Education

Research Description

A general area of Dr. Dinh's research interest is modeling and analysis of multi-phase thermal-fluid phenomena of importance to nuclear reactor design and safety. Of particular interest are physics and prediction of boiling heart transfer, critical heat flux, and other intense multi-phase interactions that govern nuclear reactor safety margins. Dr. Dinh’s current research is focused on data-driven modeling, validation, and application of digital twins, machine learning, and artificial intelligence in advanced reactor’s safety analysis and nearly autonomous control.

Publications

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Grants

Data Driven Analysis Tool for Predicting High-Speed Airbreathing Engine Performance

US Dept. of Defense (DOD)(1/10/23 - 1/09/26)

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Data Driven Analysis Tool for Predicting High-Speed Airbreathing Engine Performance

Sponsor: US Dept. of Defense (DOD)

Start Date: 1/10/23

End Date: 1/09/26

Abstract

This proposal develops new strategies for predicting the performance of high-speed airbreathing propulsion systems using data-driven techniques. The project will involve researchers at the University of Michigan, Spaceworks, and NASA as well as two departments (MAE and NE) at NCSU.

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Trustworthiness of Digital-Twin-based Automation Technology in Nuclear Power Plant Operation

US Nuclear Regulatory Commission(9/30/22 - 9/29/25)

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Trustworthiness of Digital-Twin-based Automation Technology in Nuclear Power Plant Operation

Sponsor: US Nuclear Regulatory Commission

Start Date: 9/30/22

End Date: 9/29/25

Abstract

The project seeks to establish a technical basis for, and preliminary development of, a trustworthiness assessment framework for automation enabled by digital twin (DT) technology. DTs can be used to automate the assessment of plant state and make operation and maintenance (O&M) decisions, but such automation requires that the output of DTs be trustworthy, transparent and explainable (TTE). These TTE elements are derived in the proposed project within a modern reasoning-based system.

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Center for Thermal-fluids Application in Nuclear Energy: Establishing the Knowledge Base for Thermal-hydraulic Multiscale Simulation to Accelerate the Deployment of Advanced Reactors.

US Dept. of Energy (DOE)(10/01/20 - 9/30/24)

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Center for Thermal-fluids Application in Nuclear Energy: Establishing the Knowledge Base for Thermal-hydraulic Multiscale Simulation to Accelerate the Deployment of Advanced Reactors.

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/01/20

End Date: 9/30/24

Abstract

In this DOE-funded project the NCSU team will support the larger effort in establishing the knowledgebase for thermal-hydraulic multiscale simulation to accelerate the deployment of advanced reactors. NCSU focus will be on performing high resolution simulations of advanced reactor flows as well as developing advanced methodologies for data processing using machine-learning techniques.

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Digital Engineering and Predictive Capability Maturity Model

US Dept. of Energy (DOE)(8/16/21 - 6/30/24)

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Digital Engineering and Predictive Capability Maturity Model

Sponsor: US Dept. of Energy (DOE)

Start Date: 8/16/21

End Date: 6/30/24

Abstract

A DT-DAP (Digital Twin Development and Assessment Process) methodology has been formulated at NCSU in the ARPA-E sponsored project. DT-DAP can be very effective in guiding the design, training, testing, and application of DTs to improve effectiveness, accuracy and acceptance of system design and safety analysis.

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Risk Assessment of Digital Human System Interface in Nuclear Power Plants

US Dept. of Energy (DOE)(12/15/20 - 9/30/23)

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Risk Assessment of Digital Human System Interface in Nuclear Power Plants

Sponsor: US Dept. of Energy (DOE)

Start Date: 12/15/20

End Date: 9/30/23

Abstract

Advances that support the licensing case to enable the transition from analog instrumentation and control (I&C) technologies to digital technologies in the U.S. nuclear industry are greatly needed. The Human System Interface (HSI) is one of the key advanced design features applied for modern digital I&C systems of nuclear power plants. The vulnerability of HSI is affected by many factors, human errors, cyber-attacks, software common cause failures, etc. The proposed project will identify, evaluate and reduce system vulnerabilities to support the licensing, deployment, and operation of digital HSI designs; and adapt, improve and demonstrate the Risk Assessment process for Digital I&C Systems (RADIC process) for the risk-informed analysis of plant-specific HSI.

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Release No, 00002 NUC Contract Proposal for FY 15 (2014-2015). Formerly ACE - Academic Center for Excellence

US Dept. of Energy (DOE)(10/15/14 - 9/30/23)

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Release No, 00002 NUC Contract Proposal for FY 15 (2014-2015). Formerly ACE - Academic Center for Excellence

Sponsor: US Dept. of Energy (DOE)

Start Date: 10/15/14

End Date: 9/30/23

Abstract

This contract provides support for the INL through collaboration with NUC Universities (Oregon State University, Ohio State University and in this case specifically North Carolina State University). The goal is to more closely align the NUC research activities with the mission and objectives of the INL research directorates.

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Pilot Study on Two-Phase Flow DNS Application to Heat Transfer Enhancement Pipe

Mitsubishi Heavy Industries, Ltd.(10/01/22 - 5/15/23)

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Pilot Study on Two-Phase Flow DNS Application to Heat Transfer Enhancement Pipe

Sponsor: Mitsubishi Heavy Industries, Ltd.

Start Date: 10/01/22

End Date: 5/15/23

Abstract

The project will apply state-of-the-art two-phase flow DNS techniques for advanced heat exchanger designs. New capabilities will be added as necessary, and advanced analysis techniques will be applied to support coarse-grid model development.

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Two-Phase Flow DNS Phase 2 Project

Mitsubishi Heavy Industries, Ltd.(5/01/21 - 10/31/22)

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Two-Phase Flow DNS Phase 2 Project

Sponsor: Mitsubishi Heavy Industries, Ltd.

Start Date: 5/01/21

End Date: 10/31/22

Abstract

The project will apply state-of-the-art two-phase flow DNS techniques for advanced heat exchanger designs. New capabilities will be added as necessary, and advanced analysis techniques will be applied to support coarse-grid model development.

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Development of a Nearly Autonomous Management and Control System for Advanced Reactors

US Dept. of Energy (DOE) - Advanced Research Projects Agency - Energy (ARPA-E)(10/01/18 - 9/30/21)

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Development of a Nearly Autonomous Management and Control System for Advanced Reactors

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

Start Date: 10/01/18

End Date: 9/30/21

Abstract

The proposed project seeks to establish a technical basis for, and preliminary development of, a Nearly Autonomous Management and Control (NAMAC) system in advanced reactors. The system is intended to provide recommendations to operators during all modes of plant operation except shutdown operations: plant evolutions ranging from normal operation to accident management. These recommendations are to be derived within a modern, artificial-intelligence (AI) guided system, making use of continuous extensive monitoring of plant status, knowledge of current component status, and plant parameter trends; the system will continuously predict near-term evolution of the plant state, and recommend a course of action to plant personnel.

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Severe Accidents in Nuclear Power Plants (Research and Technical Assistance Related to Severe Accidents in Nuclear Power Plants)

US Nuclear Regulatory Commission(9/08/16 - 9/07/21)

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Severe Accidents in Nuclear Power Plants (Research and Technical Assistance Related to Severe Accidents in Nuclear Power Plants)

Sponsor: US Nuclear Regulatory Commission

Start Date: 9/08/16

End Date: 9/07/21

Abstract

A team of researchers led by the University of Wisconsin-Madison (UW), and comprising Texas A&M University (TAMU), California Institute of Technology (CalTech), and North Carolina State University (NCSU) is proposing to establish a university-based center focused on severe accident research and technical assistance. Our team������������������s research objectives are to: (i) conduct research in severe accident phenomena, in particular, those phenomena where residual uncertainties remain in light of Fukushima, and reduction of such uncertainties is warranted to address high priority Near-Term Task Force (NTTF) recommendations; (ii) provide technical assistance to the NRC related to post Fukushima safety and severe accident research; and (3) develop and maintain a repository of knowledge in severe accident research. Specific areas of technical assistance in which the center has substantial expertise and experience include in-vessel core heatup and core degradation phenomena; ex-vessel phenomena, including fuel-coolant interactions and core-concrete interactions; hydrogen mixing, combustion and control strategies; reactor system behavior under beyond-design basis conditions, and advanced modeling techniques, including reactor systems modeling and Computational Fluid Dynamics (CFD) methods that can be used in severe accident evaluation.

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