Nam Dinh

Wang, L., Lin, L., & Dinh, N. (2023). Data coverage assessment on neural network based digital twins for autonomous control system. ANNALS OF NUCLEAR ENERGY, 182. https://doi.org/10.1016/j.anucene.2022.109568

Iskhakov, A. S., Leite, V. C., Merzari, E., & Dinh, N. T. (2023, April 28). Data-Driven High-to-Low for Coarse Grid System Thermal Hydraulics. NUCLEAR SCIENCE AND ENGINEERING, Vol. 4. https://doi.org/10.1080/00295639.2023.2180987

Iskhakov, A. S., Tai, C.-K., Bolotnov, I. A., Nguyen, T., Merzari, E., Shaver, D. R., & Dinh, N. T. (2023, March 16). Data-Driven RANS Turbulence Closures for Forced Convection Flow in Reactor Downcomer Geometry. NUCLEAR TECHNOLOGY, Vol. 3. https://doi.org/10.1080/00295450.2023.2185056

Tai, C.-K., Nguyen, T., Iskhakov, A. S., Merzari, E., Dinh, N. T., & Bolotnov, I. A. (2023, June 17). Direct Numerical Simulation of Low and Unitary Prandtl Number Fluids in Reactor Downcomer Geometry. NUCLEAR TECHNOLOGY, Vol. 6. https://doi.org/10.1080/00295450.2023.2213286

Iskhakova, A., Kondo, Y., Tanimoto, K., Dinh, N. T., & Bolotnov, I. A. (2023). Interface Capturing Flow Boiling Simulations in a Compact Heat Exchanger. ASME JOURNAL OF HEAT AND MASS TRANSFER, 145(4). https://doi.org/10.1115/1.4056688

Iskhakov, A. S., Dinh, N. T., Leite, V. C., & Merzari, E. (2023). Machine learning from RANS and LES to inform coarse grid simulations. PROGRESS IN NUCLEAR ENERGY, 163. https://doi.org/10.1016/j.pnucene.2023.104809

Liu, Y., Dinh, N., Sun, X., & Hu, R. (2023, February 17). Uncertainty Quantification for Multiphase Computational Fluid Dynamics Closure Relations with a Physics-Informed Bayesian Approach. NUCLEAR TECHNOLOGY, Vol. 2. https://doi.org/10.1080/00295450.2022.2162792

Iskhakov, A. S., Tai, C.-K., Bolotnov, I. A., & Dinh, N. T. (2022, September 10). A Perspective on Data-Driven Coarse Grid Modeling for System Level Thermal Hydraulics. NUCLEAR SCIENCE AND ENGINEERING, Vol. 9. https://doi.org/10.1080/00295639.2022.2107864

Zhu, Y., Dinh, N. T., Saini, N., & Bolotnov, I. A. (2022). 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. https://doi.org/10.1016/j.nucengdes.2022.111814

Gurgen, A., & Dinh, N. T. (2022). Development and assessment of a reactor system prognosis model with physics-guided machine learning. NUCLEAR ENGINEERING AND DESIGN, 398. https://doi.org/10.1016/j.nucengdes.2022.111976

Lin, L., Gurgen, A., & Dinh, N. (2022). Development and assessment of prognosis digital twin in a NAMAC system. ANNALS OF NUCLEAR ENERGY, 179. https://doi.org/10.1016/j.anucene.2022.109439

Lin, L., Athe, P., Rouxelin, P., Avramova, M., Gupta, A., Youngblood, R., … Dinh, N. (2022). 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. https://doi.org/10.1016/j.anucene.2021.108715

Hanna, B., Son, T. C., & Dinh, N. (2021). AI-Guided Reasoning-Based Operator Support System for the Nuclear Power Plant Management. ANNALS OF NUCLEAR ENERGY, 154. https://doi.org/10.1016/j.anucene.2020.108079

Bao, H., Feng, J., Dinh, N., & Zhang, H. (2021). Deep learning interfacial momentum closures in coarse-mesh CFD two-phase flow simulation using validation data. INTERNATIONAL JOURNAL OF MULTIPHASE FLOW, 135. https://doi.org/10.1016/j.ijmultiphaseflow.2020.103489

Lin, L., Athe, P., Rouxelin, P., Avramova, M., Gupta, A., Youngblood, R., … Dinh, N. (2021). Development and assessment of a nearly autonomous management and control system for advanced reactors. Annals of Nuclear Energy, 150. https://doi.org/10.1016/j.anucene.2020.107861

Dinh, N. (2021). Development of a Nearly Autonomous Management and Control (NAMAC) System for Advanced Reactors (Final Report for ARPA-E Project). https://doi.org/10.2172/1866087

Lee, J., Lin, L., Athe, P., & Dinh, N. (2021). Development of the Machine Learning-based Safety Significant Factor Inference Model for Diagnosis in Autonomous Control System. ANNALS OF NUCLEAR ENERGY, 162. https://doi.org/10.1016/j.anucene.2021.108443

Lin, L., Lee, J., Poudel, B., McJunkin, T., Dinh, N., & Agarwal, V. (2021). Enhancing the Operational Resilience of Advanced Reactors with Digital Twins by Recurrent Neural Networks. https://doi.org/10.2172/1835892

Lin, L., Lee, J., Poudel, B., McJunkin, T., Dinh, N., & Agarwal, V. (2021). Enhancing the Operational Resilience of Advanced Reactors with Digital Twins by Recurrent Neural Networks. 2021 RESILIENCE WEEK (RWS). https://doi.org/10.1109/RWS52686.2021.9611796

Iskhakov, A. S., Dinh, N. T., & Chen, E. (2021). Integration of neural networks with numerical solution of PDEs for closure models development. PHYSICS LETTERS A, 406. https://doi.org/10.1016/j.physleta.2021.127456

Lin, L., Bao, H., & Dinh, N. (2021). [Review of Uncertainty quantification and software risk analysis for digital twins in the nearly autonomous management and control systems: A review]. ANNALS OF NUCLEAR ENERGY, 160. https://doi.org/10.1016/j.anucene.2021.108362

Liu, Y., Wang, D., Sun, X., Liu, Y., Dinh, N., & Hu, R. (2021). 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. https://doi.org/10.1016/j.ress.2021.107636

Lin, L., Montanari, N., Prescott, S., Sampath, R., Bao, H., & Dinh, N. (2020). Adequacy evaluation of smoothed particle hydrodynamics methods for simulating the external-flooding scenario. Nuclear Engineering and Design, 365. https://doi.org/10.1016/j.nucengdes.2020.110720

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). An Application of ASP in Nuclear Engineering: Explaining the Three Mile Island Nuclear Accident Scenario. THEORY AND PRACTICE OF LOGIC PROGRAMMING, Vol. 20, pp. 926–941. https://doi.org/10.1017/S1471068420000241

Bao, H., Feng, J., Dinh, N., & Zhang, H. (2020). Computationally efficient CFD prediction of bubbly flow using physics-guided deep learning. International Journal of Multiphase Flow, 131. https://doi.org/10.1016/j.ijmultiphaseflow.2020.103378

Bodda, S. S., Gupta, A., & Dinh, N. (2020). Enhancement of risk informed validation framework for external hazard scenario. Reliability Engineering and System Safety, 204. https://doi.org/10.1016/j.ress.2020.107140

Hanna, B. N., Dinh, N. T., Youngblood, R. W., & Bolotnov, I. A. (2020). Machine-learning based error prediction approach for coarse-grid Computational Fluid Dynamics (CG-CFD). PROGRESS IN NUCLEAR ENERGY, 118. https://doi.org/10.1016/j.pnucene.2019.103140

Bao, H., Feng, J., Zhang, H., & Dinh, N. (2020). Probing interfacial momentum closures in two-phase bubbly flow with machine learning-aided methods. Transactions of the American Nuclear Society, 122, 844–847. https://doi.org/10.13182/T122-32371

Chang, C.-W., Fang, J., & Dinh, N. T. (2020). Reynolds-Averaged Turbulence Modeling Using Deep Learning with Local Flow Features: An Empirical Approach. NUCLEAR SCIENCE AND ENGINEERING, 194(8-9), 650–664. https://doi.org/10.1080/00295639.2020.1712928

Bodda, S. S., Gupta, A., & Dinh, N. (2020). Risk informed validation framework for external flooding scenario. NUCLEAR ENGINEERING AND DESIGN, 356. https://doi.org/10.1016/j.nucengdes.2019.110377

Bao, H., Dinh, N., Lin, L., Youngblood, R., Lane, J., & Zhang, H. (2020). Using deep learning to explore local physical similarity for global-scale bridging in thermal-hydraulic simulation. Annals of Nuclear Energy, 147. https://doi.org/10.1016/j.anucene.2020.107684

Bao, H., Youngblood, R., Zhang, H., Dinh, N., Lin, L., & Lane, J. (2019). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85073761938&partnerID=MN8TOARS

Bao, H., Dinh, N. T., Lane, J. W., & Youngblood, R. W. (2019). A data-driven framework for error estimation and mesh-model optimization in system-level thermal-hydraulic simulation. NUCLEAR ENGINEERING AND DESIGN, 349, 27–45. https://doi.org/10.1016/j.nucengdes.2019.04.023

Athe, P., & Dinh, N. (2019). A framework for assessment of predictive capability maturity and its application in nuclear thermal hydraulics. NUCLEAR ENGINEERING AND DESIGN, 354. https://doi.org/10.1016/j.nucengdes.2019.110201

Hanna, B., Son, T. C., & Dinh, N. (2019). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85073712176&partnerID=MN8TOARS

Lin, L., Dinh, N., Prescott, S., Bao, H., Montanari, N., & Sampath, R. (2019). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85073736251&partnerID=MN8TOARS

Chang, C.-W., & Dinh, N. T. (2019). Classification of machine learning frameworks for data-driven thermal fluid models. INTERNATIONAL JOURNAL OF THERMAL SCIENCES, 135, 559–579. https://doi.org/10.1016/j.ijthermalsci.2018.09.002

Bao, H., Feng, J., Zhang, H., & Dinh, N. (2019). 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. https://doi.org/10.13182/31051

Zhu, Y., Dinh, N., Hu, R., & Kraus, A. (2019). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85073734574&partnerID=MN8TOARS

Chang, C.-W., Fang, J., & Dinh, N. T. (2019). Reynolds-averaged turbulence modeling using deep learning with local flow features. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, 1698–1711. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85073713566&partnerID=MN8TOARS

Aksan, N., Andreani, M., Bechta, S., Corradini, M., D’Auria, F., Dhir, V., … Zhang, J. (2019). The life and the contribution of B. R. Sehgal, G. Yadigaroglu and G. Hewitt: Remembrance statements. Nuclear Engineering and Design, 354. https://doi.org/10.1016/j.nucengdes.2019.110252

Liu, Y., Sun, X., Liu, Y., & Dinh, N. (2019). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85073755203&partnerID=MN8TOARS

Liu, Y., Dinh, N. T., Smith, R. C., & Sun, X. (2019). 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. https://doi.org/10.1016/j.ijheatmasstransfer.2019.04.075

Liu, Y., Sun, X., & Dinh, N. T. (2019). Validation and uncertainty quantification of multiphase-CFD solvers: A data-driven Bayesian framework supported by high-resolution experiments. NUCLEAR ENGINEERING AND DESIGN, 354. https://doi.org/10.1016/j.nucengdes.2019.110200

Hanna, B. N., Dinh, N., & Bolotnov, I. A. (2018). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85050164371&partnerID=MN8TOARS

Liu, Y., Dinh, N., Sato, Y., & Niceno, B. (2018). Data-driven modeling for boiling heat transfer: Using deep neural networks and high-fidelity simulation results. APPLIED THERMAL ENGINEERING, 144, 305–320. https://doi.org/10.1016/j.applthermaleng.2018.08.041

Zhang, X., Liu, Y., Sun, X., & Dinh, N. (2018). Design of validation experiments for model improvement of dispersed flow film boiling in COBRA-TF. Transactions of the American Nuclear Society, 119, 133–136. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85060849109&partnerID=MN8TOARS

Lei, X., Zhang, W., Zhang, J., Dinh, N., & Li, H. (2018). 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. https://doi.org/10.1016/j.ijheatmasstransfer.2018.04.043

Liu, Y., & Dinh, N. (2018). Flow boiling in tubes. In Handbook of Thermal Science and Engineering (pp. 1907–1949). https://doi.org/10.1007/978-3-319-26695-4_47

Liu, Y., Shi, S., Qian, Y., Sun, X., & Dinh, N. (2018). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85060164897&partnerID=MN8TOARS

Lin, L., & Dinh, N. (2018). Predictive capability and maturity assessment with Bayesian network. Transactions of the American Nuclear Society, 118, 1087–1090. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85063015132&partnerID=MN8TOARS

Kwag, S., Gupta, A., & Dinh, N. (2018). Probabilistic risk assessment based model validation method using Bayesian network. RELIABILITY ENGINEERING & SYSTEM SAFETY, 169, 380–393. https://doi.org/10.1016/j.ress.2017.09.013

Bao, H., Zhao, H., Zhang, H., Zou, L., Sharpe, P., & Dinh, N. (2018). Safe reactor depressurization windows for BWR Mark I Station Blackout accident management strategy. ANNALS OF NUCLEAR ENERGY, 114, 518–529. https://doi.org/10.1016/j.anucene.2017.12.063

Bao, H., Dinh, N., Lane, J., & Youngblood, R. (2018). Study of data-driven mesh-model optimization in system thermal-hydraulic simulation. Transactions of the American Nuclear Society, 118, 1091–1094. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85062961048&partnerID=MN8TOARS

Liu, Y., & Dinh, N. (2018). Validation and Uncertainty Quantification for Wall Boiling Closure Relations in Multiphase-CFD Solver. Nuclear Science and Engineering, 193(1-2), 81–99. https://doi.org/10.1080/00295639.2018.1512790

Zhu, Y., & Dinh, N. (2017). A data-driven approach for turbulence modeling. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017, 2017-September. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85052541047&partnerID=MN8TOARS

Lei, X., Li, H., Dinh, N., & Zhang, W. (2017). A study of heat transfer scaling of supercritical pressure water in horizontal tubes. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 114, 923–933. https://doi.org/10.1016/j.ijheatmasstransfer.2017.06.052

Lin, L., Dinh, N., Montanari, N., Sampath, R., Akinci, N., & Prescott, S. (2017). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85047791478&partnerID=MN8TOARS

Liu, Y., & Dinh, N. (2017). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85052384281&partnerID=MN8TOARS

Lei, X., Li, H., Zhang, W., Dinh, N. T., Guo, Y., & Yu, S. (2017). Experimental study on the difference of heat transfer characteristics between vertical and horizontal flows of supercritical pressure water. APPLIED THERMAL ENGINEERING, 113, 609–620. https://doi.org/10.1016/j.applthermaleng.2016.11.051

Hess, S. M., Prescott, S., Smith, C., Lin, L., Dinh, N., Sampath, R., & Montanari, N. (2017). Integrated use of modeling and simulation in high winds PRA. International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017, 1, 30–39. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85047784184&partnerID=MN8TOARS

Chang, C.-W., Dinh, N., & Cetiner, S. M. (2017). Physics-constrained machine learning for two-phase flow simulation using deep learning-based closure relation. Transactions of the American Nuclear Society, 117, 1749–1752. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85054585553&partnerID=MN8TOARS

Liu, Y., Rollins, C., Dinh, N., & Luo, H. (2017). 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. https://doi.org/10.1115/ht2017-4963

Lin, L. Y., Dinh, N. T., Sampath, R., & Akinci, N. (2016). 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. https://doi.org/10.1115/HT2016-7382

Bao, H., Dinh, N., Omotowa, O., Zhao, H., Zhang, H., Zou, L., & Szilard, R. H. (2016). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84986182404&partnerID=MN8TOARS

Chang, C.-W., & Dinh, N. (2016). A study of physics-informed deep learning for system fluid dynamics closures. Transactions of the American Nuclear Society, 115, 1785–1788. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85033222005&partnerID=MN8TOARS

Liu, Y., & Dinh, N. (2016). Analysis of heat transfer under high heat flux nucleate boiling conditions. Kerntechnik, 81(3), 308–314. https://doi.org/10.3139/124.110750

Lin, L., & Dinh, N. (2016). Assessment of a smoothed particle hydrodynamics method for thin film on textured surfaces. Transactions of the American Nuclear Society, 115, 1453–1456. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85033230091&partnerID=MN8TOARS

Lee, J., Dinh, N., & Son, T. C. (2016). Development of a severe accident analysis engine using approximate reasoning. Transactions of the American Nuclear Society, 115, 830–833. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85032884451&partnerID=MN8TOARS

Corradini, M., Dinh, N. T., & Leon, S. B. Y. (2016). Foreword special issue on the 16th international topical meeting on nuclear reactor thermal hydraulics. Nuclear Science and Engineering, 184(3), III-.

Hanna, B. N., Dinh, N. T., & Bolotnov, I. A. (2016). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84992089403&partnerID=MN8TOARS

Athe, P., Dinh, N., & Abdel-Khalik, H. (2016). Investigation of similarity metrics for simulation based scaling analysis. International Topical Meeting on Advances in Thermal Hydraulics 2016, ATH 2016, 409–425. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84992126794&partnerID=MN8TOARS

Dinh, N., No, H. C., Sun, X., Leon, S. B. Y., Merzari, E., & Pointer, W. D. (2015). Foreword. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 1. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84962754306&partnerID=MN8TOARS

Bao, H., Zhao, H., Zhang, H., Zou, L., Szilard, R. H., & Dinh, N. (2015). Simulation of BWR Mark i station black-out accident using GOTHIc: An initial demonstration. Transactions of the American Nuclear Society, 113, 1377–1380. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85043354152&partnerID=MN8TOARS

Liu, Y., & Dinh, N. (2015). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84962715457&partnerID=MN8TOARS

Kudinov, P., Galushin, S., Yakush, S., Villanueva, W., Phung, V.-A., Grishchenko, D., & Dinh, N. (2014). A framework for assessment of severe accident management effectiveness in Nordic BWR plants. PSAM 2014 - Probabilistic Safety Assessment and Management. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-85066711344&partnerID=MN8TOARS

Chang, C.-W., & Dinh, N. (2014). A scoping study of direct containment heating in a small modular reactor. Transactions of the American Nuclear Society, 111, 907–910. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84939132697&partnerID=MN8TOARS

Bui, A., Williams, B., & Dinh, N. (2014). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84907072042&partnerID=MN8TOARS

Hanna, B., Dinh, N., & Bolotnov, I. (2014). Development of 3D containment simulation capability: High pressure steam slowdown scenario. Transactions of the American Nuclear Society, 111, 1545–1548. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84939153178&partnerID=MN8TOARS

Dinh, N., Ren, W., & Lee, H. (2014). Validation data: Managing the weak link. Transactions of the American Nuclear Society, 111, 1444–1445. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84939158259&partnerID=MN8TOARS

Hansson, R. C., Dinh, T. N., & Manickam, L. T. (2013). A study of the effect of binary oxide materials in a single droplet vapor explosion. Nuclear Engineering and Design, 264, 168–175. https://doi.org/10.1016/j.nucengdes.2013.02.017

Dinh, T.-N. (2013). Guest editorial special issue on “Nuclear reactor safety simulation and uncertainty analysis.” Annals of Nuclear Energy, 52, 1. https://doi.org/10.1016/j.anucene.2012.11.013

Dinh, T.-N., & Tu, J. P. (2013). Observations of bubble nucleation and interaction dynamics in high heat flux boiling. Transactions of the American Nuclear Society, 109(PART 2), 1819–1820. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84902837363&partnerID=MN8TOARS

Bui, A. V., Dinh, N. T., Nourgaliev, R. R., & Williams, B. J. (2013). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84883314135&partnerID=MN8TOARS

Gong, S., Ma, W., & Dinh, T.-N. (2012). Simulation and validation of the dynamics of liquid films evaporating on horizontal heater surfaces. Applied Thermal Engineering, 48, 486–494. https://doi.org/10.1016/j.applthermaleng.2012.05.021

Dinh, T.-N., Nourgaliev, R. R., & Youngblood, R. W. (2011). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84875674404&partnerID=MN8TOARS

Gong, S., Ma, W., & Dinh, T.-N. (2011). 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. https://doi.org/10.1016/j.ijheatmasstransfer.2010.11.036

Youngblood, R. W., Nourgaliev, R. R., Kelly, D. L., Smith, C. L., & Dinh, T.-N. (2011). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84875658203&partnerID=MN8TOARS

Youngblood, R. W., Nourgaliev, R. R., Kelly, D. L., Smith, C. L., & Dinh, T.-N. (2011). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-80051988899&partnerID=MN8TOARS

Nourgaliev, R. R., Dinh, T.-N., & Nelson, R. A. (2011). Lessons learned from an initial VU-assessed code development effort. Transactions of the American Nuclear Society, 104, 358–360. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84875659394&partnerID=MN8TOARS

Bui, A., Nourgaliev, R. R., & Dinh, T.-N. (2011). On physics modeling and components development in R7. Transactions of the American Nuclear Society, 104, 523–525. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84875679207&partnerID=MN8TOARS

Luo, H., Luo, L., Nourgaliev, R., Mousseau, V. A., & Dinh, N. (2010). A reconstructed discontinuous Galerkin method for the compressible Navier–Stokes equations on arbitrary grids. Journal of Computational Physics, 229(19), 6961–6978. https://doi.org/10.1016/j.jcp.2010.05.033

Tran, C. T., Kudinov, P., & Dinh, T. N. (2010). 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. https://doi.org/10.1016/j.nucengdes.2009.11.029

Gong, S., Ma, W., & Dinh, T.-N. (2010). Diagnostic techniques for the dynamics of a thin liquid film under forced flow and evaporating conditions. Microfluidics and Nanofluidics, 9(6), 1077–1089. https://doi.org/10.1007/s10404-010-0626-z

Kudinov, P., Karbojian, A., Weimin, M., & Dinh, T.-N. (2010). The defor-s experimental study of debris formation with corium simulant materials. Nuclear Technology, 170(1), 219–230. https://doi.org/10.13182/NT10-A9460

Ma, W., & Dinh, T.-N. (2010). The effects of debris bed's prototypical characteristics on corium coolability in a LWR severe accident. Nuclear Engineering and Design, 240(3), 598–608. https://doi.org/10.1016/j.nucengdes.2009.10.026

Karbojian, A., Ma, W. M., Kudinov, P., & Dinh, T. N. (2009). A scoping study of debris bed formation in the DEFOR test facility. Nuclear Engineering and Design, 239(9), 1653–1659. https://doi.org/10.1016/j.nucengdes.2009.03.002

Hansson, R. C., Park, H. S., & Dinh, T.-N. (2009). Dynamics and preconditioning in a single-droplet vapor explosion. Nuclear Technology, 167(1), 223–234. https://doi.org/10.13182/NT09-A8864

Hess, S. M., Dinh, N., Gaertner, J. P., & Szilard, R. (2009). Risk-informed safety margin characterization. International Conference on Nuclear Engineering, Proceedings, ICONE, 1, 11–17. https://doi.org/10.1115/ICONE17-75064

Tran, C.-T., & Dinh, T.-N. (2009). 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. https://doi.org/10.5516/NET.2009.41.7.929

Hansson, R. C., Park, H. S., & Dinh, T.-N. (2009). 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. https://doi.org/10.1016/j.expthermflusci.2009.01.011

Tran, C.-T., & Dinh, T.-N. (2009). 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. https://doi.org/10.1016/j.pnucene.2009.06.007

Tran, C.-T., & Dinh, T.-N. (2009). 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. https://doi.org/10.1016/j.pnucene.2009.06.001

Ma, W., Karbojian, A., Sehgal, B. R., & Dinh, T.-N. (2009). Thermal-hydraulic performance of heavy liquid metal in straight-tube and U-tube heat exchangers. Nuclear Engineering and Design, 239(7), 1323–1330. https://doi.org/10.1016/j.nucengdes.2009.03.014

Kudinov, P., & Dinh, T. N. (2008). A computational study of debris bed formation. Transactions of the American Nuclear Society, 98, 341–342. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-55249101472&partnerID=MN8TOARS

Kudinov, P., Karbojian, A., Ma, W., Davydov, M., & Dinh, T.-N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-52249116051&partnerID=MN8TOARS

Roshan, S. S., Ma, W., Kozlowski, T., & Dinh, T.-N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-52249089150&partnerID=MN8TOARS

Tran, C.-T., & Dinh, T.-N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-52249091307&partnerID=MN8TOARS

Kudinov, P., Karbojian, A., Ma, W., & Dinh, T.-N. (2008). An experimental study on debris formation with corium simulant materials. International Conference on Advances in Nuclear Power Plants, ICAPP 2008, 2, 1191–1199. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-70349971077&partnerID=MN8TOARS

Tran, C. T., & Dinh, T. N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-55249125206&partnerID=MN8TOARS

Kubarev, A., Kozlowski, T., Roshan, S. S., & Dinh, T.-N. (2008). Design of BWR instability suppression system. International Conference on the Physics of Reactors 2008, PHYSOR 08, 3, 2062–2068. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-79953854518&partnerID=MN8TOARS

Hansson, R. C., & Dinh, T.-N. (2008). Effect of non-condensable gases on triggering and energetics of a single drop vapor explosion. Transactions of the American Nuclear Society, 98, 547–548. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-55249084649&partnerID=MN8TOARS

Journeau, C., Bonnet, J. M., Godin-Jacqmin, L., Piluso, P., Tarabelli, D., Dufour, E., … Sevon, T. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-70349974746&partnerID=MN8TOARS

Theofanous, T. G., & Dinh, T.-N. (2008). Integration of multiphase science and technology with risk management in nuclear power reactors. Multiphase Science and Technology, 20(2), 81–211. https://doi.org/10.1615/MultScienTechn.v20.i2.10

Yakush, S., Kudinov, P., & Dinh, T.-N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-70349970186&partnerID=MN8TOARS

Dinh, T.-N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-52249098812&partnerID=MN8TOARS

Dinh, T.-N., Hansson, R. C., & Kudinov, P. (2008). On solidification mechanism that governs the effect of binary melt composition on steam explosion energetics. Transactions of the American Nuclear Society, 98, 615–616. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-55249084402&partnerID=MN8TOARS

Cadinu, F., Kozlowski, T., & Dinh, T.-N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-52249115142&partnerID=MN8TOARS

Kozlowski, T., Peltonen, J., & Dinh, T.-N. (2008). Spatial coupling for BWR stability analysis. Transactions of the American Nuclear Society, 98, 603–605. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-55249127520&partnerID=MN8TOARS

Peltonen, J., Kozlowski, T., & Dinh, T.-N. (2008). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-79953889385&partnerID=MN8TOARS

Dombrovsky, L. A., & Dinh, T.-N. (2008). The effect of thermal radiation on the solidification dynamics of metal oxide melt droplets. Nuclear Engineering and Design, 238(6), 1421–1429. https://doi.org/10.1016/j.nucengdes.2007.10.010

Weimin, M., & Dinh, T.-N. (2007). A study on effects of debris bed prototypicality on coolability. Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-44349091618&partnerID=MN8TOARS

Theofanous, T. G., Li, G. J., Dinh, T. N., & Chang, C. H. (2007). Aerobreakup in disturbed subsonic and supersonic flow fields. Journal of Fluid Mechanics, 593, 131–170. https://doi.org/10.1017/S0022112007008853

Kudinov, P., & Dinh, N. (2007). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-44349098203&partnerID=MN8TOARS

Hansson, R. C., Park, H. S., & Dinh, T. N. (2007). Dynamics and preconditioning in a single drop vapor explosion. Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-44349165747&partnerID=MN8TOARS

Kozlowski, T., Roshan, S., & Dinh, T.-N. (2007). Evaluation of coupled codes RELAP5/PARCS capability for BWR global stability prediction. Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-44349116232&partnerID=MN8TOARS

Dinh, T.-N. (2007). Material property effect in steam explosion energetics: Revisited. Proceedings - 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-42249093642&partnerID=MN8TOARS

Suchoszek, J., Cadinu, F., Kozlowski, T., & Dinh, T.-N. (2007). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-44349127315&partnerID=MN8TOARS

Tran, C.-T., & Dinh, T.-N. (2007). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-44449162101&partnerID=MN8TOARS

Weimin, M., Karbojian, A., Sehgal, B. R., & Dinh, T.-N. (2007). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-44349134568&partnerID=MN8TOARS

Nourgaliev, R., Dinh, N., & Theofanous, T. (2006). 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). https://doi.org/10.1007/1-4020-4977-3_34

Nourgaliev, R. R., Dinh, T. N., & Theofanous, T. G. (2006). Adaptive characteristics-based matching for compressible multifluid dynamics. Journal of Computational Physics, 213(2), 500–529. https://doi.org/10.1016/j.jcp.2005.08.028

Tran, C. T., & Dinh, T. N. (2006). Analysis of melt pool heat transfer in a BWR lower head. Transactions of the American Nuclear Society, 95, 629–631. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-33845527584&partnerID=MN8TOARS

Theofanous, T., Nourgaliev, R., Li, G., & Dinh, N. (2006). 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). https://doi.org/10.1007/1-4020-4977-3_35

Theofanous, T. G., & Dinh, T. N. (2006). High heat flux boiling and burnout as microphysical phenomena: Mounting evidence and opportunities. Multiphase Science and Technology, 18(3), 251–276. https://doi.org/10.1615/MultScienTechn.v18.i3.30

Dinh, N., Bürger, M., & Lohnert, G. (2006). Introduction to the Festschrift honoring the 70th Birthday of Professor Bal Raj Sehgal. Nuclear Engineering and Design, 236(19-21), 1939–1940. https://doi.org/10.1016/j.nucengdes.2006.04.029

Dinh, T. N., Nourgaliev, R. R., & Theofanous, T. G. (2006). On the numerical simulation of acceleration-driven multi-fluid mixing. Multiphase Science and Technology, 18(3), 199–230. https://doi.org/10.1615/MultScienTechn.v18.i3.10

Cadinu, F., Kozlowski, T., & Dinh, T.-N. (2006). RELAP5 performance in predicting critical power in a BWR fuel bundle. Transactions of the American Nuclear Society, 95, 650–651. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-33845532848&partnerID=MN8TOARS

Nourgaliev, R., Dinh, N., Nguyen, L., & Theofanous, T. (2006). Treatment of particle collisions in direct numerical simulations of high speed compressible flows. In Fluid Mechanics and its Applications (Vol. 81, pp. 247–259). Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84859934549&partnerID=MN8TOARS

Nourgaliev, R. R., Wiri, S., Dinh, T. N., & Theofanous, T. G. (2005). Adaptive strategies for mass conservation in level set treatment. 17th AIAA Computational Fluid Dynamics Conference. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84884964371&partnerID=MN8TOARS

Li, G. J., Dinh, T. N., Yang, Y. Z., & Theofanous, T. G. (2005). Investigation of breakup of isolated and multiple drops in subsonic flow. 43rd AIAA Aerospace Sciences Meeting and Exhibit - Meeting Papers, 4995–5005. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-30744460145&partnerID=MN8TOARS

Nourgaliev, R. R., Suschikh, S. Y., Dinh, T. N., & Theofanous, T. G. (2005). Numerical investigation of shock wave refraction patterns at multimaterial interfaces. 43rd AIAA Aerospace Sciences Meeting and Exhibit - Meeting Papers, 10905–10921. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-30744447245&partnerID=MN8TOARS

Nourgaliev, R. R., Wiri, S., Dinh, N. T., & Theofanous, T. G. (2005). On improving mass conservation of level set by reducing spatial discretization errors. International Journal of Multiphase Flow, 31(12), 1329–1336. https://doi.org/10.1016/j.ijmultiphaseflow.2005.08.003

Nourgaliev, R. R., Dinh, T. N., & Theofanous, T. G. (2005). Sharp treatment of surface tension and viscous stresses in multifluid dynamics. 17th AIAA Computational Fluid Dynamics Conference. https://doi.org/10.2514/6.2005-5349

Nourgaliev, R. R., Sushchikh, S. Y., Dinh, T. N., & Theofanous, T. G. (2005). Shock wave refraction patterns at interfaces. International Journal of Multiphase Flow, 31(9), 969–995. https://doi.org/10.1016/j.ijmultiphaseflow.2005.04.001

Sushchikh, S. Y., Dinh, T. N., & Theofanous, T. G. (2004). A numerical study of the shape effect on drag in supersonic low reynolds number (rarefied) flows. AIAA Paper, 6566–6575. https://doi.org/10.2514/6.2004-1063

Nourgaliev, R. R., Dinh, T. N., & Theofanous, T. G. (2004). A pseudocompressibility method for the numerical simulation of incompressible multifluid flows. International Journal of Multiphase Flow, 30(7-8 SPEC. ISS.), 901–937. https://doi.org/10.1016/j.ijmultiphaseflow.2004.03.010

Theofanous, T. G., Li, G. J., & Dinh, T. N. (2004). Aerobreakup in rarefied supersonic gas flows. Journal of Fluids Engineering, Transactions of the ASME, 126(4), 516–527. https://doi.org/10.1115/1.1777234

Li, G. J., Dinh, T. N., & Theofanous, T. G. (2004). An experimental study of droplet breakup in supersonic flow: The effect of long-range interactions. AIAA Paper, 12063–12073. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-2942741075&partnerID=MN8TOARS

Dinh, T. N., Tu, J. P., & Theofanous, T. G. (2004). Burnout in high heat flux boiling: The hydrodynaraic and physico-chemical factors. AIAA Paper, 1865–1872. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-2942709672&partnerID=MN8TOARS

Dinh, T. N., Tu, J. P., Yang, Y. Z., Nourgaliev, R. R., & Theofanous, T. G. (2004). Characterization and predictability of transient heat transfer in an unstably stratified fluid layer during power startup. 37th AIAA Thermophysics Conference. https://doi.org/10.2514/6.2004-2733

Nourgaliev, R. R., Dinh, T. N., Theofanous, T. G., Koning, J. M., Greenman, R. M., & Nakafuji, G. T. (2004). Direct numerical simulation of disperse multiphase high-speed flows. AIAA Paper, 10365–10375. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-2942741149&partnerID=MN8TOARS

Li, G. J., Nourgaliev, R. R., Dinh, T. N., & Theofanous, T. G. (2004). Particle-to-particle long range interaction and drag in supersonic flows. AIAA Paper, 6604–6614. https://doi.org/10.2514/6.2004-1064

Dinh, T. N., Yang, Y. Z., Tu, J. P., Nourgaliev, R. R., & Theofanous, T. G. (2004). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-14844334669&partnerID=MN8TOARS

Nourgaliev, R. R., Dinh, T. N., & Theofanous, T. G. (2004). 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. https://doi.org/10.1115/1.1778713

Dinh, T. N., Tu, J. P., & Theofanous, T. G. (2004). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-14844322005&partnerID=MN8TOARS

Nourgaliev, R., Dinh, N., & Theofanous, T. (2003). 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. https://doi.org/10.1115/fedsm2003-45551

Theofanous, T. G., Li, G. J., & Dinh, T. N. (2003). Aerobreakup in rarefied supersonic gas flows. Proceedings of the ASME/JSME Joint Fluids Engineering Conference, 2 B, 1685–1703. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-0347534125&partnerID=MN8TOARS

Dinh, T. N., Li, G. J., & Theofanous, T. G. (2003). An investigation of droplet breakup in a high mach, low Weber number regime. 41st Aerospace Sciences Meeting and Exhibit. https://doi.org/10.2514/6.2003-317

Sehgal, B. R., Theerthan, A., Giri, A., Karbojian, A., Willschütz, H. G., Kymäläinen, O., … Dinh, T. N. (2003). Assessment of reactor vessel integrity (ARVI). Nuclear Engineering and Design, 221(1-3 SPEC.), 23–53. https://doi.org/10.1016/S0029-5493(02)00343-6

Dinh, T. N., & Theofanous, T. G. (2003). Nucleation phenomena in boiling. Multiphase Science and Technology, 15(1-4), 349–363. https://doi.org/10.1615/MultScienTechn.v15.i1-4.290

Dinh, T. N., Tu, J. P., Dinh, A. T., & Theofanous, T. G. (2003). Nucleation phenomena in boiling on nanoscopically smooth surfaces. 41st Aerospace Sciences Meeting and Exhibit. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84894731207&partnerID=MN8TOARS

Dinh, T. N., Nourgaliev, R. R., & Theofanous, T. G. (2003). On the multiscale treatment of multifluid flow. Multiphase Science and Technology, 15(1-4), 275–288. https://doi.org/10.1615/MultScienTechn.v15.i1-4.210

Nourgaliev, R., Dinh, N., & Theofanous, T. (2003). 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. https://doi.org/10.1115/fedsm2003-45550

Nourgaliev, R. R., Dinh, T. N., Sushchikh, S. Y., Yuen, W. W., & Theofanous, T. G. (2003). The characteristics-based matching method for compressible flow in complex geometries. 41st Aerospace Sciences Meeting and Exhibit. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-84894768523&partnerID=MN8TOARS

Nourgaliev, R. R., Dinh, T. N., Theofanous, T. G., & Joseph, D. (2003). The lattice Boltzmann equation method: Theoretical interpretation, numerics and implications. International Journal of Multiphase Flow, 29(1), 117–169. https://doi.org/10.1016/S0301-9322(02)00108-8

Nourgaliev, R. R., Dinh, T. N., Dinh, A. T., Haraldsson, H. O., & Sehgal, B. R. (2003). The multiphase Eulerian-Lagrangian transport (MELT-3D) approach for modeling of multiphase mixing in fragmentation processes. Progress in Nuclear Energy, 42(2), 123–157. https://doi.org/10.1016/S0149-1970(03)80006-9

Sehgal, B. R., Nourgaliev, R. R., & Dinh, T. N. (2002). Characterization of heat transfer processes in a melt pool convection and vessel-creep experiment. Nuclear Engineering and Design, 211(2-3), 173–187. https://doi.org/10.1016/S0029-5493(01)00434-4

Nourgaliev, R. R., Dinh, T. N., & Sehgal, B. R. (2002). On lattice Boltzmann modeling of phase transition in an isothermal non-ideal fluid. Nuclear Engineering and Design, 211(2-3), 153–171. https://doi.org/10.1016/S0029-5493(01)00435-6

Theofanous, T. G., Tu, J. P., Dinh, A. T., & Dinh, T. N. (2002). The boiling crisis phenomenon part I: Nucleation and nucleate boiling heat transfer. Experimental Thermal and Fluid Science, 26(6-7), 775–792. https://doi.org/10.1016/S0894-1777(02)00192-9

Theofanous, T. G., Dinh, T. N., Tu, J. P., & Dinh, A. T. (2002). The boiling crisis phenomenon part II: Dryout dynamics and burnout. Experimental Thermal and Fluid Science, 26(6-7), 793–810. https://doi.org/10.1016/S0894-1777(02)00193-0

Haraldsson, H., Li, H. X., Yang, Z. L., Dinh, T. N., & Sehgal, B. R. (2001). Effect of solidification on drop fragmentation in liquid-liquid media. Heat and Mass Transfer/Waerme- Und Stoffuebertragung, 37(4-5), 417–426. https://doi.org/10.1007/s002310000097

Yang, Z. L., Dinh, T. N., Nourgaliev, R. R., & Sehgal, B. R. (2001). Numerical investigation of boiling regime transition mechanism by a Lattice-Boltzmann model. Nuclear Engineering and Design, 204(1-3), 143–153. https://doi.org/10.1016/S0029-5493(00)00309-5

Yang, Z. L., Dinh, T. N., Nourgaliev, R. R., & Sehgal, B. R. (2001). Numerical investigation of bubble growth and detachment by the lattice-Boltzmann method. International Journal of Heat and Mass Transfer, 44(1), 195–206. https://doi.org/10.1016/S0017-9310(00)00101-0

Haraldsson, H., Kazachkov, I. V., Dinh, T. N., & Sehgal, B. R. (2000). Analysis of the breakup length of a thin jet penetrating a fluid pool. In Advances in Fluid Mechanics (pp. 435–444). Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-2942534137&partnerID=MN8TOARS

Dinh, T. N., Konovalikhin, M. J., & Sehgal, B. R. (2000). Core melt spreading on a reactor containment floor. Progress in Nuclear Energy, 36(4), 405–468. https://doi.org/10.1016/S0149-1970(00)00088-3

Yang, Z. L., Dinh, T. N., Nourgaliev, R. R., & Sehgal, B. R. (2000). 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. https://doi.org/10.1007/s002310000089

Yang, Z. L., Dinh, T. N., Nourgaliev, R. R., & Sehgal, B. R. (2000). Numerical investigation of bubble coalescence characteristics under nucleate boiling condition by a lattice-Boltzmann model. International Journal of Thermal Sciences, 39(1), 1–17. https://doi.org/10.1016/S1290-0729(00)00199-9

Dinh, T. N., Bui, V. A., Nourgaliev, R. R., Green, J. A., & Sehgal, B. R. (1999). Experimental and analytical studies of melt jet-coolant interactions: a synthesis. Nuclear Engineering and Design, 189(1), 299–327. https://doi.org/10.1016/S0029-5493(98)00275-1

Dinh, T. N., Dinh, A. T., Nourgaliev, R. R., & Sehgal, B. R. (1999). Investigation of film boiling thermal hydraulics under FCI conditions: results of analyses and a numerical study. Nuclear Engineering and Design, 189(1), 251–272. https://doi.org/10.1016/S0029-5493(98)00276-3

Sehgal, B. R., Nourgaliev, R. R., & Dinh, T. N. (1999). Numerical simulation of droplet deformation and break-up by lattice-Boltzmann method. Progress in Nuclear Energy, 34(4), 471–488. https://doi.org/10.1016/s0149-1970(98)00025-0

Nourgaliev, R. R., Dinh, T. N., & Sehgal, B. R. (1997). Effect of fluid Prandtl number on heat transfer characteristics in internally heated liquid pools with Rayleigh numbers up to 10<sup>12</sup>. Nuclear Engineering and Design, 169(1-3), 165–184. https://doi.org/10.1016/S0029-5493(96)01282-4

Green, J. A., Dinh, T. N., & Sehgal, B. R. (1997). Molten-metal jet impingement: insights from experiments and analysis. International Conference on Nuclear Engineering, Proceedings, ICONE, 227. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-0030689335&partnerID=MN8TOARS

Dinh, T. N., Dinh, A. T., Nourgaliev, R. R., & Sehgal, B. R. (1997). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-5344226287&partnerID=MN8TOARS

Dinh, T. N., Nourgaliev, R. R., & Sehgal, B. R. (1997). On heat transfer characteristics of real and simulant melt pool experiments. Nuclear Engineering and Design, 169(1-3), 151–164. https://doi.org/10.1016/s0029-5493(96)01283-6

Dinh, T. N., Green, J. A., & Sehgal, B. R. (1997). On mechanisms that govern the vessel melt source for ex-vessel FCIS. International Conference on Nuclear Engineering, Proceedings, ICONE, 233. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-0030716074&partnerID=MN8TOARS

Nourgaliev, R. R., Dinh, T. N., & Sehgal, B. R. (1997). Parametric investigation of a local-homogeneous-slip model of film boiling on horizontal cylinders. International Conference on Nuclear Engineering, Proceedings, ICONE, 232. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-0030655511&partnerID=MN8TOARS

Nourgaliev, R. R., Dinh, T. N., & Sehgal, B. R. (1997). Simulation and analysis of transient cooldown natural convection experiments. Nuclear Engineering and Design, 178(1), 13–27. https://doi.org/10.1016/S0029-5493(97)00177-5

Nourgaliev, R. R., Dinh, T. N., & Sehgal, B. R. (1997). Simulation of multiphase mixing by a particle transport model. International Conference on Nuclear Engineering, Proceedings, ICONE, 231. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-0030684841&partnerID=MN8TOARS

Nourgaliev, R. R., & Dinh, T. N. (1997). The investigation of turbulence characteristics in an internally-heated unstably-stratified fluid layer. Nuclear Engineering and Design, 178(3), 235–258. https://doi.org/10.1016/S0029-5493(97)00231-8

Dinh, T. N., & Nourgaliev, R. R. (1997). Turbulence modelling for large volumetrically heated liquid pools. Nuclear Engineering and Design, 169(1-3), 131–150. https://doi.org/10.1016/s0029-5493(96)01281-2

Nigmatulin, B. I., & Dinh, T. N. (1996). Analysis of major accidents at atomic power stations. Heat Transfer Research, 27(1), 201–209. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-6544282746&partnerID=MN8TOARS

Dinh, T. N., Nigmatulin, B. I., Nurgaliev, R. R., & Rassokhin, N. G. (1996). Assessment of the thermal load when molten debris interact with a VVER reactor vessel during a severe accident. Thermal Engineering, 43(3), 189–197. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-2842511313&partnerID=MN8TOARS

Dinh, T. N., Bui, V. A., Nourgaliev, R. R., Okkonen, T., & Sehgal, B. R. (1996). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-30244490610&partnerID=MN8TOARS

Dinh, T. N., & Popov, A. A. (1993). Molten corium - reactor vessel interaction: Scaling and other aspects. American Society of Mechanical Engineers (Paper), 1–9. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-0027836643&partnerID=MN8TOARS

Zemlianoukhin, V. V., Dinh, T. N., Egorova, L. A., Ustinov, A. K., Khasanov, R. K., Buchilin, V. A., & Nechaieva, O. A. (1991). 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. Retrieved from http://www.scopus.com/inward/record.url?eid=2-s2.0-0025749185&partnerID=MN8TOARS