Jason Hou

An Integrated Approach for Cycle Optimization to Support Light Water Reactor Power Uprates

Rollins, N., Delipei, G., & Hou, J. (2026, January 1). SSRN Electronic Journal.

Optimizing pressurized-water reactor equilibrium cycle using a novel loading pattern encoding and rule-based genetic crossover operators

Nguyen, K. H. N., Kim, J., Rollins, N., Luque-Gutierrez, J. C., Hou, J., Lawrence, S., … Abdo, M. (2026, January 5). Nuclear Engineering and Technology.

Development and application of two-step uncertainty propagation and sensitivity analysis methodology for fast reactor safety analysis

Trivedi, I., Delipei, G., Hou, J., Grasso, G., & Ivanov, K. (2025, February 11). Nuclear Engineering and Design, Vol. 433.

A System Predictive Maintenance Framework for Advanced Reactors Using a Data-Driven Digital Twin

Rivas, A., Delipei, G. K., & Hou, J. (2024, August 2). Nuclear Science and Engineering, Vol. 8.

A component diagnostic and prognostic framework for pump bearings based on deep learning with data augmentation

Rivas, A., Delipei, G. K., Davis, I., Bhongale, S., Yang, J., & Hou, J. (2024, April 3). Reliability Engineering & System Safety, Vol. 247.

A system diagnostic and prognostic framework based on deep learning for advanced reactors

Rivas, A., Delipei, G. K., Davis, I., Bhongale, S., & Hou, J. (2024, February 13). Progress in Nuclear Energy, Vol. 170.

Development and evaluation of parallel simulated annealing algorithm for reactor core optimization problems

Mikouchi-Lopez, J., Delipei, G., & Hou, J. (2024, June 12). Nuclear Science and Technology Open Research.

Modeling a generic Pebble Bed High-Temperature Gas-Cooled Reactor to perform load-following using Simulink

Rivas, A., Delipei, G. K., & Hou, J. (2024, August 5). Nuclear Engineering and Design, Vol. 428.

Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin

Rivas, A., Delipei, G. K., & Hou, J. (2024, October 4). Journal of Nuclear Engineering and Radiation Science, Vol. 4.

Prototyping of a Machine Learning–Based Burnup Measurement Capability for Pebble Bed Reactor Fuel

Rollins, N., Allan, I., & Hou, J. (2024, April 2). Nuclear Science and Engineering, Vol. 4.

Reinforcement Learning-Based Control Sequence Optimization for Advanced Reactors

Nguyen, K. H. N., Rivas, A., Delipei, G. K., & Hou, J. (2024, July 1). Journal of Nuclear Engineering, Vol. 5, pp. 209–225.

Source term analysis of FeCrAl accident tolerant fuel using MELCOR

Baker, U., Choi, Y.-J., Rollins, N., Nguyen, K., Jung, W. H., Whitmeyer, A., … Lindley, B. (2024, March 16). Annals of Nuclear Energy, Vol. 202.

An Efficient High-to-Low Iterative Method for Light Water Reactor Analysis Based on NEAMS Tools

Nuclear Science and Engineering, 197(8), 1700–1716.

A Novel Method for Controlling Crud Deposition in Nuclear Reactors Using Optimization Algorithms and Deep Neural Network Based Surrogate Models

Andersen, B., Hou, J., Godfrey, A., & Kropaczek, D. (2022, November 23). Eng—Advances in Engineering.

A hybrid neutronics method with novel fission diffusion synthetic acceleration for criticality calculations

Nuclear Engineering and Technology, 55(4), 1428–1438.

CTF-PARCS Core Multi-Physics Computational Framework for Efficient LWR Steady-State, Depletion and Transient Uncertainty Quantification

Energies, 15(14), 5226.

Nuclear data uncertainty propagation applied to the versatile test reactor conceptual design

Rivas, A., Martin, N. P., Bays, S. E., Palmiotti, G., Xu, Z., & Hou, J. (2022, April 14). Nuclear Engineering and Design, Vol. 392, p. 111744.

Predictions of component Remaining Useful Lifetime Using Bayesian Neural Network

Rivas, A., Delipei, G. K., & Hou, J. (2022, February 21). Progress in Nuclear Energy, Vol. 146, p. 104143.

Innovations in Multi-Physics Methods Development, Validation, and Uncertainty Quantification

Journal of Nuclear Engineering, 2(1), 44–56.

Methodology for Discontinuity Factors Generation for Simplified P3 Solver Based on Nodal Expansion Formulation

Energies, 14(20), 6478.

Propagating neutronic uncertainties for FFTF LOFWOS Test #13

Rivas, A., Stauff, N., Sumner, T., & Hou, J. (2021, February 26). Nuclear Engineering and Design, Vol. 375, p. 111047.

Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I

Nuclear Engineering and Design, 384, 111474.

Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis

Science and Technology of Nuclear Installations, 2020, 1–18.

Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors

Science and Technology of Nuclear Installations, 2020, 1–14.

Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam

Nuclear Engineering and Design, 369, 110826.

Development of multi-objective core optimization framework and application to sodium-cooled fast test reactors

Zeng, K., Stauff, N. E., Hou, J., & Kim, T. K. (2019, November 13). Progress in Nuclear Energy.

Further development of methodology to model TRISO fuel and BISO absorber particles and related uncertainty quantification using SCALE 6

Sihlangu, S. F., Naicker, V. V., Hou, J., & Reitsma, F. (2019, May 23). Journal of Nuclear Science and Technology, Vol. 56, pp. 690–709.

Nuclear-data uncertainty propagation in transient simulation for the C5G7-TD benchmark problem

Wan, C., Sui, Z., Wang, B., Cao, L., Liu, Z., & Hou, J. (2019, October 23). Annals of Nuclear Energy, Vol. 140, p. 107122.

Uncertainty Quantification and Propagation of Multiphysics Simulation of the Pressurized Water Reactor Core

Nuclear Technology, 205(12), 1618–1637.

Development, verification and application of a new model for active nucleation site density in boiling systems

Nuclear Engineering and Design, Vol. 328, pp. 1–9.

Effect of Nuclear Data on Fuel Element Neutronic Characteristics of Pebble-bed High Temperature Gas-cooled Reactor

Atomic Energy Science and Technology, 51(9), 1591–1598.

OECD/NEA benchmark for time-dependent neutron transport calculations without spatial homogenization

Hou, J., Ivanov, K. N., Boyarinov, V. F., & Fomichenko, P. A. (2017, April 5). Nuclear Engineering and Design, Vol. 317, pp. 177–189.

3D in-core fuel management optimization for breed-and-burn reactors

Hou, J., Qvist, S., Kellogg, R., & Greenspan, E. (2015, December 29). Progress in Nuclear Energy, Vol. 88, pp. 58–74.

Design and performance of 2D and 3D-shuffled breed-and-burn cores

Qvist, S., Hou, J., & Greenspan, E. (2015, May 19). Annals of Nuclear Energy, Vol. 85, pp. 93–114.

Assessment of MICROX-2 Code with New ENDF/B-VII Release 0 Master Libraries

Hou, J., Choi, H., & Ivanov, K. (2014, June 1). Nuclear Technology, Vol. 6, pp. 305–316 .

Development of an iterative diffusion-transport method based on MICROX-2 cross section libraries

Hou, J., Choi, H., & Ivanov, K. N. (2014, December 10). Annals of Nuclear Energy, Vol. 77, pp. 335–342.

Self-shielding models of MICROX-2 code: Review and updates

Hou, J., Choi, H., & Ivanov, K. N. (2013, November 7). Annals of Nuclear Energy, Vol. 64, pp. 256–263.

Development of a Modern Pressurized Water Reactor Simulator: Instrumentation, Design and Data Acquisition

Osborne, D. R., Hou, J., Graves, G., & Miller, L. F. (2007, October 1). IEEE Conference Record/IEEE Conference Record - Nuclear Science Symposium & Medical Imaging Conference.