson, L. Xu, E. Baglietto, M. Bucknor, “Thermal Stratification Modeling for Sodium-Cooled Fast Reactors: A Status Update,” Proceedings of the 26th International Conference on Nuclear Engineering (ICONE-26), London, England, July 22-26 (2018). (Paper) (Presentation) (Poster) [Best student poster award]
  20. D. J. Turkoglu, Z. Wu, R. E. Williams, and T. H. Newton, “Comparison of Neutronics Performance Characteristics of the Proposed NIST Reactor with Different LEU Fuels,” PHYSOR 2018 – Reactor Physics Paving the Way Towards More Efficient Systems, Cancun, Mexico, April 22-26 (2018). (Paper) (Presentation)
  21. Z. Wu and S. Rakhshan Pouri, “A Modified Form of The SAAF Transport Equation with Fully Void-Compatible Feature,” PHYSOR 2018 – Reactor Physics Paving the Way Towards More Efficient Systems, Cancun, Mexico, April 22-26 (2018). (Paper) (Presentation)
  22. Z. Wu, “A Research Reactor Core Design for Advanced Neutron Source,” Proceedings of the 2017 25th International Conference on Nuclear Engineering (ICONE-25), July 2-6, Shanghai, China (2017). (Paper) (Presentation)
  23. Z. Wu and R. E. Williams, “Core Design Studies for A Low-Enriched Uranium Reactor for Cold Neutron Source at NIST,” the Joint International Conference on Reactor Physics PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 1583-1592 (2016). (Paper) (Presentation)
  24. B.D. Eyers, Z. Wu, and B. Kochunas, “Feasibility Investigation of Application of MPACT to Core Design Studies of NBSR-2, A Heavy Water-Reflected, Heterogeneous Fuel Research Reactor,” the Joint International Conference on Reactor Physics PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century, Sun Valley, ID, USA, May 1-5, 1631-1640 (2016). (Paper) (Presentation)
  25. Z. Wu, R. E. Williams, and J. M. Rowe, “Hypothetical Accident Analyses on the Proposed Split Core at NIST Using PARET/ANL Code,” Proceedings of the 17th International Group on Research Reactors (IGORR) Conference, Berlin, Germany, March 13-17 (2016). (Paper)
  26. Z. Wu and R. E. Williams, “A Fast and Self-Consistent Approach for Multi-cycle Equilibrium Core Studies Using Monte Carlo Models,” the Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, TN, April 19-23, on CD-ROM (2015). (Paper)(Presentation) (Poster)
  27. Z. Wu, R. E. Williams, and S. O’Kelly, “Preliminary Studies on a New Reactor and Cold Neutron Sources at NCNR,” Proceedings of the 16th International Group on Research Reactors (IGORR) Conference, Bariloche, Argentina, Nov. 17-21 (2014). (Paper)(Presentation)
  28. 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)
  29. P. McIntyre, A. Sattarov, M. Adams, F. Best, C. Kurwitz, and Z. Wu, “Accelerator-Driven Thorium Cycle Power Reactor: Design and Performance Calculations,” Proceedings of GLOBAL 2003, 1881-1885 (2003). (Paper)

Refereed Conference Summaries

  1. M. H. Elhareef and Z. Wu, “Estimating the Molten Salt Flow Rate for the MSRE Isothermal Transient Benchmark Development,” Trans. Am. Nucl. Soc., 129 (2023). (Paper)The ANS Winter Meeting, Washington D.C., November 12–15 (2023). (Presentation)
  2. B. Goddard, Z. C. Crouch, B. A. Impson, and Z. Wu, “Material Attractiveness of Advanced Nuclear Fuels,” Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC 2023), Washington D.C., November 12–15 (2023). (Abstract) (Presentation)
  3. Z. C. Crouch, B. Goddard, Z. Wu, and B. A. Impson, “Pebble Bed Reactor Neutronics and Isotopic Analysis,” Advances in Nuclear Nonproliferation Technology and Policy Conference (ANTPC 2023), Washington D.C., November 12–15 (2023). (Abstract) (Presentation)
  4. M Elhareef and Z. Wu, “Coupled Neutronics and Thermal Hydraulics Calculations for the MSRE Pump Startup and Coastdown Transients,” _the ANS Student Conference, _University of Tennessee at Knoxville, Knoxville, TN, April 13-15 (2023). (Paper) (Presentation)
  5. W. Strom, M. Elhareef, and Z. Wu, “Importance Sampling Methods to Accelerate PINN Calculations for k-Eigenvalue Neutron Diffusion Problems,” the ANS Student Conference, University of Tennessee at Knoxville, Knoxville, TN, April 13-15 (2023). (Paper) (Poster)
  6. C. Pochron, Z. Wu, N. Mann, and M. Pop, “Neutronics Analysis of Molten Uranium Breeder Reactor with a Code-to-Code Verification,” _the ANS Student Conference, _University of Tennessee at Knoxville, Knoxville, TN, April 13-15 (2023). (Paper) (Lightning Talk)
  7. Z. Crouch, B. Goddard, Z. Wu, and B. Impson, “MCNP Simulations of Various Pebble Models for Pebble Bed Gas Cooled Reactors,” _the ANS Student Conference, _University of Tennessee at Knoxville, Knoxville, TN, April 13-15 (2023). (Paper) (Poster)
  8. B. Impson, Z. Crouch, B. Goddard, and Z. Wu, “Automation of Creating High Fidelity TRISO Particle Fuel Element in MCNP Models,” _the ANS Student Conference, _University of Tennessee at Knoxville, Knoxville, TN, April 13-15 (2023). (Paper) (Poster)
  9. Z. Wu, M. H. Elhareef, M. Fratoni, B. R. Betzler, T. Fei, and K. Harris, “MSRE Transient Benchmark Development and Evaluation: NEUP Project Updates,” Trans. Am. Nucl. Soc., 127 (2022). (Paper) The ANS Winter Meeting, Phoenix, AZ, November 13–17 (2022). (Presentation)
  10. Z. Wu and C. Lu, “Preliminary Fuel Cycle Analysis of the -UB2 Composite Fuels in Pressurized Water Reactors,” Trans. Am. Nucl. Soc., 126(2022). (Paper) (DOI) The ANS Annual Meeting, Anaheim, CA, June 14-16 (2022). (Presentation)
  11. Y. Zou and Z. Wu, “A Multiphysics Framework to Characterize the Fuel Rod and Assembly Bowing Effect in PWRs,” Trans. Am. Nucl. Soc., 126 (2022). (Paper) (DOI) The ANS Annual Meeting, Anaheim, CA, June 14-16 (2022). (Presentation)
  12. T. Liu, Z. Wu, Z. Ma, S. Zhang, and H. Jiang, “An Investigation of MSPI Optimization to Improve NPP Safety and Efficiency,” _the ANS Student Conference, _University of Illinois Urbana-Champaign, Urbana, IL, April 14-16 (2022). (Paper) (Presentation)
  13. M. H. Elhareef and Z. Wu, “Extending the Physics Informed Neural Network Model to Multigroup Neutron Diffusion Problems,” _the ANS Student Conference, _University of Illinois Urbana-Champaign, Urbana, IL, April 14-16 (2022). (Paper) (Presentation)
  14. C. Lu, Z. Wu, E. Mulder, and S. Sen, “A Direct Comparison of High-Order and Low-Order Neutronics Calculations of the 165MWth Xe-100 Reactor,” Trans. Am. Nucl. Soc., 124, 563-566 (2021). (Paper) (DOI) ANS Virtual National Meeting, June 14-16 (2021). (Presentation)
  15. T. Liu and Z. Wu, “Adjoint Solution of Time-dependent Multigroup Diffusion Model with Generalized Temporal and Spatial Boundary Conditions,” ANS Student Conference, North Carolina State University, Raleigh, NC, Virtual Meeting, April 8-10 (2021) [Best paper award in the track of reactor physics]. (Paper) (Presentation)
  16. R. Blackwell, A. Chadwick, D. Monge, M. Murphy, and Z. Wu, “Space Nuclear Thermal Propulsion Design,” ANS Student Conference, North Carolina State University, Raleigh, NC, Virtual Meeting, April 8-10 (2021). (Paper) (Presentation)
  17. L. Carlson, Z. Wu, J. Olson, and L. Liu, “A LOCE Estimation on HALEU Fuels for Small Modular Reactors,” Trans. Am. Nucl. Soc., 123, 1073-1075 (2020). (Paper) (DOI) ANS Virtual Winter Meeting, November 16-19 (2020). (Presentation)
  18. 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)
  19. C. Lu, Z. Wu, B. Ward, and H. Bindra, “Validation of the 1-D Thermal Stratification Model in Gallium Environment,” Trans. Am. Nucl. Soc., 122, 851-854 (2020). (Paper) (DOI) ANS National Meeting, June 7-11, originally planned to be hold at Phoenix, AZ, later converted to an online virtual meeting due to the COVID-19 pandemic (2020). (Presentation)
  20. C. Lu, Z. Wu, J. Schneider, M. Anderson, L. Xu, E. Baglietto, M. Bucknor, M. Weathered, S. Morgan, S. Bilbao y Leon, “Thermal Stratification Analysis for Sodium-cooled Fast Reactors: Development of the 1-D System Model,” Trans. Am. Nucl. Soc., 121, 1703-1706 (2019). (Paper) (DOI) ANS Winter Meeting, November 17-21, Washington D.C. (2019). (Presentation)
  21. D. Wang and Z. Wu, “A Modified Step Characteristic Method for Solving the S_N Transport Equation,” _Trans. Am. Nucl. Soc., 121, 802-804 (2019). (Paper) (DOI) ANS Winter Meeting, November 17-21, Washington D.C. (2019). (Presentation)
  22. Z. Wu, “Extending Wang’s 1D Sn Analytic Solution to Heterogeneous Problems with No Iteration on Interfacial Fluxes,” Trans. Am. Nucl. Soc., 121, 819-822 (2019). (Paper) (DOI) ANS Winter Meeting, November 17-21, Washington D.C. (2019). (Presentation)
  23. T. Liu and Z. Wu, “Comparing the Steady State System Modeling Results of the Conceptual NIST Reactor with ANL-PARET and RELAP5-3D,” ANS Student Conference, Virginia Commonwealth University, Richmond, VA, April 4-6 (2019). (Paper) (Presentation)
  24. R. Kelley and Z. Wu, “On the Effect of the Diffusion Coefficient Treatment in Finite Difference Schemes of Diffusion Equation,” ANS Student Conference, Virginia Commonwealth University, Richmond, VA, April 4-6 (2019). (Paper) (Presentation)
  25. A. English and Z. Wu, “A Semi-Analytic Solution to the 1D SN Transport Equation for a Multi-Region Problem,” ANS Student Conference, Virginia Commonwealth University, Richmond, VA, April 4-6 (2019). (Paper) (Presentation)
  26. J. Schneider, M. Anderson, E. Baglietto, S. Bilbao y Leon, M. Bucknor, S. Morgan, M. Weathered, Z. Wu, and L. Xu, “Thermal Stratification Modeling and Analysis for Sodium Fast Reactor Technology,” Trans. Am. Nucl. Soc., 119, 142-145 (2018). (Paper) ANS Winter Meeting, November 11–15, Orlando, FL (2018). (Presentation)
  27. J. Liang, Z. Wu, and H. S. Abdel-Kalik, “Nuclear Data Sensitivity Analysis in OpenMC Using the GPT-Free Method,” Trans. Am. Nucl. Soc., 118, 921-924 (2018). (Paper) ANS Annual Meeting, June 17-21, Philadelphia, PA (2018). (Presentation)
  28. S. Rakhshan Pouri, S. Phongikaroon, and Z. Wu, “Diffusion Model and Artificial Neural Intelligence (ANI) Comparison for Cyclic Voltammetry Prediction of Uranium and Zirconium Chloride in LiCl-KCl Eutectic Salt,” Trans. Am. Nucl. Soc., 118, 95-98 (2018). (Paper) ANS Annual Meeting, June 17-21, Philadelphia, PA (2018). (Presentation)
  29. R. Leos, Z. Wu, R. E. Williams, and X. Yang, “Integrating Sudo-Kaminaga Correlation to the Safety Analysis Code PARET-ANL,” Trans. Am. Nucl. Soc., 116, 1369-1172, (2017). (Paper) ANS National Meeting, San Francisco, CA, June 11-15 (2017). (Presentation)
  30. Z. Wu and R. E. Williams, “The Water Ingress Effects on the Reactivity Change of the Conceptual Designed Reactor at NIST,” Trans. Am. Nucl. Soc., 115, 1186-1188 (2016). (Paper)  ANS Winter Meeting, Las Vegas, NV, November 6-10 (2016). (Presentation)
  31. A. Oredeko, X. Yang, and Z. Wu, “MOCUM Verification with a Heterogeneous MOX Whole Core C5G7 Benchmark Problem,” Trans. Am. Nucl. Soc., 115, 1344-1346 (2016). (Paper) ANS Winter Meeting, Las Vegas, NV, November 6-10 (2016). (Presentation)
  32. Z. Wu, R. E. Williams, and T. H. Newton, “Reactivity Coefficient Calculation for a Low-Power LEU Research Reactor,” Trans. Am. Nucl. Soc., 114, 814-816 (2016). (Paper) ANS National Meeting, New Orleans, LA, June 12-16 (2016). (Presentation)
  33. D. Prevost, Z. Wu, and R. E. Williams, “Feasibility Studies on a Hexagonal-Lattice Core for a World-Class Cold Neutron Source,” Trans. Am. Nucl. Soc., 114, 671-674 (2016). (Paper) ANS National Meeting, New Orleans, LA, June 12-16 (2016). (Presentation)
  34. 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)
  35. Z. Wu, R. E. Williams, and J. M. Rowe, “Preliminary Safety Analyses on a Conceptual LEU Fueled Research Reactor at NIST,” Trans. Am. Nucl. Soc., 113, 1397-1400 (2015). (Paper) ANS Winter Meeting, Washington D.C., November 8-12 (2015).(Presentation)
  36. Z. Wu, M. Carlson, R. E. Williams, S. O’Kelly, and J. M. Rowe, “A Novel Compact Core Design for Beam Tube Research Reactors,” Trans. Am. Nucl. Soc., 112, 795-798 (2015). (Paper) ANS National Meeting, San Antonio, TX, June 7-11 (2015).(Presentation)
  37. Z. Wu, W. Yang, S. Shi, and M. Ishii, “Core Design Studies for a BWR-Based Small Modular Reactor with Long-Life Core,” Trans. Am. Nucl. Soc., 112, 751-754 (2015). (Paper) ANS National Meeting, San Antonio, TX, June 7-11 (2015). (Presentation)
  38. Z. Wu and H. S. Abdel-Khalik, “Further GPT-free Developments for Monte Carlo Models,” Trans. Am. Nucl. Soc., 107, 981-984 (2012). (Paper) ANS Winter Meeting, San Diego, CA, Nov. 11-15 (2012). (Presentation)
  39. Z. Wu, C.B. Kennedy, and H.S. Abdel-Khalik, “Application of GPT-Free Method to Sensitivity Analysis in Monte Carlo Models,” Trans. Am. Nucl. Soc., 106, 763-766 (2012). (Paper) ANS Annual Meeting, Chicago, IL, Jun. 24-28 (2012). (Presentation)
  40. Z. Wu, Q. Zhang and H. S. Abdel-Khalik, “A Hybrid Variance Reduction Method Based on Gaussian Process for Core Simulation”, Trans. Am. Nucl. Soc., 105, 872-874 (2011). (Paper) ANS Winter Meeting, Washington D.C., Oct. 30 – Nov. 3 (2011). (Presentation)
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