PGS.TS. Nguyễn Văn Thái

Phó Trưởng Khoa, Khoa Vật lý kỹ thuật

Tiến sỹ (Kỹ thuật Hạt nhân, Đại học KAERI & UST, Hàn quốc, 2013)
Kỹ sư (KT Hạt nhân & VL Môi trường, trường Đại học Bách khoa Hà Nội, 2004)

Email: thai.nguyenvan@hust.edu.vn

• NE2010: Vật lý hiện đại
• NE3050: Kỹ thuật đo đạc bức xạ 1
• NE6050: An toàn lò phản ứng hạt nhân
• NE5101: Thủy nhiệt ĐH trong lò PƯHN
• NE6303: Kỹ thuật Thủy nhiệt HN
• NE4115: Nhà máy điện Hạt nhân
• NE5104: Quản lý và xử lý chất thải phóng xạ
• PH2020: Technical Writing and Presentation
• NE3036: Đầu dò bức xạ
• Động học và trao đổi nhiệt dòng hai pha (Field Research)
• Phương pháp số trị động học dòng chảy & CFD (Field Research)
• Chuyên đề Kỹ thuật Hạt nhân

• Radiation Measurements and Protection
• Experiments in Two-phase Flow and Heat Transfer
• Computational Fluid Dynamics Application for Nuclear Reactor Safety
• Modeling, Analysis and Simulation of Nuclear Reactor Transients and Accidents
• Neutronic-Thermal Hydraulics Coupling Simulation
• High Precision Measurement Techniques for Nuclear Reactor Safety

• Radiation Measurements and Protection
• Experiments in Two-phase Flow and Heat Transfer
• Computational Fluid Dynamics Application for Nuclear Reactor Safety
• Modeling, Analysis and Simulation of Nuclear Reactor Transients and Accidents
• Neutronic-Thermal Hydraulics Coupling Simulation
• High Precision Measurement Techniques for Nuclear Reactor Safety

• Bằng khen Bộ trưởng Bộ GDĐT 2019

PGS.TS. Nguyễn Văn Thái hiện là Phó Trưởng Khoa Vật lý kỹ thuật, Đại học Bách khoa Hà Nội. PGS.TS. Nguyễn Văn Thái nhận bằng Tiến sỹ chuyên ngành Kỹ thuật Hệ thống Hạt nhân Tiên tiến tại Đại học Khoa học Công nghệ Hàn Quốc (UST) và Viện nghiên cứu Năng lượng Nguyên tử Hàn Quốc (KAERI) năm 2013. Các hướng nghiên cứu của PGS.TS. Nguyễn Văn Thái bao gồm: Đo đạc và bảo vệ bức xạ; Dòng chảy hai pha và truyền nhiệt; Ứng dụng tính toán động lực học chất lỏng cho an toàn lò phản ứng hạt nhân; Mô hình hóa, phân tích và mô phỏng các quá trình và tai nạn của lò phản ứng hạt nhân; Mô phỏng kết hợp neutronic-Thủy nhiệt; Kỹ thuật đo lường chính xác cao áp dụng trong nghiên cứu an toàn lò phản ứng hạt nhân.

TẠP CHÍ

• Tran Hoai-Nam, Nguyen Van Thai, Alexander Agung, 2024. Preface for the ”OUTCOMES AND ACHIEVEMENTS FROM RESEARCHES ORIENTING THE FUTURE IN NUCLEAR FISSION TECHNOLOGY: Asia South-East (Vietnam, Thailand, Indonesia, Malaysia, Singapore, Bangladesh) and Australia”. Nuclear Engineering and Design, 428, 113500.
  https://doi.org/10.1016/j.nucengdes.2024.113500
  
• F. D’auria, …, Nguyen Van Thai, …., 2024. What is the future for nuclear fission technology? A technical opinion from the Guest Editors of VSI NFT series and the Editor of the Journal Nuclear Engineering and Design, Nuclear Engineering and Design, 425, 113332.
  https://doi.org/10.1016/j.nucengdes.2024.113332 
  
• M. Quach, M. C. Ngo, Y. Yang, T. B. Nguyen, V. T. Nguyen, Y. Fujita, T. M. D. Do, T. Nakayama, T. Suzuki, H. Suematsu, 2023. Extraction of 99Mo hot atoms made by a neutron capture method from α-MoO3 to water, Journal of Radioanalytical and Nuclear Chemistry, 332:4057–4064
  https://doi.org/10.1007/s10967-023-09125-7
• Ngoc Dat Nguyen, Van Thai Nguyen, 2022. Development of ANN structural optimization framework for data-driven prediction of local two-phase flow parameters, Progress in Nuclear Energy, 146.
  https://doi.org/10.1016/j.pnucene.2022.104176
• Ngoc Dat Nguyen, Van Thai Nguyen, 2021. Application of Artificial Neural Network for Prediction of Local Void Fraction in Vertical Subcooled Boiling Flow, Nuclear Science and Technology, 11(2), 14-22.
  https://vinatom.gov.vn/nuclear-science-and-technology-no2-2021/ 
• Manh Long Doan, Van Thai Nguyen,  Chi Thanh Tran, 2021. An analysis of In-Vessel Melt Retention strategy for VVER-1000 considering the effect of torospherical lower head vessel, Nuclear Engineering and Design, 371.
  https://www.sciencedirect.com/science/article/pii/S0029549320304660
• Manh Long Doan, Van Thai Nguyen,  Chi Thanh Tran, 2020. Analysis of in-vessel accident progression in VVER1000 NPP during SBO accident with external reactor vessel cooling method, Nuclear Science and Technology, 10(2), 1-14
• Van Thai Nguyen, Manh Long Doan, Chi Thanh Tran, 2019. Evaluation of the Potential for Containment Bypass due to Steam Generator Tube Rupture in VVER-1000/V320 Reactor during Extended SBO sequence using SCDAP/RELAP5 code, Nuclear Science and Technology, 9 (4), 9-15.
  https://vinatom.gov.vn/nuclear-science-and-technology-no4-2019/
• Van Thai Nguyen, Ngoc Dung Kieu, 2015. Analysis of Containment Pressure and Temperature Changes Following Loss of Coolant Accident (LOCA), Nuclear Science and Technology, 5 (4),1-8. https://inis.iaea.org/search/search.aspx?orig_q=RN:47065298
• Van Thai Nguyen, Huu Toan Trinh, 2014. Assessment of Steam Condensation Model with the Presence of Non-Condensable Gas in a Vertical Tube using RELAP5 MOD 3.2 Code and MIT Exp. Data,  Nuclear Science and Technology, 4 (3), 7 -18.
  https://inis.iaea.org/search/search.aspx?orig_q=RN:46084858
• Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae, Dong Jin Euh, 2013. The Dependence of Wall Lubrication Force on Liquid Velocity in Turbulent Bubbly Two-Phase Flows. Journal of Nuclear Science and Technology, 50 (8), 781-798.
  http://dx.doi.org/10.1080/00223131.2013.807999
• Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae, Dong Jin Euh, 2013. Modeling of Bubble Coalescence and Break-up considering Turbulent Suppression Phenomena in Bubbly Two-Phase Flow. International Journal of Multiphase Flow, 54, 31-42.
  https://doi.org/10.1016/j.ijmultiphaseflow.2013.03.001
• Van Thai Nguyen, Byoung-Uhn Bae, Dong Jin Euh, Chul-Hwa Song and Byong-Jo Yun, 2012. The effect of Bubble-induced Turbulence on the Interfacial Area Transport in Gas-Liquid Two-phase Flow. Journal of Computational Multiphase Flows, (4), 3, 327-340.
  http://journals.sagepub.com/doi/abs/10.1260/1757-482X.4.3.327
• Van Thai Nguyen, Dong Jin Euh and Chul-Hwa Song, 2010. An application of wavelet analysis for the objective discrimination of two-phase flow patterns, International Journal of Multiphase Flow, 36, 755-768. https://doi.org/10.1016/j.ijmultiphaseflow.2010.04.007

HỘI NGHỊ

• Ngoc Đat Nguyen, Van Thai Nguyen, Performance comparison of ANN-based model and empirical correlations for void fraction prediction of subcooled boiling flow in vertical upward channel, The 14th Vietnam Conference on Nuclear Science and Technology (VINANST-14), Dalat, December, 9-10, 2021.
• Hong Ngoc Le, Ngoc Đat Nguyen, Van Thai Nguyen, Identification of Cold-Leg break size in LOCA accident using artificial neural networks and simulation databasse, The 14th Vietnam Conference on Nuclear Science and Technology (VINANST-14), Dalat, December, 9-10, 2021.
• Ngoc Mai Quach, Van Thai Nguyen, Mai Dung Do, H. Suematsu, Theoretical calculation and simulation of 99mTc production process by neutron irradiation of MoO3 wire using MCNPX code, The 14th Vietnam Conference on Nuclear Science and Technology (VINANST-14), Dalat, December, 9-10, 2021.
• Van Thai Nguyen, Van Loan Dau, Chi Thanh Tran, Effect of Non-Condensable Gas on the Performance of Passive Containment Cooling System in VVER-1200 Design, International Conference on Topical Issues in Nuclear Installation Safety, Vienna, Austria, June 6 -9, 2017.  https://nucleus.iaea.org/sites/gsan/act/CN-251/papers/87-0.pdf
  https://nucleus.iaea.org/sites/gsan/act/CN-251/presentations/V.T.%20Nguyen.pdf
• Van Thai Nguyen, Predictive Capability of Subcooled Boiling Flow in Pressurized Vertical Annulus Channel with Advanced Force-Balance Model and Interfacial Area Transport Equation, The 11th International Topical Meeting on Nuclear Reator Thermal Hydraulics,Operation and Safety (NUTHOS-11), Gyeongju, Korea, October 9 -134, 2016.
• Van Thai Nguyen, Chul-Hwa Song, Chi Thanh Tran, CFD Prediction of Subcooled Boiling with Advanced Mechanistic Models of Interfacial Area Transport Equation, The 16th International Topical Meeting on Nuclear Reator Thermal Hydraulics (NURETH-16), Chicago, USA, Sept 30 – Oct 4, 2015. https://www.scopus.com/record/display.uri?eid=2-s2.0-84962687067&origin=inward&txGid=9705d0f057f807502b94dd4bea7eb303
• Van Thai Nguyen, Huu Toan Trinh, Assessment of Steam Condensation Model with the Presence of Non-Condensable Gas in a Vertical Tube using RELAP5 MOD3.2 Code and MIT Exp. Data, The 3rd Young Researchers Conference on Nuclear Energy, Hanoi, Vietnam, October, 3-4, 2014.
• Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae, Dong Jin Euh and In-Cheol Chu,Computational Fluid Dynamics Models for Boiling Flows in Nuclear Reactor Fuel Assemblies, The 1st Vietnam/Japan Research HRD Forum on Nuclear Technology, Hanoi, Vietnam, December 23-24, 2013.
• Nhan Hien Hoang, Van Thai Nguyen, In-Cheol Chu, Dong Jin Euh and Chul-Hwa Song, Assessment of Bubble Departure Diameter Models for Nucleate Boiling Heat Transfer, Transaction of the Korean Nuclear Society Autumn Meeting, Gyeongju, Korea, October 24-25, 2013. https://inis.iaea.org/search/search.aspx?orig_q=RN:45082378
• Van Thai Nguyen, In-Cheol Chu, Chul-Hwa Song and Dong Jin Euh, Measurement of Small Bubble using Miniature Optical Fiber Probe in Turbulent Bubbly Flows, 2013 International Congress on Advances in Nuclear Power Plants, Jeju, April 14-18, 2013. https://www.scopus.com/record/display.uri?eid=2-s2.0-84925068004&origin=inward&txGid=f53176f708ef861c311485bba68ae4bd
• Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae and Dong Jin Euh, Development of Bubble Break-up and Coalescence Models for 1-G Interfacial Area Transport Equation, The Six Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics, Busan, April 11-13, 2013.
• Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae, In-Cheol Chu and Dong Jin Euh, CFD Modeling of Two-Phase Flows using Interfacial Area Transport Equation, Transaction of KSME, Autumn Meeting, Daejeon, October, 2012.
• Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae, In-Cheol Chu and Dong Jin Euh, Simulation of DEBORA Experiments for Subcooled Boiling Flow by the EAGLE code with One-group Interfacial Area Transport Equation, Transaction of Korean Nuclear Society, Autumn Meeting, Gyeongju, October, 25-26, 2012. https://inis.iaea.org/search/search.aspx?orig_q=RN:44062831
• Dong Jin Euh, Van Thai, Nguyen, Byong Jo Yun and Chul-Hwa Song, Experimental Study for Local Air/Water Flow Structure of Bubbly and Slug Flow Regime, 9th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, Malta, July, 14-17, 2012. https://edas.info/web/hefat2012/programme.html
• Van Thai Nguyen, Byoung-Uhn Bae and Chul-Hwa Song, CFD Analysis of Two-group IATE Models for Bubbly-Cap Flow with EAGLE code, Transaction of American Nuclear Society, Annual meeting, Chicago, USA, June, 24-28, 2012. https://www.scopus.com/record/display.uri?eid=2-s2.0-84876382376&origin=inward&txGid=158dc9156ed1eb19fea1def5c4581faa
• Van Thai Nguyen, Chul-Hwa Song, Byoung-Uhn Bae and Dong Jin Euh, A bubble coalescence model by improving the contact time term with a consideration of the turbulent eddy size, Transaction of KSME, Spring Meeting, Daejeon, May, 10, 2012.
• Van Thai Nguyen, Byoung-Uhn Bae, Dong Jin Euh and Chul-Hwa Song, On the consistency of non-drag interfacial forces in fully developed turbulent bubbly two-phase flow, Transaction of Korean Nuclear Society, Autumn Meeting, Jeju, May, 17-18, 2012. https://inis.iaea.org/search/search.aspx?orig_q=RN:43073545
• Van Thai Nguyen, Byoung-Uhn Bae and Chul-Hwa Song, Simulation of Two-group IATE models with EAGLE code, Transaction of Korean Nuclear Society, Autumn meeting, Gyeongju, Korea, October, 27-28, 2011. https://inis.iaea.org/search/search.aspx?orig_q=RN:43045452
• Van Thai Nguyen, Byoung-Uhn Bae, Dong Jin Euh and Chul-Hwa Song,The effect of Bubble-induced Turbulence and the Bubble Size on the Interfacial Area Transport in Gas-Liquid Two-phase Flow, The 14th International Topical Meeting on Nuclear Reactor ThermalHydraulics, Toronto, Ontario, Canada, September, 25-30, 2011. https://inis.iaea.org/search/search.aspx?orig_q=RN:47071280
• Van Thai Nguyen, Dong Jin Euh and Chul-Hwa Song, Bubble size effect on the interfacial area transport in gas-liquid two-phase flow, Transaction of Korean Nuclear Society, Spring meeting, Taebaek, Korea, May, 26-27, 2011.
• Byoung-Uhn Bae, Dong Jin Euh , Byong-Jo Yun, Van Thai Nguyen and Chul-Hwa Song, Development of EAGLE code with Modeling Interfacial Area Transport Equation,Transaction of American Nuclear Society, Winter meeting, Neveda, USA, November, 7-11, 2010. https://www.scopus.com/record/display.uri?eid=2-s2.0-84875681471&origin=inward&txGid=ac9f8cf0a88912d970745965c08df983
• Van Thai Nguyen, Dong Jin Euh and Chul-Hwa Song, Flow regime identification by continuous wavelet transform, The Seventh Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety, Chuncheon, Korea, Oct, 14-17, 2010.
• Dong Jin Euh ,Van Thai Nguyen, Byong-Jo Yun and Chul-Hwa Song, Transport of Local Two-phase Parameters in Vertical Air/Water Flow for Bubbly and Slug Flow Regime,Transaction of Korean Nuclear Society, Spring meeting, Pyoungchang, Korea, May, 26-28, 2010. ttps://www.kns.org/kns_files/kns/file/14%be%ee%b5%bf%c1%f8.pdf
• Van Thai Nguyen, Byoung-Uhn Bae, Byong-Jo Yun, Dong Jin Euh and Chul-Hwa Song, Assessment of Bubble-Induced Turbulence Models for Isothermal Vertical-upward Bubbly Flows, Transaction of Korean Nuclear Society, Autumn meeting, Jeju, Korea, October, 20-22, 2010.
• Van Thai Nguyen, Dong Jin Euh and Chul-Hwa Song, Identification of Two-Phase Flow Pattern by Wavelet Analysis Technique Using Void Fraction Signals, Transaction of Korean Nuclear Society, Autumn meeting, Gyeongju, Korea, October, 29-30, 2009.
   https://inis.iaea.org/search/search.aspx?orig_q=RN:41027331
• Van Thai Nguyen, Dong Jin Euh and Chul-Hwa Song, Characteristics of Drift-Flux Models for the 3’’ Diameter Vertical-Upward Air-Water Flow Condition, The Fourth Korea-China Workshop on Nuclear Reactor Thermal Hydraulics, Jeju, May 18-20^th, 2009. https://inis.iaea.org/search/search.aspx?orig_q=RN:40081996
• Phung Van Duan, Luu Nam Hai and Nguyen Van Thai. Trial investigation of a neutron reaction by using homemade gaseous detector. Proceedings of Scientific Conference of Vietnam Physics Society ( Hanoi University of Technology,  23 to 25 November 2005), Hanoi, 2006, pp.531-534