Jason Hou

Assistant Professor

Director of Advanced Reactor Design and Optimization Research (ARDOR) Lab

Dr. Jason Hou is an advocate of nuclear energy and the mission of his research is to promote nuclear energy primarily by advancing scientific understanding of advanced nuclear reactor technologies. There are four main research thrust areas: computational reactor physics, multiphysics modeling and simulation capabilities, advanced reactor design and fuel cycle analysis, and machine learning for reactor operation and maintenance.

Dr. Hou is current teaching NE 403 Nuclear Reactor Laboratory, NE 412/512 Nuclear Fuel Cycle, and co-teaching NE 491/591 Metal Cooled Reactor.

Dr. Hou is the Director of the Advanced Reactor Design and Optimization Research (ARDOR) Lab. He also serves as the Coordinator of the Nuclear Simulation Laboratory.

Education

Ph.D. 2013

Nuclear Engineering

Pennsylvania State University

M.S. 2010

Nuclear Engineering

University of Michigan

M.S. 2007

Nuclear Engineering

University of Tennessee

B.S. 2005

Engineering Physics

Tsinghua University

Research Description

Dr. Hou's area of research interest includes multi-physics reactor simulation, advanced reactors, fuel cycle analysis, uncertainty quantification, machine learning in engineering applications, and nuclear power plant simulator. Presently he performs studies on the Hi2Lo informing scheme for multi-physics simulation, sensitivity and uncertainty (S/U) analysis in modeling of various reactor systems, high-fidelity reactor core simulator, hybrid Monte Carlo (MC) and deterministic method for core calculations, machine learning for plant prognosis and diagnosis. He is the coordinator of the NEA/OECD homogenization-free time-dependent neutron transport benchmark (C5G7-TD).

Publications

Innovations in Multi-Physics Methods Development, Validation, and Uncertainty Quantification
Avramova, M., Abarca, A., Hou, J., & Ivanov, K. (2021), Journal of Nuclear Engineering. https://doi.org/10.3390/jne2010005
Methodology for Discontinuity Factors Generation for Simplified P-3 Solver Based on Nodal Expansion Formulation
Xu, Y., Hou, J., & Ivanov, K. (2021), ENERGIES, 14(20), 6478. https://doi.org/10.3390/en14206478
Propagating neutronic uncertainties for FFTF LOFWOS Test #13
Rivas, A., Stauff, N., Sumner, T., & Hou, J. (2021), NUCLEAR ENGINEERING AND DESIGN, 375, 111047. https://doi.org/10.1016/j.nucengdes.2020.111047
Summary of comparative analysis and conclusions from OECD/NEA LWR-UAM benchmark Phase I
Delipei, G. K., Hou, J., Avramova, M., Rouxelin, P., & Ivanov, K. (2021), NUCLEAR ENGINEERING AND DESIGN, 384, 111474. https://doi.org/10.1016/j.nucengdes.2021.111474
Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis
Hou, J., Avramova, M., & Ivanov, K. (2020), Science and Technology of Nuclear Installations. https://doi.org/10.1155/2020/7526864
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. (2020), Progress in Nuclear Energy. https://doi.org/10.1016/j.pnucene.2019.103184
Nuclear Data Uncertainty Quantification and Propagation for Safety Analysis of Lead-Cooled Fast Reactors
Trivedi, I., Hou, J., Grasso, G., Ivanov, K., & Franceschini, F. (2020), Science and Technology of Nuclear Installations. https://doi.org/10.1155/2020/3961095
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. (2020), Annals of Nuclear Energy, 140, 107122. https://doi.org/10.1016/j.anucene.2019.107122
Preliminary design and analysis of Liquid Fuel Molten Salt Reactor using multi-physics code GeN-Foam
Ramzy Altahhan, M., Bhaskar, S., Ziyad, D., Balestra, P., Fiorina, C., Hou, J., … Avramova, M. (2020), Nuclear Engineering and Design, 369, 110826. https://doi.org/10.1016/j.nucengdes.2020.110826
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), Journal of Nuclear Science and Technology, 5, 1–20. https://doi.org/10.1080/00223131.2019.1617204

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Grants

Development of LWR Fuel Reload Optimization Framework
Battelle Energy Alliance, LLC(10/28/21 - 9/30/22)
Xe-100 Burn Up Measurement System, CNP Core Project #5
Consortium for Nuclear Power (CNP)(7/01/21 - 6/30/22)
Development of High-Fidelity Transient Model for Pulsed Plasma Reactor
National Aeronautics & Space Administration (NASA)(10/01/20 - 2/28/21)
Development of Simulation Capabilities and Validation Basis to Support Evaluation of Advanced Nuclear Fuel Concepts
US Dept. of Energy (DOE)(10/01/20 - 9/30/22)
Modeling SFR-UAM Benchmark Services On the NEAMS Workbench Project
US Dept. of Energy (DOE)(1/29/19 - 9/30/19)
Demonstration of utilization of high-fidelity NEAMS tools to inform the improved use of conventional tools within the NEAMS Workbench on the NEA/OECD C5G7-TD benchmark
US Dept. of Energy (DOE)(10/01/18 - 9/30/22)
Development of Information Trustworthiness and Integrity Algorithms for Cybersecurity Defenses of Nuclear Power Reactors Technical Workscope Identification: NE-1
US Dept. of Energy (DOE)(10/01/17 - 9/30/20)