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Journal Articles<\/h2>\n\n\n\n

2026<\/h3>\n\n\n\n
    \n
  1. Nguyen, K. H. N., Kim, J., Rollins, N., Luque-Gutierrez, J. C., Hou, J., Lawrence, S., \u2026 & Abdo, M. (2026). Optimizing Pressurized-Water Reactor Equilibrium Cycle Using a Novel Loading Pattern Encoding and Rule-based Genetic Crossover Operators. Nuclear Engineering and Technology, 104113. https:\/\/doi.org\/10.1016\/j.net.2026.104113<\/a><\/li>\n<\/ol>\n\n\n\n

    2025<\/h3>\n\n\n\n
      \n
    1. Trivedi, I., Delipei, G. K., Hou, J., Grasso, G., Ivanov, K. (2025). Development and Application of Two-step Uncertainty Propagation and Sensitivity Analysis Methodology for Fast Reactor Safety Analysis. Nuclear Engineering and Design. 433 (113882). https:\/\/doi.org\/10.1016\/j.nucengdes.2025.113882<\/a><\/li>\n<\/ol>\n\n\n\n

      2024<\/h3>\n\n\n\n
        \n
      1. Rivas, A., Delipei, G. K., & Hou, J. (2024). Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin.\u00a0ASME Journal of Nuclear Engineering and Radiation Science. April 2025; 11(2): 021801. https:\/\/doi.org\/10.1115\/1.4066777<\/a> <\/li>\n\n\n\n
      2. Rivas, A., Delipei, G. K., & Hou, J. (2024). Modeling a generic Pebble Bed High-Temperature Gas-Cooled Reactor to perform load-following using Simulink. Nuclear Engineering and Design, 428, 113506. https:\/\/doi.org\/10.1016\/j.nucengdes.2024.113506<\/a><\/li>\n\n\n\n
      3. Rivas, A., Delipei, G. K., & Hou, J. (2024). A System Predictive Maintenance Framework for Advanced Reactors Using a Data-Driven Digital Twin. Nuclear Science and Engineering, 1-30. https:\/\/doi.org\/10.1080\/00295639.2024.2372515<\/a><\/li>\n\n\n\n
      4. Nguyen, K. H., Rivas, A., Delipei, G. K., & Hou, J. (2024). Reinforcement Learning-Based Control Sequence Optimization for Advanced Reactors. Journal of Nuclear Engineering. https:\/\/doi.org\/10.3390\/jne5030015<\/a><\/li>\n\n\n\n
      5. Rivas, A., Delipei, G. K., Davis, I., Bhongale, S., Yang, J., & Hou, J. (2024). A component diagnostic and prognostic framework for pump bearings based on deep learning with data augmentation. Reliability Engineering & System Safety, 110121. https:\/\/doi.org\/10.1016\/j.ress.2024.110121<\/a><\/li>\n\n\n\n
      6. Rollins, N., Allan, I. & Hou, J. (2024) Prototyping of a Machine Learning-Based Burnup Measurement Capability for Pebble Bed Reactor Fuel. Nuclear Science and Engineering. https:\/\/doi.org\/10.1080\/00295639.2024.2328937<\/a><\/li>\n\n\n\n
      7. Rivas, A., Delipei, G. K., Davis, I., Bhongale S. & Hou, J. (2024) A System Diagnostic and Prognostic Framework Based on Deep Learning for Advanced Reactors. Progress in Nuclear Energy. https:\/\/doi.org\/10.1016\/j.pnucene.2024.105114<\/a><\/li>\n\n\n\n
      8. Mikouchi-Lopez, J., Delipei, G.*, & Hou, J. (2024). Development and evaluation of parallel simulated annealing algorithm for reactor core optimization problems. Nuclear Science and Technology Open Research, 2(5), 5. https:\/\/doi.org\/10.12688\/nuclscitechnolopenres.17464.2<\/a><\/li>\n\n\n\n
      9. Baker, U., Choi; Y-J, Rollins, N., Nguyen, K., Jung, WH, Whitmeyer, A., Hou, J. (2023) Source Term Analysis of FeCrAl Accident Tolerant Fuel using MELCOR. Annals of Nuclear Energy. https:\/\/doi.org\/10.1016\/j.anucene.2024.110482<\/a><\/li>\n<\/ol>\n\n\n\n

        2023<\/h3>\n\n\n\n
          \n
        1. Kan, N., Hou, J. An Efficient High-to-low Iterative Method for Light Water Reactor Analysis Based on NEAMS Tools. Nuclear Science and Engineering, 1-17. https:\/\/doi.org\/10.1080\/00295639.2022.2158706<\/a><\/li>\n<\/ol>\n\n\n\n

          2022<\/h3>\n\n\n\n
            \n
          1. Andersen B, Hou J, Godfrey A, Kropaczek D. A Novel Method for Controlling Crud Deposition in Nuclear Reactors Using Optimization Algorithms and Deep Neural Network Based Surrogate Models. Eng. 2022; 3(4):504-522. https:\/\/doi.org\/10.3390\/eng3040036<\/a><\/li>\n\n\n\n
          2. Chen J., Hou J., Ivanov K. Hybrid Neutronics Method with Novel Fission Diffusion Synthetic Acceleration for Criticality Calculations. Nuclear Engineering and Technology. https:\/\/doi.org\/10.1016\/j.net.2022.12.022<\/a><\/li>\n\n\n\n
          3. Trivedi, I., Delipei, G., Hou, J., Grasso, G., Ivanov, K. Development and Application of Two-step Uncertainty Propagation and Sensitivity Analysis Methodology for Fast Reactor Safety Analysis. Progress in Nuclear Energy. (submitted for review).<\/li>\n\n\n\n
          4. Delipei, G.K., Rouxelin, P., Abarca, A., Hou, J., Avramova, M., Ivanov, K (2022). CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification. Energies,15(14):5226. https:\/\/doi.org\/10.3390\/en15145226<\/a><\/li>\n\n\n\n
          5. Rivas, A., Martin, N., Bays, S., Palmiotti, G., Xu, Z., & Hou, J. (2022). Nuclear Data Uncertainty Propagation Applied to the Versatile Test Reactor Conceptual Design. Nuclear Engineering and Design, 392(111744). https:\/\/doi.org\/10.1016\/j.nucengdes.2022.111744<\/a><\/li>\n\n\n\n
          6. Rivas, A., Delipei, G., Hou J. (2022) Predictions of Component Remaining Useful Lifetime Using Bayesian Neural Network. Progress in Nuclear Energy. 146(104143). https:\/\/doi.org\/10.1016\/j.pnucene.2022.104143<\/a><\/li>\n<\/ol>\n\n\n\n

            2021<\/h3>\n\n\n\n
              \n
            1. Xu Y, Hou J, Ivanov K. Methodology for Discontinuity Factors Generation for Simplified P3 Solver Based on Nodal Expansion Formulation. Energies. 2021; 14(20): 6478. https:\/\/doi.org\/10.3390\/en14206478<\/a><\/li>\n\n\n\n
            2. G. Delipei, J. Hou, M. Avramova, K. Ivanov. Summary of Comparative Analysis and Conclusions from OECD\/NEA LWR-UAM Benchmark Phase I. Nuclear Engineering and Design. 384 (2021): 111474. https:\/\/doi.org\/10.1016\/j.nucengdes.2021.111474<\/a><\/li>\n\n\n\n
            3. Avramova, M.; Abarca, A.; Hou, J.; Ivanov, K. Innovations in Multi-Physics Methods Development, Validation, and Uncertainty Quantification. Journal of Nuclear Engineering. 2021, 2, 44-56. https:\/\/doi.org\/10.3390\/jne2010005<\/a><\/li>\n\n\n\n
            4. A. Rivas, N. Stauff, T. Sumner, J. Hou, \u201cPropagating Neutronic Uncertainties for FFTF LOFWOS Test# 13.\u201d Nuclear Engineering and Design, 375 (2021): 111047. https:\/\/doi.org\/10.1016\/j.nucengdes.2020.111047<\/a><\/li>\n<\/ol>\n\n\n\n

              2020<\/h3>\n\n\n\n
                \n
              1. M. Altahhan, S. Bhaskar, D. Ziyad, P. Balestra, C. Fiorina, J. Hou, N. Smith, M. Avramova, \u201cPreliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam,\u201d Nuclear Engineering and Design, 369 (2020). https:\/\/doi.org\/10.1016\/j.nucengdes.2020.110826<\/a>.<\/li>\n\n\n\n
              2. I. Trivedi, J. Hou, G. Grasso, K. Ivanov, F. Franceschini, \u201cNuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-cooled Fast Reactors,\u201d Science and Technology of Nuclear Installations, vol. 2020, Article ID 3961095, 2020. https:\/\/doi.org\/10.1155\/2020\/3961095<\/a>.<\/li>\n\n\n\n
              3. J. Hou, M. Avramova, K. Ivanov, \u201cBest-Estimate Plus Uncertainty Framework for Multi-Scale, Multi-Physics Light Water Reactor Core Analysis,\u201d Science and Technology of Nuclear Installations, vol. 2020, Article ID 7526864, 2020. https:\/\/doi.org\/10.1155\/2020\/7526864<\/a>.<\/li>\n\n\n\n
              4. C. Wan, Z. Sui, L. Cao, Z. Liu, B. Wang, J. Hou, \u201cNuclear-data Uncertainty Propagation in Transient Simulation for the C5G7-TD Benchmark Problem,\u201d Annals of Nuclear Energy, 140, 107122 (2020). https:\/\/doi.org\/10.1016\/j.anucene.2019.107122<\/a>.<\/li>\n\n\n\n
              5. K. Zeng, N.E. Stauff, J. Hou, T.K. Kim, \u201cDevelopment of Multi-Objective Core Optimization Framework and Application to Sodium-cooled Fast Test Reactors,\u201d Progress of Nuclear Energy, 120,103184 (2020). https:\/\/doi.org\/10.1016\/j.pnucene.2019.103184<\/a>.<\/li>\n<\/ol>\n\n\n\n

                2019<\/h3>\n\n\n\n
                  \n
                1. K. Zeng, J. Hou, M. Jessee, K. Ivanov, \u201cUncertainty Quantification and Propagation of Multi-Physics Simulation of the Pressurized Water Reactor Core,\u201d Nuclear Technology, 205:12, 1618-1637 (2019). https:\/\/doi.org\/10.1080\/00295450.2019.1580533<\/a>.<\/li>\n\n\n\n
                2. S. Sihlangu, V. Naicker, J. Hou, F. Reitsma, \u201cFurther Development of Methodology to Model TRISO and BISO Particles and Related Uncertainty Quantification using SCALE 6,\u201d Journal of Nuclear Science and Technology, 56:8, 690-709 (2019). https:\/\/doi.org\/10.1080\/00223131.2019.1617204<\/a>.<\/li>\n<\/ol>\n\n\n\n

                  2016 – 2018<\/h3>\n\n\n\n
                    \n
                  1. Q. Li, Y. Jiao, M. Avramova, P. Chen, J. Yu, J. Chen, J. Hou, \u201cDevelopment, Verification and Application of a New Model for Active Nucleation Site Density in Boiling Systems,\u201d Nuclear Engineering and Design, 328, pp. 1-9, (2018). https:\/\/doi.org\/10.1016\/j.nucengdes.2017.12.027<\/a>.<\/li>\n\n\n\n
                  2. L. Wang, J. Guo, F. Li, J. Hou and K. Ivanov, \u201cEffect of Nuclear Data on Fuel Element Neutronic Characteristics of Pebble-bed High Temperature Gas-cooled Reactor,\u201d Atomic Energy Science and Technology, 51, 9 (2017). [In Chinese]<\/li>\n\n\n\n
                  3. J. Hou, K. Ivanov, V. Boyarinov and P. Fomichenko, \u201cOECD\/NEA Benchmark for Time-Dependent Neutron Transport Calculations without Spatial Homogenization,\u201d Nuclear Engineering and Design, 317, pp. 177-189 (2017). https:\/\/doi.org\/10.1016\/j.nucengdes.2017.02.008<\/a>.<\/li>\n\n\n\n
                  4. J. Hou, S. Qvist, R. Kellogg and E. Greenspan, \u201c3D In-core Fuel Management Optimization for Breed-and-Burn Reactors,\u201d Progress in Nuclear Energy, 88, pp. 58-74 (2016). https:\/\/doi.org\/10.1016\/j.pnucene.2015.12.002<\/a>.<\/li>\n<\/ol>\n\n\n\n

                    Conference Proceedings and Transactions<\/h2>\n\n\n\n

                    2024<\/h3>\n\n\n\n
                      \n
                    1. Rollins, N.<\/em> , Hou, J. \u201cImpact of Cooldown on Pebble Fuel Burnup Prediction Using Machine Learning\u201d, International Conference on Physics of Reactors (PHYSOR), San Francisco, California, USA, April, 2024.<\/li>\n<\/ol>\n\n\n\n

                      2023<\/h3>\n\n\n\n
                        \n
                      1. Rivas, A.<\/em>, Delipei, G.K.*, Satyan, B., Davis, I., & Hou, J. (2023, August). Preliminary Investigation on Multivariate Control Scheme and Optimization for Advanced Reactors. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada.<\/li>\n\n\n\n
                      2. Delipei, G.K.*, Mikouchi-Lopez, J.<\/em>, Rouxelin, P. & Hou, J. (2023, August). Reactor Core Loading Pattern Optimization with Reinforcement Learning. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada.<\/li>\n\n\n\n
                      3. Rollins, N.<\/em>, Allen, I.<\/em>, & Hou, J. (2023, August). Burnup Correlation with Gamma Spectrum of the Pebble Bed Reactor Fuel Using Machine Learning. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada.<\/li>\n\n\n\n
                      4. Nguyen, K.<\/em>, Rivas, A.<\/em>, Delipei, G.K.*, & Hou, J. (2023, August). Preliminary Study on Control Sequence Optimization for Advanced Reactors using Reinforcement Learning. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada.<\/li>\n\n\n\n
                      5. Nguyen, K.<\/em>, Ogujiuba, K.<\/em>, & Hou, J. (2023, August). Summary of comparative study on Deterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD). International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023), Niagara Falls, Canada.<\/li>\n\n\n\n
                      6. Baker, U.<\/em>, Lindley, B., Nguyen, K. H. N., Choi, Y. J., Hou, J. (2023) Analysis of Accident Tolerant Fuel Design in Light Water Reactors. Transactions of the American Nuclear Society, Vol. 128, 302-305, 2023 ANS Annual Meeting, Indianapolis, IN, June 11\u201314, 2023.<\/li>\n\n\n\n
                      7. Nguyen, K.<\/em>, Choi, Y. J.,  Abdo, M. G., Kim, J., Wang, C., Hou, J. (2023) Optimization of Light Water Reactor Core Design Using a Genetic Algorithm in the RAVEN Framework. Transactions of the American Nuclear Society, Vol. 128, 664-667, 2023 ANS Annual Meeting, Indianapolis, IN, June 11\u201314, 2023.<\/li>\n<\/ol>\n\n\n\n

                        <\/p>\n\n\n\n

                        2022<\/h3>\n\n\n\n
                          \n
                        1. Bullerwell, L., Abarca, A., Avramova, M., Hou, J. (2022) A Three-Dimensional Cartesian Thermal-Hydraulic Solver in the Residual Formulation of CTF. Transactions of the American Nuclear Society, Vol. 127, 1226-1229, 2022 ANS Winter Meeting, Phoenix, AZ, November 13\u201317, 2022.<\/li>\n\n\n\n
                        2. Rivas, A., Delipei, G.K., Davis, I., Bhongale, S., Yang, J., Hou, J. (2022) Fault Characterization of Centrifugal Pump Bearings Using Deep Neural Networks. Transactions of the American Nuclear Society, Vol. 127, 846-849, 2022 ANS Winter Meeting, Phoenix, AZ, November 13\u201317, 2022.<\/li>\n\n\n\n
                        3. Ogujiuba, K., Nguyen, K.H.N., Choi, Y-J., Hou, J. (2022) Neutronics Assessment of Advanced Fuel Claddings in the Equilibrium LWR Core Design. Transactions of the American Nuclear Society, Vol. 127, 569-572, 2022 ANS Winter Meeting, Phoenix, AZ, November 13\u201317, 2022.<\/li>\n\n\n\n
                        4. Fustero, J. Powell, W., Ni, K., Kulkarni, K.A, Delipei, G.K., Holler, D., Hou, J. Delchini, M. Smith, R., Avramova, M. (2022) High-to-Low Multi-Physics Modeling and Uncertainty Propagation Using NEAMS Tools. Transactions of the American Nuclear Society, Vol. 127, 438-441, 2022 ANS Winter Meeting, Phoenix, AZ, November 13\u201317, 2022.<\/li>\n\n\n\n
                        5. Choi, Y-J., Palamone, G., Heagy, S., Frepoli, C., Ogujiuba, K., Rollins, N., Delipei, G., Hou, J., & Blakely, C. (2022) Modeling and Simulation Needs and Capabilities for Artificial Intelligence Based Plant Reload Optimization Platform. Probabilistic Safety Assessment and Management PSAM 16, Honolulu, Hawaii, June 26-July 1, 2022.<\/li>\n\n\n\n
                        6. Ogujiuba, K., Delipei, G., Mertyurek, U., Hou, J., Wieselquist, W., & Ivanov, K. (2022) Estimation of Recoverable Energies in Neutron-Induced Fission and Capture with Associated Uncertainties. International Conference on Physics of Reactors 2022 (PHYSOR 2022). Pittsburgh, PA. May 15-20, 2022.<\/li>\n\n\n\n
                        7. Altahhan, M., Delipei, G., Holler, D., Hou, J., Avramova, M., & Ivanov, K. (2022) julia for Enhancing Nuclear Engineering Simulations (JENES): Introduction to the JENES Project and Platform. International Conference on Physics of Reactors 2022 (PHYSOR 2022). Pittsburgh, PA. May 15-20, 2022.<\/li>\n\n\n\n
                        8. Ni, K., Cao, Y., Stauff, N.E., & Hou, J. (2022) Assessment of Griffin Cross-Section Interpolation Capability on TRISO-Fueled Heat-Pipe Micro-Reactor. International Conference on Physics of Reactors 2022 (PHYSOR 2022). Pittsburgh, PA. May 15-20, 2022.<\/li>\n\n\n\n
                        9. Ni, K. & Hou, J. (2022) An Efficient High-To-Low Informing Scheme for Core Neutronics Calculations Based on NEAMS Tools. International Conference on Physics of Reactors 2022 (PHYSOR 2022). Pittsburgh, PA. May 15-20, 2022.<\/li>\n\n\n\n
                        10. Trivedi, I., Zeng, K., Hou, J., & Stauff, N.E. (2022) Impact of Nuclear Data Covariance Libraries on Uncertainty Quantification of Sodium Cooled Fast Reactor Simulation. International Conference on Physics of Reactors 2022 (PHYSOR 2022). Pittsburgh, PA. May 15-20, 2022.<\/li>\n\n\n\n
                        11. Williams, J., Howe, T., & Hou, J. (2022) Neutronics Modeling of the Pulsed Plasma Rocket Reactor Using Rattlesnake. International Conference on Physics of Reactors 2022 (PHYSOR 2022). Pittsburgh, PA. May 15-20, 2022.<\/li>\n\n\n\n
                        12. L. Bullerwell, A. Abarca, M. Avramova, J. Hou, \u201cDevelopment of a Steady-State solver and Nonlinear Iteration in the Residual Formulation of CTF,\u201d 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), March 6-11, 2022.<\/li>\n\n\n\n
                        13. S. Bhaskar, D. Holler, M. Avramova, J. Hou, \u201cLiquid Fuel Molten Salt Reactor Uncertainty Analysis Using Gen-Foam and Dakota,\u201d 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), March 6-11, 2022.<\/li>\n<\/ol>\n\n\n\n

                          2021<\/h3>\n\n\n\n
                            \n
                          1. A. Rivas, G.K. Delipei, I. Davis, Y. Britts, J. Hou, \u201cTransient Characterization in High-temperature Gas-cooled Reactors Using Deep Neural Networks,\u201d Transactions of the American Nuclear Society, Vol. 125, 778-781, 2021 ANS Winter Meeting, November 30-December 3, 2021.<\/li>\n\n\n\n
                          2. J. Chen, J. Hou, K. Ivanov, \u201cA Hybrid Monte Carlo Method for k-eigenvalue Problem,\u201d Proceedings of M&C 2021 Conference, 220-229, Raleigh, NC, October 3-7, 2021.<\/li>\n\n\n\n
                          3. G. K. Delipei, K. Zeng, J. Hou, \u201cImpact of Covariances Estimation on Uncertainty Propagation in Reactor Core Simulations,\u201d Proceedings of M&C 2021 Conference, 1656-1665, Raleigh, NC, October 3-7, 2021.<\/li>\n\n\n\n
                          4. K. Ni, J. Hou, M. Avramova, \u201cDevelopment of a High-to-Low Informing Scheme for Core Neutronics Calculations Based on NEAMS Tools,\u201d Proceedings of M&C 2021 Conference, 1394-1403, Raleigh, NC, October 3-7, 2021.<\/li>\n\n\n\n
                          5. Y. Xu, J. Hou, K. Ivanov, \u201cA Transport Corrected SP3 Solver Development with Nodal Expansion Method,\u201d Proceedings of M&C 2021 Conference, 1729-1739, Raleigh, NC, October 3-7, 2021.<\/li>\n\n\n\n
                          6. B. Andersen, A. Godfrey, J. Hou, D. Kropaczek, \u201cApplication of Deep Learning Networks to Surrogate Modeling of Crud Deposition,\u201d Proceedings of M&C 2021 Conference, 1782-1791, Raleigh, NC, October 3-7, 2021.<\/li>\n\n\n\n
                          7. L. Bullerwell, P. C. Shriwise, P. K. Romano, J. Hou, \u201cDevelopment of an OpenFOAM interface for ENRICO,\u201d Proceedings of M&C 2021 Conference, 641-650, Raleigh, NC, October 3-7, 2021.<\/li>\n\n\n\n
                          8. B. Andersen, J. Hou, D. Kropaczek, \u201cMinimizing CRUD Deposition through Optimization of Associated Parameters,\u201d EPJ Web Conf. 247 12009 (2021). https:\/\/doi.org\/10.1051\/epjconf\/202124712009<\/a>.<\/li>\n\n\n\n
                          9. Y. Xu, J. Hou, K. Ivanov, \u201cImprovement to NEM SP3 Modelling and Simulation,\u201d EPJ Web Conf. 247 03008 (2021). DOI: 10.1051\/epjconf\/202124703008. https:\/\/doi.org\/10.1051\/epjconf\/202124703008<\/a>.<\/li>\n\n\n\n
                          10. K. Ni, J. Hou, M. Avramova, \u201cImplementation and Comparison of Assembly Discontinuity Factors for PROTEUS-MOCEX,\u201d EPJ Web Conf. 247 02035 (2021). https:\/\/doi.org\/10.1051\/epjconf\/202124702035<\/a>.<\/li>\n<\/ol>\n\n\n\n

                            2020<\/h3>\n\n\n\n
                              \n
                            1. A. Rivas, J. Hou, G Ilas, \u201cPreliminary Benchmark Calculations of Spent Nuclear Fuel Isotopic Concentration Using BWR Assay Data,\u201d Transactions of the American Nuclear Society, Vol. 123, 1365-1368, 2020 ANS Virtual Winter Meeting, November 16-19 (2020). https:\/\/dx.doi.org\/10.13182\/T123-33033<\/a>.<\/li>\n\n\n\n
                            2. V. Naicker, S. Sihlangu, J. Hou, F. Reitsma, \u201cNeutronic Uncertainty Propagation for the HTTR in terms of the IAEA CRP on HTGR uncertainty Analysis in Modelling,\u201d International Conference on High Temperature Reactor Technology (HTR 2020), Yogyakarta, Oct 6-8, 2020.<\/li>\n\n\n\n
                            3. J. Chen, J. Hou, \u201cA Hybrid Neutronics Method with Diffusion Synthetic Acceleration for k-eigenvalue Problem,\u201d 2020 ANS Annual Meeting Transactions, Virtual Meeting, June 8-11, 2020.<\/li>\n<\/ol>\n\n\n\n

                              2019<\/h3>\n\n\n\n
                                \n
                              1. K. Zeng, N. Stauff, J. Hou, \u201cSensitivity and Uncertainty Analysis of the Advanced Burner Reactor Core Using NEAMS Workbench,\u201d 2019 ANS Winter Meeting Transactions, Washington DC, November 17-21, 2019.<\/li>\n\n\n\n
                              2. M. Avramova, J. Hou, K. Ivanov, \u201cContributions of Mark Williams to OECD\/NEA LWR-UAM Multi-Scale Reactor Physics Framework,\u201d 2019 ANS Winter Meeting Transactions, Washington DC, November 17-21, 2019.<\/li>\n\n\n\n
                              3. K. Zeng, J. Hou, K. Ivanov, \u201cUncertainty Analysis of Pressurized Water Reactor Core Cycle Depletion Calculation,\u201d 2019 ANS Winter Meeting Transactions, Washington DC, November 17-21, 2019.<\/li>\n\n\n\n
                              4. B. Andersen, D. Kropaczek, J. Hou, \u201cBWR Fuel Bundle Optimization Based on Three-Dimensional Fuel Rods,\u201d 2019 ANS Winter Meeting Transactions, Washington DC, November 17-21, 2019.<\/li>\n\n\n\n
                              5. K. Zeng, J. Hou, K. Ivanov, \u201cImpact of Spatial Coupling Schemes and Perturbation Options on Uncertainty Quantification of PWR Core Simulation,\u201d Proceedings of M&C 2019 Conference (pp. 2755-2764), Portland, OR, August 25-29, 2019.<\/li>\n\n\n\n
                              6. J. Hou, C. Maras, C. Gozum, M. Avramova, K. Ivanov, \u201cComparative Analysis of Solutions of Neutronics Exercises of the LWR UAM Benchmark,\u201d Proceedings of M&C 2019 Conference (pp. 2726-2735), Portland, OR, August 25-29, 2019.<\/li>\n\n\n\n
                              7. I. Trivedi, J. Hou, G. Grasso, K. Ivanov, \u201cUncertainty Quantification on Feedback and Safety Parameters of Lead-Cooled Fast Reactors,\u201d Proceedings of M&C 2019 Conference (pp. 1483-1492), Portland, OR, August 25-29, 2019.<\/li>\n\n\n\n
                              8. S. Bhaskar, M. Altahhan, P. Balestra, J. Hou, M. Avramova, N. Smith, C. Fiolina, \u201cGeN-Foam 3D Coupled Calculation of Liquid Fuel Molten Salt Reactor Primary Loop,\u201d Proceedings of NURETH 18, Portland, Oregon, Aug 18-23, 2019.<\/li>\n\n\n\n
                              9. J. Hou, K. Ni, A. Hawari, \u201cAn Artificial Neural Network Based Anomaly Detection Algorithm for Nuclear Power Plants,\u201d ANS Annual Meeting, Minneapolis, MN, June 9-13, 2019.<\/li>\n\n\n\n
                              10. L. Bullerwell, N. Smith, J. Hou, \u201cDesign of a Small Modular Molten Salt Reactor,\u201d ANS Annual Meeting, Minneapolis, MN, June 9-13, 2019.<\/li>\n<\/ol>\n\n\n\n

                                2016 – 2018<\/h3>\n\n\n\n
                                  \n
                                1. M. Altahhan, S. Bhaskar, P. Balestra, J. Hou, M. Avramova, N. Smith, \u201cAdvanced Liquid Fuel Molten Salt Reactor Core Simulation Using Gen-Foam,\u201d Advances in Thermal Hydraulics (ATH 2018), Orlando, FL, November 11-15, 2018.<\/li>\n\n\n\n
                                2. M. Altahhan, P. Balestra, J. Hou, M. Avramova, \u201cImplementation of the Multigroup Telegraph Based P1 Approximation and Comparison to the Multigroup Diffusion Based P1 Approximation in Gen-Foam,\u201d Proceedings of PHYTRA4, Marrakech, Morocco, September 17-19, 2018.<\/li>\n\n\n\n
                                3. S. Bhaskar, M. Altahhan, Devshibhai Ziyad, P. Balestra, J. Hou, M. Avramova, \u201cModelling and Simulation of a Liquid Fuel Molten Salt Reactor Core Using Gen-Foam,\u201d Proceedings of PHYTRA4, Marrakech, Morocco, September 17-19, 2018.<\/li>\n\n\n\n
                                4. Y. Xu, J. Hou, K. Ivanov, \u201cNew Implementation of Second-Order Discontinuity Factor for Simplified P3 Theory in NEM,\u201d Proceedings of PHYTRA4, Marrakech, Morocco, September 17-19, 2018.<\/li>\n\n\n\n
                                5. G. Zhang, K. Zeng, N. Stauff, J. Hou, T.K. Kim, T.H. Fanning, \u201cUncertainty Quantification of ABR Transient Safety Analysis,\u201d ANS Best Estimate Uncertainty International Conference (BEPU 2018), Lucca, Italy, May 13-19, 2018.<\/li>\n\n\n\n
                                6. N.E. Stauff, K. Zeng, G. Zhang, G. Aliberti, J. Hou, T. Fanning, and T. K. Kim, \u201cUncertainty Quantification of ABR Transient Safety Analysis \u2013 Nuclear Data Uncertainties,\u201d ANS Best Estimate Uncertainty International Conference (BEPU 2018), Lucca, Italy, May 13-19, 2018.<\/li>\n\n\n\n
                                7. I. Trivedi, J. Hou, J. Li, G. Grasso, F. Franceschini, K. Ivanov, \u201cImpact of Nuclear Data Uncertainties on Lead-cooled Fast Reactors,\u201d ANS Best Estimate Uncertainty International Conference (BEPU 2018), Lucca, Italy, May 13-19, 2018.<\/li>\n\n\n\n
                                8. K. Zeng, J. Hou, M. Jessee, K. Ivanov, \u201cUncertainty Quantification on Pressurized Water Reactor Coupled Core Simulation Using Stochastic Sampling Method,\u201d ANS Best Estimate Uncertainty International Conference (BEPU 2018), Lucca, Italy, May 13-19, 2018.<\/li>\n\n\n\n
                                9. S.F. Sihlangu, V.V. Naicker, J. Hou, F. Reitsma, \u201cUncertainty Quantification in the MHGTR-350 Fuel Compact and Block Using TSUNAMI-3D Clutch Method and Sampler,\u201d ANS Best Estimate Uncertainty International Conference (BEPU 2018), Lucca, Italy, May 13-19, 2018.<\/li>\n\n\n\n
                                10. A. Jambria, A. Alfonsi, C. Rabiti, J. Hou, K. Ivanov, \u201cPHISICS\/INSTANT Time-dependent Heterogeneous Transport Simulations of the C5G7-TD Benchmark,\u201d PHYSOR 2018: Reactors Physics paving the way towards more efficient systems, Cancun, Mexico, April 22-26, 2018.<\/li>\n\n\n\n
                                11. Y. Xu, J. Hou, K. Ivanov, \u201cImplementation of Second-Order Discontinuity Factor for Simplified P3 Theory in NEM,\u201d PHYSOR 2018: Reactors Physics paving the way towards more efficient systems, Cancun, Mexico, April 22-26, 2018.<\/li>\n\n\n\n
                                12. J. Hou, K. Ivanov, V. Boyarinov, P. Fomichenko, \u201cC5G7-TD Benchmark for Time-Dependent Heterogeneous Neutron Transport Calculations,\u201d Int\u2019l Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, Apr 16-20, 2017.<\/li>\n\n\n\n
                                13. K. Zeng, J. Hou, K. Ivanov, M. Jessee, \u201cUncertainty Analysis of Light Water Reactor Core Simulations Using Statistic Sampling Method,\u201d Int\u2019l Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering, Jeju, Korea, Apr 16-20, 2017.<\/li>\n\n\n\n
                                14. L. Wang, J. Guo, F. Li, J. Hou, K. Ivanov, \u201cEffect of Double Heterogeneity Treatment on Neutronics Modeling of HTGR Unit Cell,\u201d 2016 International Topical Meeting on High Temperature Reactor Technology (HTR2016), Las Vegas, NV, Nov 2016.<\/li>\n\n\n\n
                                15. Q. Li, M. Avramova, J. Yu, Y. Jiao, J. Hou, \u201cA New Model for Active Nucleation Site Density In Boiling Systems,\u201d International Topical Meeting on Advances in Thermal Hydraulics 2016 (ATH 16), New Orleans, LA, June 2016.<\/li>\n\n\n\n
                                16. J. Hou, S. Qvist, R. Kellogg, E. Greenspan, \u201cIn-core Fuel Management Optimization for Breed-and-Burn Reactors with 3D Fuel Shuffling,\u201d PHYSOR 2016 – Unifying Theory and Experiments in the 21st Century, Sun Valley, Idaho, May 2016.<\/li>\n<\/ol>\n\n\n\n

                                  Technical Reports<\/h2>\n\n\n\n

                                  2024<\/h3>\n\n\n\n
                                    \n
                                  1. Kim, J. , Lawrence, S. , Abdo, M. , Luque-Gutierrez, J. , Rollins, N. , Hou, J. , Ivanov, B. , Donell, A. , Spooner, S. \u201cGains in operational flexibility, safety margins, and cost efficiencies via integrated Plant Reload Optimization platform\u201d . INL\/MIS-24-77706-Rev000, U.S. D.O.E., August 2024.<\/li>\n<\/ol>\n\n\n\n

                                    2023<\/h3>\n\n\n\n
                                      \n
                                    1. Nguyen, K, & DeHart, Mark D. “Modeling of the Advanced Test Reactor Using OpenMC, Cubit and Griffin”. INL\/RPT-23-74489, Idaho National Laboratory, August 2023.<\/li>\n<\/ol>\n\n\n\n

                                      2022<\/h3>\n\n\n\n
                                        \n
                                      1. Y-J Choi, M. Abdo, C. Wang, J. Valeri, C. Frepoli, K. Nguyen, J. Hou. “Development of Plant Reload Optimization Platform Capabilities for Core Design and Fuel Performance Analysis”. INL\/RPT-22-70382, Idaho National Laboratory, December 2022.<\/li>\n\n\n\n
                                      2. Y-J Choi, M. Abdo, G. Palamone, S. Heagy, C. Frepoli, K. Ogujiuba, N. Rollins, G. Delipei*, J. Hou, \u201cDevelopment and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis,\u201d INL\/RPT-22-68628, Idaho National Laboratory, August 2022.<\/li>\n\n\n\n
                                      3. Y-J Choi, K. Ogujiuba, N. Rollins, K. Nguyen, J. Hou, U Baker, B. Lindley, \u201cSafety Analysis for Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup,\u201d INL\/RPT-22-68581, Idaho National Laboratory, August 2022.<\/li>\n<\/ol>\n\n\n\n

                                        2016 – 2021<\/h3>\n\n\n\n
                                          \n
                                        1. J. Christensen, V. Agarwal, M. Avramova, M. Diaconeasa, J. Hou, S. Palmtag, Y. Azmy, \u201cFission Battery Initiative \u2013 Safety and Licensing Workshop Report,\u201d INL\/EXT-21 Rev 0, Idaho National Laboratory, September 2021.<\/li>\n\n\n\n
                                        2. N. Stauff, P. Lartaud, Y.S. Jung, P. Seurin, C.H. Lee, K. Zeng, J. Hou, \u201cStatus of the NEAMS and ARC Neutronics Fast Reactor Tools Integration to the NEAMS Workbench,\u201d ANL\/NEAMS-19\/1, Argonne National Laboratory, September 30, 2019.<\/li>\n\n\n\n
                                        3. K. Zeng, J. Hou, \u201cModeling SFR-UAM Benchmark Using NEAMS Workbench,\u201d RDFMG_UAM-SFR, August 2019.<\/li>\n\n\n\n
                                        4. M. Altahhan, S. Bhaskar, P. Balestra, J. Hou, M. Avramova, \u201cNCSU Progress Report for the MSR Design Project,\u201d RDFMG, April 2019.<\/li>\n\n\n\n
                                        5. M. Altahhan, S. Bhaskar, P. Balestra, J. Hou, M. Avramova, \u201cNCSU Progress Report for the MSR Design Project,\u201d RDFMG, December 2018.<\/li>\n\n\n\n
                                        6. M. Altahhan, S. Bhaskar, D. Ziyad, J. Hou, P. Balestra, \u201cNCSU Technical Report for the MSR Design Project,\u201d RDFMG_MSRDES\/001, April 2018.<\/li>\n\n\n\n
                                        7. V. Boyarinov, P. Formichenko, J. Hou, M. Avramov, K. Ivanov, A. Aures, W. Zwermann, K. Velkov, \u201cDeterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD), Volume II: Dynamics Phase,\u201d’ NEA\/NSC 2018.<\/li>\n\n\n\n
                                        8. V. Boyarinov, P. Formichenko, J. Hou, K. Ivanov, A. Aures, W. Zwermann, K. Velkov, \u201cDeterministic Time-Dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD), Volume I: Kinetics Phase,\u201d’ NEA\/NSC 2016.<\/li>\n<\/ol>\n","protected":false},"excerpt":{"rendered":"

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