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2025

  1. B. Impson, M. H. Elhareef, Z. Wu, and B. Goddard, “Definitive and Stochastic Fuel Distributions in Pebble Bed Reactors,” Progress in Nuclear Energy, Under review (March 2025);
  2. M. Manuel, C. Warren, M. Divittorio, B. Goddard, and Z. Wu, “Innovative Fuel Designs for Pebble Bed Reactors,” the ANS Student Conference, University of New Mexico, Albuquerque, NM, April 3-5 (2025). (Paper)(Presentation)
  3. M. E. Grove, M. H. Elhareef, and Z. Wu, “The Effect of Nuclear Data Discrepancies on Criticality Simulations of Molten Salt Fast Reactors,” the ANS Student Conference, University of New Mexico, Albuquerque, NM, April 3-5 (2025). (Paper)(Poster)
  4. C. Bales and Z. Wu, “Point Kinetic Behavior of Molten Salt Reactors Using Delayed Differential Equation Solver in MATLAB,” the ANS Student Conference, University of New Mexico, Albuquerque, NM, April 3-5 (2025). (Paper)(Poster)
  5. M. H. Elhareef and Z. Wu, “Benchmarking a Point Reactor Kinetics Method with Delayed Neutron Precursors Transport Using Data from Molten Salt Reactor Experiment,” Annals of Nuclear Energy, 217, 111366, Available online (March 2025). (Paper)(DOI)
  6. 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, Accepted (February 2025). (Paper)(DOI)

2024

  1. M. H. Elhareef and Z. Wu, “Effect of Turbulent Diffusion on Delayed Neutron Precursors in the Molten Salt Reactor Experiment (MSRE),” Trans. Am. Nucl. Soc., 131 (2024). (Paper)(DOI)The ANS Winter Meeting, Orlando, FL, November 17–21 (2024). (Presentation)
  2. K. S. Mehta, B. Goddard, and Z. Wu, “Neutronics Analysis on High Temperature Gas Cooled Pebble Bed Reactors by Coupling Monte Carlo Method and Discrete Element Method,” Energies, 17, 5188 (October 2024). (Paper) (DOI)
  3. N. Mann, Z. Wu, and M. G. M. Pop, “Molten Uranium Breeder Reactor (MUBR) and Its Development Steps,” Nuclear Science and Technology Open Research, 2, 68 (October 1st, 2024). (Paper) (DOI)
  4. M. H. Elhareef and Z. Wu, “Uncertainty Analysis on the Pump Flow Transient Phenomena in the Molten Salt Reactor Experiment,” Trans. Am. Nucl. Soc., 130 (2024). (Paper)The ANS Annual Meeting, Las Vegas, NV, June 16–19 (2024). (Presentation)
  5. 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)
  6. M. H. Elhareef, T. Fei, and Z. Wu, “Computational Modeling and Verification of MSR Transients via MSRE Reactivity Insertion Tests,” PHYSOR 2024 – Beyond the Blueprint: Pioneering Reactor Physics for Real-World Implementation, San Francisco, CA, April 21–24 (2024). (Paper) (Presentation)
  7. J. P. Shurie and Z. Wu, “Neutronics Benchmark Studies on the Hallam Nuclear Power Facility (HNPF) First Core Loading,” the ANS Student Conference, the Pennsylvania State University, University Park, PA, April 4-6 (2024). (Paper) (Presentation)
  8. J. P. Shurie, R. Krushelnisky, C. T. King, W. E. Strom, and Z. Wu, “A Novel Stationary Molten Salt Reactor Design for Spent Nuclear Fuel Burning,” the ANS Student Conference, the Pennsylvania State University, University Park, PA, April 4-6 (2024). (Paper) (Presentation)
  9. K. S. Mehta, Z. Wu, and B. Goddard, “A High-Fidelity Multiphysics Computational Model for Pebble Bed Gas Reactor Based on Open-Source Software,” the ANS Student Conference, the Pennsylvania State University, University Park, PA, April 4-6 (2024). (Paper) (Presentation) (Poster)
  10. B. A. Impson, B. Goddard, and Z. Wu, “An INDEPTH Analysis of Spent Pebbles,” the ANS Student Conference, the Pennsylvania State University, University Park, PA, April 4-6 (2024). (Paper) (Presentation) (Best oral presentation award)
  11. L. Diehl and Z. Wu, “Neutronics Benchmark Development of the ALFRED Alike Reactor Using MCNP Code,” the ANS Student Conference, the Pennsylvania State University, University Park, PA, April 4-6 (2024). (Paper) (Presentation) (Poster)
  12. 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)

2023

  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. 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. 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)
  6. 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)
  7. 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)
  8. 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)
  9. 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)
  10. Z. Wu, N. Mann, and M. Pop, “Molten Uranium Breeder Reactor – a Paradigm Change in Fuel Cycle,” Proceedings of the 30th Conference on Nuclear Engineering (ICONE-30), Kyoto, Japan, May 21-26 (2023). (Abstract) (Presentation)
  11. 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)
  12. 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)
  13. 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)
  14. 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)
  15. 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)
  16. 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)
  17. 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)

2022

  1. 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)
  2. 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)
  3. 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)
  4. 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)
  5. 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)
  6. 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)
  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. 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)
  10. 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)
  11. 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)
  12. 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)
  13. 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)

2021

  1. 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)
  2. 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)
  3. 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)
  4. 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)
  5. 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)
  6. 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)
  7. 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)
  8. 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)

2020

  1. 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)
  2. 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)
  3. 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)
  4. 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)
  5. 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)
  6. 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)
  7. 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)
  8. 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)
  9. 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)
  10. 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)
  11. 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)
  12. 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)

2019

  1. 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, Washington D.C., November 17-21 (2019). (Presentation)
  2. 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, Washington D.C., November 17-21 (2019). (Presentation)
  3. 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, Washington D.C., November 17-21 (2019). (Presentation)
  4. 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)
  5. 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)
  6. 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)
  7. 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)
  8. 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)
  9. 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)
  10. 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)
  11. 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)
  12. 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)
  13. 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)

2018

  1. 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)
  2. 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)
  3. 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]
  4. 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)
  5. 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)
  6. 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)
  7. 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)

2017

  1. 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)
  2. 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)
  3. 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)

2016

  1. 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)
  2. 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)
  3. 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)
  4. 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)
  5. 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)
  6. 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)
  7. 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)
  8. 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)

2015

  1. 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)
  2. 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)
  3. 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)
  4. 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)
  5. 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)
  6. 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)
  7. 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)

2014 and before

  1. 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)
  2. Z. Wu and H. S. Abdel-Khalik, “Hybrid Biasing Approaches for Global Variance Reduction,” Applied Radiation and Isotopes, 72, 83-88 (2013). (Paper) (DOI)
  3. 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)
  4. 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)
  5. 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)
  6. 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)
  7. 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)
  8. 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)
  9. 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)
  10. P. McIntyre, M. Adams, F. Best, A. Sattarov, C. Kurwitz, Z. Wu, A. McInturff, B. Rogers, M. Yavuz, and C. Meitzler, “Accelerator-Driven Thorium Cycle: New Technology Makes It Feasible,” Transaction of Conference ICAPP’02: 2002 International Congress on Advances in Nuclear Power Plants (2002). (Abstract)
  11. 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)