Education

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

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

Chen, J., Hou, J., & Ivanov, K. (2023), NUCLEAR ENGINEERING AND TECHNOLOGY, 55(4), 1428–1438. https://doi.org/10.1016/j.net.2022.12.022

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

Ni, K., & Hou, J. (2023, February 15), NUCLEAR SCIENCE AND ENGINEERING, Vol. 2. https://doi.org/10.1080/00295639.2022.2158706

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), Eng. https://doi.org/10.3390/eng3040036

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

Delipei, G. K., Rouxelin, P., Abarca, A., Hou, J., Avramova, M., & Ivanov, K. (2022), ENERGIES, 15(14). https://doi.org/10.3390/en15145226

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), NUCLEAR ENGINEERING AND DESIGN, 392. https://doi.org/10.1016/j.nucengdes.2022.111744

Predictions of component Remaining Useful Lifetime Using Bayesian Neural Network

Rivas, A., Delipei, G. K., & Hou, J. (2022), PROGRESS IN NUCLEAR ENERGY, 146. https://doi.org/10.1016/j.pnucene.2022.104143

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). 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. 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. https://doi.org/10.1016/j.nucengdes.2021.111474

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Grants

Machine Learning Based Lattice and Core Optimization Methodology for Multi-Cycle Operations – CNP Core Project 6

Consortium for Nuclear Power (CNP)(7/01/22 - 6/30/23)

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Machine Learning Based Lattice and Core Optimization Methodology for Multi-Cycle Operations – CNP Core Project 6

Sponsor: Consortium for Nuclear Power (CNP)

Start Date: 7/01/22

End Date: 6/30/23

Abstract

One of the key challenges of the nuclear industry for operating the current nuclear power plants (NPPs) is to reduce the cost, often evaluated by the levelized cost of energy (LCOE), while maintaining safety and efficiency of nuclear reactors. The proposed project aims to develop and apply ML/AI RL techniques for the combined in-core and out-of-core optimization of PWR using the NCSU Modular Optimization Framework (MOF) . The Python 3 based MOF currently has two solvers, GA and SA, and can solver for assembly optimization, single cycle, and multi-cycle core optimization using the code interface with CASMO4 (lattice calculations) and SIMULATE3 (core simulation). CASMO4/SIMULATE3 is a computationally very efficient code suite that will allow the exploration of various optimization goals and constraints. The RL solver will be developed within MOF by leveraging existing capabilities to reduce the lead time.

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Machine Learning Model Development in 2022 (ARPA-E WP 2.3.3)

US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)(1/03/22 - 12/31/22)

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Machine Learning Model Development in 2022 (ARPA-E WP 2.3.3)

Sponsor: US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)

Start Date: 1/03/22

End Date: 12/31/22

Abstract

This project is aims for the development and application of machine learning (ML) models to the nuclear power plant diagnosis and prognosis, and predictive maintenance, to support the reduction of operation and maintenance (O&M) cost of advanced reactor concepts. The first phase is focused on the development of a ML model for pump degradation prediction and failure mode diagnosis, more specifically aiming to make remaining useful life (RUL) predictions and corresponding failure mode of pumps. A synthetic database for the pump operation (and degradation) over time will be generated using the physics model mentioned above. Next, a ML model will be trained, tested, and validated for the pump degradation prediction and failure mode diagnosis using the sensor readings synthesized based on the pump degradation database. In the second phase, we will integrate the physics-based pump degradation model developed in Phase 1 with the Xe-100 simulator and develop a ML degradation model that is capable of making predictions using system-wise sensor data.

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Performance Evaluation of Accident Tolerant Fuel in Optimized LWR Designs

US Dept. of Energy (DOE)(2/17/22 - 9/30/23)

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Performance Evaluation of Accident Tolerant Fuel in Optimized LWR Designs

Sponsor: US Dept. of Energy (DOE)

Start Date: 2/17/22

End Date: 9/30/23

Abstract

This proposed work aims to develop an optimized core design for a generalized PWR with a two-year cycle length using ATF and to evaluate the core performance using high-fidelity multiphysics simulation code VERA-CS. Increased fuel enrichment and extended fuel burnup will be implemented to achieve the desired cycle length. Literature review of the ATF will be conducted first with the focus placed on the Iron-Chromium-Aluminum (FeCrAl) cladding. Metaheuristic optimization methods including genetic algorithm (GA) and simulated annealing (SA) available in the Modular Optimization Framework (MOF) will be leveraged to perform the optimization. Results from VERA-CS will be converted to be used in the MACCS (MELCORE Accident Consequence Code System) for the analysis of offsite consequences of a hypothetical release of radioactive material to the environment.

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Machine Learning Methods for Xe-100 Plant Monitoring and Operations

US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)(9/01/21 - 12/31/22)

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Machine Learning Methods for Xe-100 Plant Monitoring and Operations

Sponsor: US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)

Start Date: 9/01/21

End Date: 12/31/22

Abstract

In the proposed project, we seek to develop advanced plant monitoring and operating technologies for the Xe-100 by developing, implementing, and validating the machine learning (ML) based algorithms. It will be carried out in two sub-projects, each concentrating on one focus area. First, we will develop an advanced methodology to continuously measure and analyze fuel pebbles discharge from the Xe-100 HTGR core to achieve the objective of burnup and enrichment measurement based on the gamma and neutron spectrometry. It is proposed to adopt a two-step approach with the first step focusing on distinguishing the influence of burnup and enrichment level of the pebble fuel, and the second step aiming at the fuel burnup estimation. ML models will be developed, first using synthetic data and later using experimental results, to achieve accurate and real-time analysis. The method will eventually be demonstrated on the detection system being engineered at X-energy.

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Development of LWR Fuel Reload Optimization Framework

Battelle Energy Alliance, LLC(10/28/21 - 9/30/23)

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Development of LWR Fuel Reload Optimization Framework

Sponsor: Battelle Energy Alliance, LLC

Start Date: 10/28/21

End Date: 9/30/23

Abstract

This proposed work intends to support the ongoing development within the framework with a target effort to identify and select the optimal reactor core M&S tools to be integrated and to further develop various key capabilities of the framework. More specifically, the objectives of the study are twofold: 1) Test and assess features and modeling capabilities of various multi-physics reactor core simulators through well controlled benchmark calculations. 2) Develop and enhance the automation of core design optimization in RAVEN within the Plant Fuel Reload Optimization Framework.

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Xe-100 Burn Up Measurement System, CNP Core Project #5

Consortium for Nuclear Power (CNP)(7/01/21 - 6/30/23)

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Xe-100 Burn Up Measurement System, CNP Core Project #5

Sponsor: Consortium for Nuclear Power (CNP)

Start Date: 7/01/21

End Date: 6/30/23

Abstract

X Energy, LLC (X-energy) is transforming the nuclear energy marketplace through the development of the Xe-100, a 200 MWth modular pebble-bed HTGR to produce electricity and/or process steam. The Xe-100 Reactor uses pebble Type fuel elements (6 cm in diameter) which contains around 19,000 Triso-coated particles each. The Xe-100 Reactor utilizes an online refueling fuel handling system to achieve an availability factor of 95%. On average the pebble fuel will pass the Xe-100 reactor an average of 6 times to achieve the design burn-up of 165,000 MWd/tHM. During the start-up procedure of the Xe-100 reactor different enrichment pebbles will be introduced to the Xe-100 reactor until the equilibrium core is achieved with an enrichment of 15.5%. It is important for the Xe-100 Burn-Up-Measurement-System (BUMS) which forms part of the Xe-100 fuel handling system to distinguish between both pebble fuel burn-up and enrichment level. For the CNP Project, X-Energy proposes to develop an advanced methodology to continuously measure and analyze fuel pebbles discharge from the Xe-100 HTGR core to achieve the objective of burnup and enrichment measurement based on the gamma and neutron spectrometry. It is proposed to adopt a two-step approach with the first step focusing on distinguishing the influence of burnup and enrichment level of the pebble fuel, and the second step aiming at the fuel burnup estimation. Machine learning models will be developed, first using synthetic data and later using experimental results, to achieve accurate and real-time analysis. The method will be demonstrated on the detection system being engineered at X-energy.

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Development of High-Fidelity Transient Model for Pulsed Plasma Reactor

National Aeronautics & Space Administration (NASA)(10/01/20 - 2/28/21)

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Development of High-Fidelity Transient Model for Pulsed Plasma Reactor

Sponsor: National Aeronautics & Space Administration (NASA)

Start Date: 10/01/20

End Date: 2/28/21

Abstract

In the proposed work, the NCSU team, led by Dr. Jason Hou, will provide technical support to the ongoing project: “Pulse Plasma Rocket: Shielded, Fast Transits for Humans to Mars”, which is funded by the NASA Innovative Advanced Concepts (NIAC) Program. The lead Principal Investigator (PI) of the project is Steven Howe from Howe Industries LLC. The overall objective is to develop a propulsion system that may produce 20,000 lbsf of thrust with an Isp of 5,000 s. This work aims to support the ongoing modeling and simulation (M&S) effort of the nuclear reactor portion of the rocket concept using high-fidelity neutronics tools in the MOOSE framework. More specifically, the project intends to develop and refine a time-dependent simulation model for the reactor using the radiation transport code Mammoth/Rattlesnake, which takes the kinetics parameters and cross sections generated by the Monte Carlo code Serpent. Transient simulation of the core performance will be conducted using the reactor physics model and core design parameters will be perturbed to determine the optimal design.

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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)

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Development of Simulation Capabilities and Validation Basis to Support Evaluation of Advanced Nuclear Fuel Concepts

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/20

End Date: 9/30/22

Abstract

The proposed project aims to support the ongoing development of advanced nuclear fuel design concepts, including the Accident Tolerant Fuel (ATF), HBU (High Burnup fuels), and High-Assay Low Enriched Uranium (HALEU), by extending selected computation tools, data, validation basis, and uncertainty analysis in the SCALE code system. These new fuel concepts have been proposed by the Department of Energy (DOE) and nuclear industry aiming to improve the safety and economics of nuclear power. The work intends to: 1) improve the energy deposition model and data (nominal value and its uncertainties) to be used in the lattice physics calculation; 2) extend the stochastic sampling capabilities to perform the uncertainty analysis of heat generation distribution in space and its variations in time; 3) develop a sampling-based similarity (or representation) evaluation method to allow for the validation and uncertainty quantification using existing validation database. The deliverables include documented methodologies, augmented data file, updated computational modules in the SCALE package, as well as verification and validation results.

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Advanced Operation & Maintenance Techniques Implemented in the Xe-100 Plant Digital Twin to Reduce Fixed O&M Cost

US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)(1/29/21 - 12/31/22)

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Advanced Operation & Maintenance Techniques Implemented in the Xe-100 Plant Digital Twin to Reduce Fixed O&M Cost

Sponsor: US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)

Start Date: 1/29/21

End Date: 12/31/22

Abstract

"X-energy is proposing a project to significantly reduce the fixed operator and maintenance (O&M) cost of an advanced reactor to a target of $2/MWh. The project will follow two parallel paths to achieve its cost saving goals. The first path will access the plant using techniques such as human factors engineering, risk and hazard analysis, and maintenance evaluations to identify areas for optimization and then to develop new and innovative ways to leverage techniques such as automation, robotics, remote and centralized maintenance, and monitoring to optimized and reduce staff. A second path involves the development of virtual models that can be used to evaluate and validate the solutions proposed above. Two virtual models are an Immersive Environment Toolset and a Digital Twin. The Immersive Environment Toolset is a multidiscipline 3D model which, when combined with virtual reality, will be used to test maintenance concepts and techniques and optimize maintenance and security staff. The Digital Twin synthesizes information from the as operating plant, past operating history and planned future evolutions as well as assimilating data from other plants across the fleet to provide a wholistic understanding of the plant, health and remaining lifetime of critical plant components and identify predictive maintenance needs of physical assets with the overall goals of reducing staff requirements by optimizing O&M. The Xe-100 reactor features unsurpassed inherent safety characteristics which make it ideal to showcase the abilities of the Digital Twin. X-energy’s project will demonstrate an estimated 86% reduction in the Xe-100 plant fixed O&M Costs.

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Modeling SFR-UAM Benchmark Services On the NEAMS Workbench Project

US Dept. of Energy (DOE)(1/29/19 - 9/30/19)

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Modeling SFR-UAM Benchmark Services On the NEAMS Workbench Project

Sponsor: US Dept. of Energy (DOE)

Start Date: 1/29/19

End Date: 9/30/19

Abstract

The objective of this study is to perform analysis for the OECD/NEA Benchmark of Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM). The benchmark was established formed under the NSC/WPRS/EGUAM to check the use of best-estimate codes and data aiming to design reactors with improved safety performance while preserving a sustainable source of energy at a rather low cost. The NEAMS (Nuclear Energy Advanced Modeling and Simulation) Workbench is a new initiative that will facilitate the transition from conventional tools to high-fidelity tools by providing a common user interface for model creation, review, execution, output review, and visualization for integrated codes. In this study, various tools availabe in the NEAMS Workbench will be utlized to perform the simulation and analysis, including MCC2, DIF3D, and PERSENT etc. Both SFRs core specified in the benchmark will be analyzed, the large 3600 MWth oxide core and the medium 1000 MWth metallic core, for all the sub-cases.

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