Nam Dinh

Also known as: T.N. Dinh; Truc-Nam Dinh; Nam Truc Dinh; N.T. Dinh

https://orcid.org/0000-0003-0879-9710

nuclear reactor safety, thermal-hydraulics, severe accidents, boiling heat transfer, modeling and simulation, verification and validation

Works (169)

2020 journal article

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

Nuclear Engineering and Design, 365.

By: L. Lin, N. Montanari, S. Prescott, R. Sampath, H. Bao & N. Dinh

Source: ORCID
Added: July 28, 2020

2020 journal article

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

International Journal of Multiphase Flow, 131.

By: H. Bao, J. Feng, N. Dinh & H. Zhang

Source: ORCID
Added: July 28, 2020

2020 journal article

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

PROGRESS IN NUCLEAR ENERGY, 118.

By: B. Hanna, N. Dinh, R. Youngblood & I. Bolotnov

Sources: Web Of Science, ORCID
Added: January 21, 2020

2020 article

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

NUCLEAR SCIENCE AND ENGINEERING, Vol. 2, pp. 1–15.

By: C. Chang, J. Fang & N. Dinh

Sources: Web Of Science, ORCID
Added: April 20, 2020

2020 journal article

Risk informed validation framework for external flooding scenario

NUCLEAR ENGINEERING AND DESIGN, 356.

By: S. Bodda, A. Gupta & N. Dinh

Sources: Web Of Science, ORCID
Added: January 13, 2020

2020 journal article

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

Annals of Nuclear Energy, 147.

By: H. Bao, N. Dinh, L. Lin, R. Youngblood, J. Lane & H. Zhang

Source: ORCID
Added: July 28, 2020

2019 conference paper

A data-driven approach to scale bridging in system thermal-hydraulic simulation

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 6069–6082.

By: H. Bao, R. Youngblood, H. Zhang, N. Dinh, L. Lin & J. Lane

Source: ORCID
Added: July 28, 2020

2019 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 349, 27–45.

By: H. Bao, N. Dinh, J. Lane & R. Youngblood

Sources: Web Of Science, ORCID
Added: June 4, 2019

2019 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 354.

By: P. Athe & N. Dinh

Sources: Web Of Science, ORCID
Added: September 9, 2019

2019 conference paper

An artificial intelligence-guided decision support system for the nuclear power plant management

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 394–406.

By: B. Hanna, T. Son & N. Dinh

Source: ORCID
Added: July 28, 2020

2019 conference paper

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

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 981–992.

By: L. Lin, N. Dinh, S. Prescott, H. Bao, N. Montanari & R. Sampath

Source: ORCID
Added: July 28, 2020

2019 journal article

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

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

By: C. Chang & N. Dinh

Sources: Web Of Science, ORCID
Added: May 28, 2019

2019 conference paper

Development of a data-driven turbulence model for 3D thermal stratification simulation during reactor transients

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 2223–2234.

By: Y. Zhu, N. Dinh, R. Hu & A. Kraus

Source: ORCID
Added: July 28, 2020

2019 conference paper

Reynolds-averaged turbulence modeling using deep learning with local flow features

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 1698–1711.

By: C. Chang, J. Fang & N. Dinh

Source: ORCID
Added: July 28, 2020

2019 journal article

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

Nuclear Engineering and Design, 354.

By: N. Aksan, M. Andreani, S. Bechta, M. Corradini, F. D’Auria, V. Dhir, W. Frid, J. Jones ...

Source: ORCID
Added: July 28, 2020

2019 conference paper

Uncertainty quantification and reduction for multiphase-CFD solvers: A data-driven Bayesian approach supported by high-resolution local measurements

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 3582–3597.

By: Y. Liu, X. Sun, Y. Liu & N. Dinh

Source: ORCID
Added: July 28, 2020

2019 journal article

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.

By: Y. Liu, N. Dinh, R. Smith & X. Sun

Sources: Web Of Science, ORCID
Added: July 15, 2019

2019 journal article

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

NUCLEAR ENGINEERING AND DESIGN, 354.

By: Y. Liu, X. Sun & N. Dinh

Sources: Web Of Science, ORCID
Added: September 9, 2019

2018 conference paper

Coarse grid computational fluid dynamics (cg-cfd) error prediction via random forest regression

Proceedings of the 2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018, 1125–1133.

By: B. Hanna, N. Dinh & I. Bolotnov

Source: ORCID
Added: July 28, 2020

2018 journal article

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

Applied Thermal Engineering, 144, 305–320.

By: Y. Liu, N. Dinh, Y. Sato & B. Niceno

Sources: NC State University Libraries, ORCID
Added: December 17, 2018

2018 conference paper

Design of validation experiments for model improvement of dispersed flow film boiling in COBRA-TF

Transactions of the American Nuclear Society, 119, 133–136.

By: X. Zhang, Y. Liu, X. Sun & N. Dinh

Source: ORCID
Added: July 28, 2020

2018 journal article

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.

By: X. Lei, W. Zhang, J. Zhang, N. Dinh & H. Li

Sources: NC State University Libraries, ORCID
Added: October 19, 2018

2018 book

Flow boiling in tubes

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

By: Y. Liu & N. Dinh

Source: ORCID
Added: July 28, 2020

2018 conference paper

Inverse uncertainty quantification of turbulence modeling in multiphase-CFD solver using high-resolution data from particle image velocimetry

International Topical Meeting on Advances in Thermal Hydraulics, ATH 2018 - Embedded Topical Meeting, 1028–1040.

By: Y. Liu, S. Shi, Y. Qian, X. Sun & N. Dinh

Source: ORCID
Added: July 28, 2020

2018 conference paper

Predictive capability and maturity assessment with Bayesian network

Transactions of the American Nuclear Society, 118, 1087–1090.

By: L. Lin & N. Dinh

Source: ORCID
Added: July 28, 2020

2018 journal article

Probabilistic risk assessment based model validation method using Bayesian network

Reliability Engineering and System Safety, 169, 380–393.

By: S. Kwag, A. Gupta & N. Dinh

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2018 journal article

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

Annals of Nuclear Energy, 114, 518–529.

By: H. Bao, H. Zhao, H. Zhang, L. Zou, P. Sharpe & N. Dinh

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2018 conference paper

Study of data-driven mesh-model optimization in system thermal-hydraulic simulation

Transactions of the American Nuclear Society, 118, 1091–1094.

By: H. Bao, N. Dinh, J. Lane & R. Youngblood

Source: ORCID
Added: July 28, 2020

2018 journal article

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

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

By: Y. Liu & N. Dinh

Sources: ORCID, Crossref
Added: February 24, 2020

2017 conference paper

A data-driven approach for turbulence modeling

17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-September.

By: Y. Zhu & N. Dinh

Source: ORCID
Added: July 28, 2020

2017 journal article

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

International Journal of Heat and Mass Transfer, 114, 923–933.

By: X. Lei, H. Li, N. Dinh & W. Zhang

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2017 conference paper

Assessment of smoothed particle hydrodynamics in application of high-wind risk analysis

17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-September.

By: L. Lin, N. Dinh, N. Montanari, R. Sampath, N. Akinci & S. Prescott

Source: ORCID
Added: July 28, 2020

2017 conference paper

Development of a VUQ framework for Wall Boiling model in McFD Solver

17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-September.

By: Y. Liu & N. Dinh

Source: ORCID
Added: July 28, 2020

2017 journal article

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

Applied Thermal Engineering, 113, 609–620.

By: X. Lei, H. Li, W. Zhang, N. Dinh, Y. Guo & S. Yu

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2017 conference paper

Integrated use of modeling and simulation in high winds PRA

International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017, 1, 30–39.

By: S. Hess, S. Prescott, C. Smith, L. Lin, N. Dinh, R. Sampath, N. Montanari

Source: ORCID
Added: July 28, 2020

2017 conference paper

Physics-constrained machine learning for two-phase flow simulation using deep learning-based closure relation

Transactions of the American Nuclear Society, 117, 1749–1752.

By: C. Chang, N. Dinh & S. Cetiner

Source: ORCID
Added: July 28, 2020

2017 conference paper

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.

By: Y. Liu, C. Rollins, N. Dinh & H. Luo

Sources: NC State University Libraries, ORCID
Added: August 6, 2018

2016 conference paper

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

ASME 2016 Heat Transfer Summer Conference, HT 2016, collocated with the ASME 2016 Fluids Engineering Division Summer Meeting and the ASME 2016 14th International Conference on Nanochannels, Microchannels, and Minichannels, 2.

By: L. Lin, R. Sampath, N. Dinh & N. Akinci

Source: ORCID
Added: July 28, 2020

2016 conference paper

A study of bwr mark i station blackout accident with GOTHIC modeling

International Congress on Advances in Nuclear Power Plants, ICAPP 2016, 1, 184–193.

By: H. Bao, N. Dinh, O. Omotowa, H. Zhao, H. Zhang, L. Zou, R. Szilard

Source: ORCID
Added: July 28, 2020

2016 conference paper

A study of physics-informed deep learning for system fluid dynamics closures

Transactions of the American Nuclear Society, 115, 1785–1788.

By: C. Chang & N. Dinh

Source: ORCID
Added: July 28, 2020

2016 journal article

Analysis of heat transfer under high heat flux nucleate boiling conditions

Kerntechnik, 81(3), 308–314.

By: Y. Liu & N. Dinh

Source: ORCID
Added: July 28, 2020

2016 conference paper

Assessment of a smoothed particle hydrodynamics method for thin film on textured surfaces

Transactions of the American Nuclear Society, 115, 1453–1456.

By: L. Lin & N. Dinh

Source: ORCID
Added: July 28, 2020

2016 conference paper

Development of a severe accident analysis engine using approximate reasoning

Transactions of the American Nuclear Society, 115, 830–833.

By: J. Lee, N. Dinh & T. Son

Source: ORCID
Added: July 28, 2020

2016 journal article

Foreword special issue on the 16th international topical meeting on nuclear reactor thermal hydraulics

Nuclear Science and Engineering, 184(3), III-.

By: M. Corradini, N. Dinh & S. Leon

Source: NC State University Libraries
Added: August 6, 2018

2016 conference paper

High-fidelity simulation-driven model development for coarse-grained computational fluid dynamics

International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016, 121–131.

By: B. Hanna, N. Dinh & I. Bolotnov

Source: ORCID
Added: July 28, 2020

2016 conference paper

Investigation of similarity metrics for simulation based scaling analysis

International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016, 409–425.

By: P. Athe, N. Dinh & H. Abdel-Khalik

Source: ORCID
Added: July 28, 2020

2015 conference paper

Foreword

International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 1.

By: N. Dinh, H. No, X. Sun, S. Leon, E. Merzari & W. Pointer

Source: ORCID
Added: July 28, 2020

2015 conference paper

Simulation of BWR Mark i station black-out accident using GOTHIc: An initial demonstration

Transactions of the American Nuclear Society, 113, 1377–1380.

By: H. Bao, H. Zhao, H. Zhang, L. Zou, R. Szilard & N. Dinh

Source: ORCID
Added: July 28, 2020

2015 conference paper

Treatment of nucleation and bubble dynamics in high heat flux film boiling

International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 5, 4097–4111.

By: Y. Liu & N. Dinh

Source: ORCID
Added: July 28, 2020

2014 conference paper

A framework for assessment of severe accident management effectiveness in Nordic BWR plants

PSAM 2014 - Probabilistic Safety Assessment and Management.

By: P. Kudinov, S. Galushin, S. Yakush, W. Villanueva, V. Phung, D. Grishchenko, N. Dinh

Source: ORCID
Added: July 28, 2020

2014 conference paper

A scoping study of direct containment heating in a small modular reactor

Transactions of the American Nuclear Society, 111, 907–910.

By: C. Chang & N. Dinh

Source: ORCID
Added: July 28, 2020

2014 conference paper

Advanced calibration and validation of a mechanistic model of subcooled boiling two-phase flow

International Congress on Advances in Nuclear Power Plants, ICAPP 2014, 2, 1486–1493.

By: A. Bui, B. Williams & N. Dinh

Source: ORCID
Added: July 28, 2020

2014 conference paper

Development of 3D containment simulation capability: High pressure steam slowdown scenario

Transactions of the American Nuclear Society, 111, 1545–1548.

By: B. Hanna, N. Dinh & I. Bolotnov

Source: ORCID
Added: July 28, 2020

2014 conference paper

Validation data: Managing the weak link

Transactions of the American Nuclear Society, 111, 1444–1445.

By: N. Dinh, W. Ren & H. Lee

Source: ORCID
Added: July 28, 2020

2013 journal article

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

Nuclear Engineering and Design, 264, 168–175.

By: R. Hansson, T. Dinh & L. Manickam

Sources: ORCID, Crossref
Added: July 28, 2020

2013 journal article

Guest editorial special issue on "nuclear reactor safety simulation and uncertainty analysis"

Annals of Nuclear Energy, 52, 1.

By: T. Dinh

Source: ORCID
Added: July 28, 2020

2013 conference paper

Observations of bubble nucleation and interaction dynamics in high heat flux boiling

Transactions of the American Nuclear Society, 109(PART 2), 1819–1820.

By: T. Dinh & J. Tu

Source: ORCID
Added: July 28, 2020

2013 conference paper

Statistical modeling support for calibration of a multiphysics model of subcooled boiling flows

International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013, 3, 2229–2244.

By: A. Bui, N. Dinh, R. Nourgaliev & B. Williams

Source: ORCID
Added: July 28, 2020

2012 journal article

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

Applied Thermal Engineering, 48, 486–494.

By: S. Gong, W. Ma & T. Dinh

Source: ORCID
Added: July 28, 2020

2011 conference paper

A system simulation code to support the safety case in the LVVR life extension: Selection, development, and testing of code architecture and solution algorithms, invited

Transactions of the American Nuclear Society, 104, 951–953.

By: T. Dinh, R. Nourgaliev & R. Youngblood

Source: ORCID
Added: July 28, 2020

2011 journal article

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.

By: S. Gong, W. Ma & T. Dinh

Source: ORCID
Added: July 28, 2020

2011 conference paper

Framework for applying a next-generation safety analysis code to plant life extension decision making, invited

Transactions of the American Nuclear Society, 104, 949–950.

By: R. Youngblood, R. Nourgaliev, D. Kelly, C. Smith & T. Dinh

Source: ORCID
Added: July 28, 2020

2011 conference paper

Heartbeat model for component failure time in simulation of plant behavior

International Topical Meeting on Probabilistic Safety Assessment and Analysis 2011, PSA 2011, 1, 646–654.

By: R. Youngblood, R. Nourgaliev, D. Kelly, C. Smith & T. Dinh

Source: ORCID
Added: July 28, 2020

2011 conference paper

Lessons learned from an initial VU-assessed code development effort

Transactions of the American Nuclear Society, 104, 358–360.

By: R. Nourgaliev, T. Dinh & R. Nelson

Source: ORCID
Added: July 28, 2020

2011 conference paper

On physics modeling and components development in R7

Transactions of the American Nuclear Society, 104, 523–525.

By: A. Bui, R. Nourgaliev & T. Dinh

Source: ORCID
Added: July 28, 2020

2010 journal article

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

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

By: H. Luo, L. Luo, R. Nourgaliev, V. Mousseau & N. Dinh

Sources: ORCID, Crossref
Added: July 28, 2020

2010 journal article

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.

By: C. Tran, P. Kudinov & T. Dinh

Sources: ORCID, Crossref
Added: July 28, 2020

2010 journal article

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

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

By: S. Gong, W. Ma & T. Dinh

Sources: ORCID, Crossref
Added: July 28, 2020

2010 journal article

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

Nuclear Technology, 170(1), 219–230.

By: P. Kudinov, A. Karbojian, M. Weimin & T. Dinh

Source: ORCID
Added: July 28, 2020

2010 journal article

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

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

By: W. Ma & T. Dinh

Sources: ORCID, Crossref
Added: July 28, 2020

2009 journal article

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

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

By: A. Karbojian, W. Ma, P. Kudinov & T. Dinh

Sources: ORCID, Crossref
Added: July 28, 2020

2009 journal article

Dynamics and preconditioning in a single-droplet vapor explosion

Nuclear Technology, 167(1), 223–234.

By: R. Hansson, H. Park & T. Dinh

Source: ORCID
Added: July 28, 2020

2009 conference paper

Risk-informed safety margin characterization

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

By: S. Hess, N. Dinh, J. Gaertner & R. Szilard

Source: ORCID
Added: July 28, 2020

2009 journal article

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.

By: C. Tran & T. Dinh

Source: ORCID
Added: July 28, 2020

2009 journal article

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.

By: R. Hansson, H. Park & T. Dinh

Source: ORCID
Added: July 28, 2020

2009 journal article

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.

By: C. Tran & T. Dinh

Source: ORCID
Added: July 28, 2020

2009 journal article

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

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

By: W. Ma, A. Karbojian, B. Sehgal & T. Dinh

Sources: ORCID, Crossref
Added: July 28, 2020

2008 conference paper

A computational study of debris bed formation

Transactions of the American Nuclear Society, 98, 341–342.

By: P. Kudinov & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

A study of ex-vessel debris formation in a LWR severe accident

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 5, 2848–2859.

By: P. Kudinov, A. Karbojian, W. Ma, M. Davydov & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

A study of reactor systems during a loss of offsite electric power in Forsmark-1 plant

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 4, 2642–2651.

By: S. Roshan, W. Ma, T. Kozlowski & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

An effective convectivity model for simulation of in-vessel core melt progression in a boiling water reactor

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 2, 925–935.

By: C. Tran & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

An experimental study on debris formation with corium simulant materials

International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 2, 1191–1199.

By: P. Kudinov, A. Karbojian, W. Ma & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

Application of the phase-change effective convectivity model to analysis of core melt pool formation and heat transfer in a BWR lower head

Transactions of the American Nuclear Society, 98, 617–618.

By: C. Tran & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

Design of BWR instability suppression system

International Conference on the Physics of Reactors 2008, PHYSOR 08, 3, 2062–2068.

By: A. Kubarev, T. Kozlowski, S. Roshan & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

Effect of non-condensable gases on triggering and energetics of a single drop vapor explosion

Transactions of the American Nuclear Society, 98, 547–548.

By: R. Hansson & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

European Research on the Corium issues within the SARNET network of excellence

International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 2, 1172–1181.

By: C. Journeau, J. Bonnet, L. Godin-Jacqmin, P. Piluso, D. Tarabelli, E. Dufour, B. Spindler, L. Nicolas ...

Source: ORCID
Added: July 28, 2020

2008 journal article

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

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

By: T. Theofanous & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

Modeling of two-phase natural convection flows in a water pool with a decay-heated debris bed

International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 2, 1141–1150.

By: S. Yakush, P. Kudinov & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

Multiphase flow phenomena of steam generator tube rupture in a lead-cooled reactor system: A scoping analysis

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 5, 2765–2775.

By: T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

On solidification mechanism that governs the effect of binary melt composition on steam explosion energetics

Transactions of the American Nuclear Society, 98, 615–616.

By: T. Dinh, R. Hansson & P. Kudinov

Source: ORCID
Added: July 28, 2020

2008 conference paper

Relating system-to-CFD coupled code analyses to theoretical framework of a multiscale method

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 5, 2959–2967.

By: F. Cadinu, T. Kozlowski & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

Spatial coupling for BWR stability analysis

Transactions of the American Nuclear Society, 98, 603–605.

By: T. Kozlowski, J. Peltonen & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 conference paper

Spatial coupling for coupled code safety analysis of BWR design-basis accidents

International Conference on the Physics of Reactors 2008, PHYSOR 08, 2, 1313–1320.

By: J. Peltonen, T. Kozlowski & T. Dinh

Source: ORCID
Added: July 28, 2020

2008 journal article

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

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

By: L. Dombrovsky & T. Dinh

Sources: ORCID, Crossref
Added: July 28, 2020

2007 conference paper

A study on effects of debris bed prototypicality on coolability

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: M. Weimin & T. Dinh

Source: ORCID
Added: July 28, 2020

2007 journal article

Aerobreakup in disturbed subsonic and supersonic flow fields

Journal of Fluid Mechanics, 593, 131–170.

By: T. Theofanous, G. Li, T. Dinh & C. Chang

Sources: ORCID, Crossref
Added: July 28, 2020

2007 conference paper

An analytical study of mechanisms that govern debris packing in a LWR severe accident

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: P. Kudinov & N. Dinh

Source: ORCID
Added: July 28, 2020

2007 conference paper

Dynamics and preconditioning in a single drop vapor explosion

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: R. Hansson, H. Park & T. Dinh

Source: ORCID
Added: July 28, 2020

2007 conference paper

Evaluation of coupled codes RELAP5/PARCS capability for BWR global stability prediction

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: T. Kozlowski, S. Roshan & T. Dinh

Source: ORCID
Added: July 28, 2020

2007 conference paper

Material property effect in steam explosion energetics: Revisited

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: T. Dinh

Source: ORCID
Added: July 28, 2020

2007 conference paper

RELAP5 and TRACE codes comparison and validation under steady-state and transient conditions on the basis of NUPEC data

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: J. Suchoszek, F. Cadinu, T. Kozlowski & T. Dinh

Source: ORCID
Added: July 28, 2020

2007 conference paper

Simulation of core melt pool formation in a reactor pressure vessel lower head using an effective convectivity model

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: C. Tran & T. Dinh

Source: ORCID
Added: July 28, 2020

2007 conference paper

Thermal-hydraulic performance of lead-bismuth eutectic in a straight-tube and a U-tube heat exchangers

Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12.

By: M. Weimin, A. Karbojian, B. Sehgal & T. Dinh

Source: ORCID
Added: July 28, 2020

2006 book

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).

By: R. Nourgaliev, N. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2006 journal article

Adaptive characteristics-based matching for compressible multifluid dynamics

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

By: R. Nourgaliev, T. Dinh & T. Theofanous

Sources: ORCID, Crossref
Added: July 28, 2020

2006 conference paper

Analysis of melt pool heat transfer in a BWR lower head

Transactions of the American Nuclear Society, 95, 629–631.

By: C. Tran & T. Dinh

Source: ORCID
Added: July 28, 2020

2006 book

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).

By: T. Theofanous, R. Nourgaliev, G. Li & N. Dinh

Source: ORCID
Added: July 28, 2020

2006 journal article

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

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

By: T. Theofanous & T. Dinh

Source: ORCID
Added: July 28, 2020

2006 journal article

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

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

By: N. Dinh, M. Bürger & G. Lohnert

Source: ORCID
Added: July 28, 2020

2006 journal article

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

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

By: T. Dinh, R. Nourgaliev & T. Theofanous

Source: ORCID
Added: July 28, 2020

2006 conference paper

RELAP5 performance in predicting critical power in a BWR fuel bundle

Transactions of the American Nuclear Society, 95, 650–651.

By: F. Cadinu, T. Kozlowski & T. Dinh

Source: ORCID
Added: July 28, 2020

2006 book

Treatment of particle collisions in direct numerical simulations of high speed compressible flows

In Fluid Mechanics and its Applications (Vol. 81, pp. 247–259).

By: R. Nourgaliev, N. Dinh, L. Nguyen & T. Theofanous

Source: ORCID
Added: July 28, 2020

2005 conference paper

Adaptive strategies for mass conservation in level set treatment

17th AIAA Computational Fluid Dynamics Conference.

By: R. Nourgaliev, S. Wiri, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2005 conference paper

Investigation of breakup of isolated and multiple drops in subsonic flow

43rd AIAA Aerospace Sciences Meeting and Exhibit - Meeting Papers, 4995–5005.

By: G. Li, T. Dinh, Y. Yang & T. Theofanous

Source: ORCID
Added: July 28, 2020

2005 conference paper

Numerical investigation of shock wave refraction patterns at multimaterial interfaces

43rd AIAA Aerospace Sciences Meeting and Exhibit - Meeting Papers, 10905–10921.

By: R. Nourgaliev, S. Suschikh, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2005 journal article

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

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

By: R. Nourgaliev, S. Wiri, N. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2005 conference paper

Sharp treatment of surface tension and viscous stresses in multifluid dynamics

17th AIAA Computational Fluid Dynamics Conference.

By: R. Nourgaliev, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2005 journal article

Shock wave refraction patterns at interfaces

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

By: R. Nourgaliev, S. Sushchikh, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 conference paper

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

AIAA Paper, 6566–6575.

By: S. Sushchikh, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 journal article

A pseudocompressibility method for the numerical simulation of incompressible multifluid flows

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

By: R. Nourgaliev, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 journal article

Aerobreakup in rarefied supersonic gas flows

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

By: T. Theofanous, G. Li & T. Dinh

Source: ORCID
Added: July 28, 2020

2004 conference paper

An experimental study of droplet breakup in supersonic flow: The effect of long-range interactions

AIAA Paper, 12063–12073.

By: G. Li, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 conference paper

Burnout in high heat flux boiling: The hydrodynaraic and physico-chemical factors

AIAA Paper, 1865–1872.

By: T. Dinh, J. Tu & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 conference paper

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

37th AIAA Thermophysics Conference.

By: T. Dinh, J. Tu, Y. Yang, R. Nourgaliev & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 conference paper

Direct numerical simulation of disperse multiphase high-speed flows

AIAA Paper, 10365–10375.

By: R. Nourgaliev, T. Dinh, T. Theofanous, J. Koning, R. Greenman & G. Nakafuji

Source: ORCID
Added: July 28, 2020

2004 conference paper

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

AIAA Paper, 6604–6614.

By: G. Li, R. Nourgaliev, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 conference paper

Rayleigh-Bénard natural convection heat transfer: Pattern formation, complexity and predictability

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, 1342–1352.

By: T. Dinh, Y. Yang, J. Tu, R. Nourgaliev & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 journal article

The Characteristics-Based Matching (CBM) method for compressible flow with moving boundaries and interfaces

Journal of Fluids Engineering, Transactions of the ASME, 126(4), 586–604.

By: R. Nourgaliev, T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2004 conference paper

Two-phase natural circulation flow in AP-1000 in-vessel retention-related ULPU-V facility experiments

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04, 928–938.

By: T. Dinh, J. Tu & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 conference paper

A characteristics-based approach to the numerical solution of the two-fluid model

Proceedings of the ASME/JSME Joint Fluids Engineering Conference, 2 B, 1729–1748.

By: R. Nourgaliev, N. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 conference paper

Aerobreakup in rarefied supersonic gas flows

Proceedings of the ASME/JSME Joint Fluids Engineering Conference, 2 B, 1685–1703.

By: T. Theofanous, G. Li & T. Dinh

Source: ORCID
Added: July 28, 2020

2003 conference paper

An investigation of droplet breakup in a high mach, low Weber number regime

41st Aerospace Sciences Meeting and Exhibit.

By: T. Dinh, G. Li & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 journal article

Assessment of reactor vessel integrity (ARVI)

Nuclear Engineering and Design, 221(1-3 SPEC.), 23–53.

By: B. Sehgal, A. Theerthan, A. Giri, A. Karbojian, H. Willschütz, O. Kymäläinen, S. Vandroux, J. Bonnet ...

Source: ORCID
Added: July 28, 2020

2003 journal article

Nucleation phenomena in boiling

Multiphase Science and Technology, 15(1-4), 349–363.

By: T. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 conference paper

Nucleation phenomena in boiling on nanoscopically smooth surfaces

41st Aerospace Sciences Meeting and Exhibit.

By: T. Dinh, J. Tu, A. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 journal article

On the multiscale treatment of multifluid flow

Multiphase Science and Technology, 15(1-4), 275–288.

By: T. Dinh, R. Nourgaliev & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 conference paper

The 'Characteristics-Based Matching' (CBM) method for compressible flow with moving boundaries and interfaces

Proceedings of the ASME/JSME Joint Fluids Engineering Conference, 2 B, 1705–1728.

By: R. Nourgaliev, N. Dinh & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 conference paper

The characteristics-based matching method for compressible flow in complex geometries

41st Aerospace Sciences Meeting and Exhibit.

By: R. Nourgaliev, T. Dinh, S. Sushchikh, W. Yuen & T. Theofanous

Source: ORCID
Added: July 28, 2020

2003 journal article

The lattice Boltzmann equation method: Theoretical interpretation, numerics and implications

International Journal of Multiphase Flow, 29(1), 117–169.

By: R. Nourgaliev, T. Dinh, T. Theofanous & D. Joseph

Source: ORCID
Added: July 28, 2020

2003 journal article

The multiphase Eulerian-Lagrangian transport (MELT-3D) approach for modeling of multiphase mixing in fragmentation processes

Progress in Nuclear Energy, 42(2), 123–157.

By: R. Nourgaliev, T. Dinh, A. Dinh, H. Haraldsson & B. Sehgal

Source: ORCID
Added: July 28, 2020

2002 journal article

Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment

Nuclear Engineering and Design, 211(2-3), 173–187.

By: B. Sehgal, R. Nourgaliev & T. Dinh

Source: ORCID
Added: July 28, 2020

2002 journal article

On lattice Boltzmann modeling of phase transition in an isothermal non-ideal fluid

Nuclear Engineering and Design, 211(2-3), 153–171.

By: R. Nourgaliev, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

2002 journal article

The boiling crisis phenomenon part I: Nucleation and nucleate boiling heat transfer

Experimental Thermal and Fluid Science, 26(6-7), 775–792.

By: T. Theofanous, J. Tu, A. Dinh & T. Dinh

Source: ORCID
Added: July 28, 2020

2002 journal article

The boiling crisis phenomenon part II: Dryout dynamics and burnout

Experimental Thermal and Fluid Science, 26(6-7), 793–810.

By: T. Theofanous, T. Dinh, J. Tu & A. Dinh

Source: ORCID
Added: July 28, 2020

2001 journal article

Effect of solidification on drop fragmentation in liquid-liquid media

Heat and Mass Transfer/Waerme- Und Stoffuebertragung, 37(4-5), 417–426.

By: H. Haraldsson, H. Li, Z. Yang, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

2001 journal article

Numerical investigation of boiling regime transition mechanism by a Lattice-Boltzmann model

Nuclear Engineering and Design, 204(1-3), 143–153.

By: Z. Yang, T. Dinh, R. Nourgaliev & B. Sehgal

Source: ORCID
Added: July 28, 2020

2001 journal article

Numerical investigation of bubble growth and detachment by the lattice-Boltzmann method

International Journal of Heat and Mass Transfer, 44(1), 195–206.

By: Z. Yang, T. Dinh, R. Nourgaliev & B. Sehgal

Source: ORCID
Added: July 28, 2020

2000 book

Analysis of the breakup length of a thin jet penetrating a fluid pool

In Advances in Fluid Mechanics (pp. 435–444).

By: H. Haraldsson, I. Kazachkov, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

2000 journal article

Core melt spreading on a reactor containment floor

Progress in Nuclear Energy, 36(4), 405–468.

By: T. Dinh, M. Konovalikhin & B. Sehgal

Source: ORCID
Added: July 28, 2020

2000 journal article

Evaluation of the Darcy's law performance for two-fluid flow hydrodynamics in a particle debris bed using a lattice-Boltzmann model

Heat and Mass Transfer/Waerme- Und Stoffuebertragung, 36(4), 295–304.

By: Z. Yang, T. Dinh, R. Nourgaliev & B. Sehgal

Source: ORCID
Added: July 28, 2020

2000 journal article

Numerical investigation of bubble coalescence characteristics under nucleate boiling condition by a lattice-Boltzmann model

International Journal of Thermal Sciences, 39(1), 1–17.

By: Z. Yang, T. Dinh, R. Nourgaliev & B. Sehgal

Source: ORCID
Added: July 28, 2020

1999 journal article

Experimental and analytical studies of melt jet-coolant interactions: a synthesis

Nuclear Engineering and Design, 189(1), 299–327.

By: T. Dinh, V. Bui, R. Nourgaliev, J. Green & B. Sehgal

Source: ORCID
Added: July 28, 2020

1999 journal article

Investigation of film boiling thermal hydraulics under FCI conditions: results of analyses and a numerical study

Nuclear Engineering and Design, 189(1), 251–272.

By: T. Dinh, A. Dinh, R. Nourgaliev & B. Sehgal

Source: ORCID
Added: July 28, 2020

1999 journal article

Numerical simulation of droplet deformation and break-up by lattice-Boltzmann method

Progress in Nuclear Energy, 34(4), 471–488.

By: B. Sehgal, R. Nourgaliev & T. Dinh

Source: ORCID
Added: July 28, 2020

1997 journal article

Effect of fluid Prandtl number on heat transfer characteristics in internally heated liquid pools with Rayleigh numbers up to 1012

Nuclear Engineering and Design, 169(1-3), 165–184.

By: R. Nourgaliev, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 conference paper

Molten-metal jet impingement: insights from experiments and analysis

International Conference on Nuclear Engineering, Proceedings, ICONE, 227.

By: J. Green, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 conference paper

Numerical simulation of film boiling heat transfer: Modeling concept and model capabilities

American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD, 348, 1–10.

By: T. Dinh, A. Dinh, R. Nourgaliev & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 journal article

On heat transfer characteristics of real and simulant melt pool experiments

Nuclear Engineering and Design, 169(1-3), 151–164.

By: T. Dinh, R. Nourgaliev & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 conference paper

On mechanisms that govern the vessel melt source for ex-vessel FCIS

International Conference on Nuclear Engineering, Proceedings, ICONE, 233.

By: T. Dinh, J. Green & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 conference paper

Parametric investigation of a local-homogeneous-slip model of film boiling on horizontal cylinders

International Conference on Nuclear Engineering, Proceedings, ICONE, 232.

By: R. Nourgaliev, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 journal article

Simulation and analysis of transient cooldown natural convection experiments

Nuclear Engineering and Design, 178(1), 13–27.

By: R. Nourgaliev, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 conference paper

Simulation of multiphase mixing by a particle transport model

International Conference on Nuclear Engineering, Proceedings, ICONE, 231.

By: R. Nourgaliev, T. Dinh & B. Sehgal

Source: ORCID
Added: July 28, 2020

1997 journal article

The investigation of turbulence characteristics in an internally-heated unstably-stratified fluid layer

Nuclear Engineering and Design, 178(3), 235–258.

By: R. Nourgaliev & T. Dinh

Source: ORCID
Added: July 28, 2020

1997 journal article

Turbulence modelling for large volumetrically heated liquid pools

Nuclear Engineering and Design, 169(1-3), 131–150.

By: T. Dinh & R. Nourgaliev

Source: ORCID
Added: July 28, 2020

1996 journal article

Analysis of major accidents at atomic power stations

Heat Transfer Research, 27(1), 201–209.

By: B. Nigmatulin & T. Dinh

Source: ORCID
Added: July 28, 2020

1996 journal article

Assessment of the thermal load when molten debris interact with a VVER reactor vessel during a severe accident

Thermal Engineering, 43(3), 189–197.

By: T. Dinh, B. Nigmatulin, R. Nurgaliev & N. Rassokhin

Source: ORCID
Added: July 28, 2020

1996 journal article

Modelling of heat and mass transfer processes during core melt discharge from a reactor pressure vessel

Nuclear Engineering and Design, 163(1-2), 191–206.

By: T. Dinh, V. Bui, R. Nourgaliev, T. Okkonen & B. Sehgal

Source: ORCID
Added: July 28, 2020

1993 conference paper

Molten corium - reactor vessel interaction: Scaling and other aspects

American Society of Mechanical Engineers (Paper), 1–9.

By: T. Dinh & A. Popov

Source: ORCID
Added: July 28, 2020

1991 conference paper

Mathematical and experimental modeling of the thermal-hydraulics for PWR reactivity initiated accident simulation

American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD, 165, 69–74.

By: V. Zemlianoukhin, T. Dinh, L. Egorova, A. Ustinov, R. Khasanov, V. Buchilin, O. Nechaieva

Source: ORCID
Added: July 28, 2020

Employment

2013 - present

North Carolina State University Raleigh, NC, US
Professor Nuclear Engineering

Education

1991 - 1993

Moscow Power Engineering Institute Moscow, RU
Doctor of Science Nuclear Engineering

1988 - 1991

Moscow Power Engineering Institute Moscow, RU
Doctor of Philosophy Nuclear Engineering

1982 - 1988

Moscow Power Engineering Institute Moscow, RU
Master of Science Nuclear Engineering