Nam Truc Dinh

Building a multiscale framework: An overview of the NEAMS thermal-hydraulics integrated research project

NUCLEAR ENGINEERING AND DESIGN, 433.

High-Resolution flow boiling simulations with multiple nucleation sites in mini-channels with offset strip fins

APPLIED THERMAL ENGINEERING, 268.

NEAMS IRP challenge problem 3: Mixing in large enclosures and thermal stratification

NUCLEAR ENGINEERING AND DESIGN, 433.

Evaluating the reliability of machine-learning-based predictions used in nuclear power plant instrumentation and control systems

RELIABILITY ENGINEERING & SYSTEM SAFETY, 250.

Knowledge representation to support EMDAP implementation in advanced reactor licensing applications

NUCLEAR ENGINEERING AND DESIGN, 428.

NEAMS IRP challenge problem 1: Flexible modeling for heat transfer for low-to-high Prandtl number fluids for applications in advanced reactors

NUCLEAR ENGINEERING AND DESIGN, 428.

Data coverage assessment on neural network based digital twins for autonomous control system

ANNALS OF NUCLEAR ENERGY, 182.

Data-Driven High-to-Low for Coarse Grid System Thermal Hydraulics

Iskhakov, A. S., Leite, V. C., Merzari, E., & Dinh, N. T. (2023, April 28). NUCLEAR SCIENCE AND ENGINEERING, Vol. 4.

Data-Driven RANS Turbulence Closures for Forced Convection Flow in Reactor Downcomer Geometry

Iskhakov, A. S., Tai, C.-K., Bolotnov, I. A., Nguyen, T., Merzari, E., Shaver, D. R., & Dinh, N. T. (2023, March 16). NUCLEAR TECHNOLOGY, Vol. 3.

Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in Reactor Downcomer Geometry

Tai, C.-K., Nguyen, T., Iskhakov, A. S., Merzari, E., Dinh, N. T., & Bolotnov, I. A. (2023, June 17). NUCLEAR TECHNOLOGY, Vol. 6.

Interface Capturing Flow Boiling Simulations in a Compact Heat Exchanger

ASME JOURNAL OF HEAT AND MASS TRANSFER, 145(4).

Machine learning from RANS and LES to inform coarse grid simulations

PROGRESS IN NUCLEAR ENERGY, 163.

Uncertainty Quantification for Multiphase Computational Fluid Dynamics Closure Relations with a Physics-Informed Bayesian Approach

Liu, Y., Dinh, N., Sun, X., & Hu, R. (2023, February 17). NUCLEAR TECHNOLOGY, Vol. 2.

A Perspective on Data-Driven Coarse Grid Modeling for System Level Thermal Hydraulics

Iskhakov, A. S., Tai, C.-K., Bolotnov, I. A., & Dinh, N. T. (2022, September 10). NUCLEAR SCIENCE AND ENGINEERING.

An adaptive knowledge-based data-driven approach for turbulence modeling using ensemble learning technique under complex flow configuration: 3D PWR sub-channel with DNS data

NUCLEAR ENGINEERING AND DESIGN, 393.

Development and assessment of a reactor system prognosis model with physics-guided machine learning

NUCLEAR ENGINEERING AND DESIGN, 398.

Development and assessment of prognosis digital twin in a NAMAC system

ANNALS OF NUCLEAR ENERGY, 179.

Digital-twin-based improvements to diagnosis, prognosis, strategy assessment, and discrepancy checking in a nearly autonomous management and control system

Annals of Nuclear Energy, 166, 108715.

AI-Guided Reasoning-Based Operator Support System for the Nuclear Power Plant Management

ANNALS OF NUCLEAR ENERGY, 154.

Deep learning interfacial momentum closures in coarse-mesh CFD two-phase flow simulation using validation data

INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 135.

Development and assessment of a nearly autonomous management and control system for advanced reactors

Annals of Nuclear Energy, 150, 107861.

Development of a Nearly Autonomous Management and Control (NAMAC) System for Advanced Reactors (Final Report for ARPA-E Project)

Development of the Machine Learning-based Safety Significant Factor Inference Model for Diagnosis in Autonomous Control System

ANNALS OF NUCLEAR ENERGY, 162.

Enhancing the Operational Resilience of Advanced Reactors with Digital Twins by Recurrent Neural Networks

Enhancing the Operational Resilience of Advanced Reactors with Digital Twins by Recurrent Neural Networks

2021 RESILIENCE WEEK (RWS).

Integration of neural networks with numerical solution of PDEs for closure models development

PHYSICS LETTERS A, 406.

Uncertainty quantification and software risk analysis for digital twins in the nearly autonomous management and control systems: A review

[Review of ]. ANNALS OF NUCLEAR ENERGY, 160.

Uncertainty quantification for Multiphase-CFD simulations of bubbly flows: a machine learning-based Bayesian approach supported by high-resolution experiments

RELIABILITY ENGINEERING & SYSTEM SAFETY, 212.

Adequacy evaluation of smoothed particle hydrodynamics methods for simulating the external-flooding scenario

Nuclear Engineering and Design, 365.

An Application of ASP in Nuclear Engineering: Explaining the Three Mile Island Nuclear Accident Scenario

HANNA, B. O. T. R. O. S. N., TRIEU, L. Y. L. Y. T., SON, T. R. A. N. C., & DINH, N. A. M. T. (2020, November). THEORY AND PRACTICE OF LOGIC PROGRAMMING, Vol. 20, pp. 926–941.

Computationally efficient CFD prediction of bubbly flow using physics-guided deep learning

International Journal of Multiphase Flow, 131.

Enhancement of risk informed validation framework for external hazard scenario

Reliability Engineering and System Safety, 204.

Machine-learning based error prediction approach for coarse-grid Computational Fluid Dynamics (CG-CFD)

PROGRESS IN NUCLEAR ENERGY, 118.

Probing interfacial momentum closures in two-phase bubbly flow with machine learning-aided methods

Transactions of the American Nuclear Society, 122, 844–847.

Reynolds-Averaged Turbulence Modeling Using Deep Learning with Local Flow Features: An Empirical Approach

NUCLEAR SCIENCE AND ENGINEERING, 194(8-9), 650–664.

Risk informed validation framework for external flooding scenario

NUCLEAR ENGINEERING AND DESIGN, 356.

Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation

Annals of Nuclear Energy, 147.

A data-driven framework for error estimation and mesh-model optimization in system-level thermal-hydraulic simulation

NUCLEAR ENGINEERING AND DESIGN, 349, 27–45.

A framework for assessment of predictive capability maturity and its application in nuclear thermal hydraulics

NUCLEAR ENGINEERING AND DESIGN, 354.

Classification of machine learning frameworks for data-driven thermal fluid models

INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 135, 559–579.

Demonstration of a data-driven approach for error estimation in two-phase flow simulation using coarse-mesh CFD

Transactions of the American Nuclear Society, 121, 1865–1868.

The life and the contribution of B. R. Sehgal, G. Yadigaroglu and G. Hewitt: Remembrance statements

Nuclear Engineering and Design, 354.

Uncertainty quantification of two-phase flow and boiling heat transfer simulations through a data-driven modular Bayesian approach

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 138, 1096–1116.

Validation and uncertainty quantification of multiphase-CFD solvers: A data-driven Bayesian framework supported by high-resolution experiments

NUCLEAR ENGINEERING AND DESIGN, 354.

Data-driven modeling for boiling heat transfer: Using deep neural networks and high-fidelity simulation results

APPLIED THERMAL ENGINEERING, 144, 305–320.

Experimental investigations on the boiling heat transfer of horizontal flow in the near-critical region

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 125, 618–628.

Flow boiling in tubes

In Handbook of Thermal Science and Engineering (pp. 1907–1949).

Probabilistic risk assessment based model validation method using Bayesian network

RELIABILITY ENGINEERING & SYSTEM SAFETY, 169, 380–393.

Safe reactor depressurization windows for BWR Mark I Station Blackout accident management strategy

ANNALS OF NUCLEAR ENERGY, 114, 518–529.

Validation and Uncertainty Quantification for Wall Boiling Closure Relations in Multiphase-CFD Solver

Nuclear Science and Engineering, 193(1-2), 81–99.

A study of heat transfer scaling of supercritical pressure water in horizontal tubes

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 114, 923–933.

Experimental study on the difference of heat transfer characteristics between vertical and horizontal flows of supercritical pressure water

APPLIED THERMAL ENGINEERING, 113, 609–620.

Sensitivity analysis of interfacial momentum closure terms in two phase flow and boiling simulations using MCFD solver

ASME 2017 Heat Transfer Summer Conference, HT 2017, 2.

A computational study of thin film dynamics on micro-structured surfaces

A Computational study of thin film dynamics on micro structured surfaces. Proceedings of the Asme Summer Heat Transfer Conference, 2016, vol 2, 2.

Analysis of heat transfer under high heat flux nucleate boiling conditions

Kerntechnik, 81(3), 308–314.

A study of the effect of binary oxide materials in a single droplet vapor explosion

Nuclear Engineering and Design, 264, 168–175.

Guest editorial special issue on “Nuclear reactor safety simulation and uncertainty analysis”

Guest editorial special issue on “Nuclear reactor safety simulation and uncertainty analysis.” Annals of Nuclear Energy, 52, 1.

Simulation and validation of the dynamics of liquid films evaporating on horizontal heater surfaces

Applied Thermal Engineering, 48, 486–494.

An experimental study of rupture dynamics of evaporating liquid films on different heater surfaces

International Journal of Heat and Mass Transfer, 54(7-8), 1538–1547.

A reconstructed discontinuous Galerkin method for the compressible Navier–Stokes equations on arbitrary grids

Journal of Computational Physics, 229(19), 6961–6978.

An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head

Nuclear Engineering and Design, 240(9), 2148–2159.

Diagnostic techniques for the dynamics of a thin liquid film under forced flow and evaporating conditions

Microfluidics and Nanofluidics, 9(6), 1077–1089.

The defor-s experimental study of debris formation with corium simulant materials

Nuclear Technology, 170(1), 219–230.

The effects of debris bed's prototypical characteristics on corium coolability in a LWR severe accident

Nuclear Engineering and Design, 240(3), 598–608.

A scoping study of debris bed formation in the DEFOR test facility

Nuclear Engineering and Design, 239(9), 1653–1659.

Dynamics and preconditioning in a single-droplet vapor explosion

Nuclear Technology, 167(1), 223–234.

Risk-informed safety margin characterization

International Conference on Nuclear Engineering, Proceedings, ICONE, 1, 11–17.

Simulation of core melt pool formation in a Reactor pressure vessel lower head using an Effective Convectivity Model

Nuclear Engineering and Technology, 41(7), 929–944.

Simultaneous high speed digital cinematographic and X-ray radiographic imaging of a intense multi-fluid interaction with rapid phase changes

Experimental Thermal and Fluid Science, 33(4), 754–763.

The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part I: Physical processes, modeling and model implementation

Progress in Nuclear Energy, 51(8), 849–859.

The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part II: Model assessment and application

Progress in Nuclear Energy, 51(8), 860–871.

Thermal-hydraulic performance of heavy liquid metal in straight-tube and U-tube heat exchangers

Nuclear Engineering and Design, 239(7), 1323–1330.

Integration of multiphase science and technology with risk management in nuclear power reactors

Multiphase Science and Technology, 20(2), 81–211.

The effect of thermal radiation on the solidification dynamics of metal oxide melt droplets

Nuclear Engineering and Design, 238(6), 1421–1429.

Aerobreakup in disturbed subsonic and supersonic flow fields

Journal of Fluid Mechanics, 593, 131–170.

Adaptive characteristics-based matching (aCBM): A method for interfacial dynamics in compressible multiphase flows

In Fluid Mechanics and its Applications (Vol. 81, pp. 341–352).

Adaptive characteristics-based matching for compressible multifluid dynamics

Journal of Computational Physics, 213(2), 500–529.

Compressible multi-hydrodynamics (CMH): Breakup, mixing and dispersal of liquids/solids in high speed flows

In Fluid Mechanics and its Applications (Vol. 81, pp. 353–369).

High heat flux boiling and burnout as microphysical phenomena: Mounting evidence and opportunities

Multiphase Science and Technology, 18(3), 251–276.

Introduction to the Festschrift honoring the 70th Birthday of Professor Bal Raj Sehgal

Nuclear Engineering and Design, 236(19-21), 1939–1940.

On the numerical simulation of acceleration-driven multi-fluid mixing

Multiphase Science and Technology, 18(3), 199–230.

On improving mass conservation of level set by reducing spatial discretization errors

International Journal of Multiphase Flow, 31(12), 1329–1336.

Sharp treatment of surface tension and viscous stresses in multifluid dynamics

17th AIAA Computational Fluid Dynamics Conference.

Shock wave refraction patterns at interfaces

International Journal of Multiphase Flow, 31(9), 969–995.

A numerical study of the shape effect on drag in supersonic low reynolds number (rarefied) flows

AIAA Paper, 6566–6575.

A pseudocompressibility method for the numerical simulation of incompressible multifluid flows

International Journal of Multiphase Flow, 30(7-8 SPEC. ISS.), 901–937.

Aerobreakup in rarefied supersonic gas flows

Journal of Fluids Engineering, Transactions of the ASME, 126(4), 516–527.

Characterization and predictability of transient heat transfer in an unstably stratified fluid layer during power startup

37th AIAA Thermophysics Conference.

Particle-to-particle long range interaction and drag in supersonic flows

AIAA Paper, 6604–6614.