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Publications

Selected Journal Publications

  1. Salvi, U., Lattimer, B.Y., Alhadhrami, S., Wang, J., Sahin, E., and Duarte, J.P., Analysis of historic fires to determine most frequent challenging events, Progress in Nuclear Energy, v.146, 104146, 2022.
  2. Kim, K.M., Hurley, P., Duarte, J.P., High-resolution prediction of quenching behavior using machine learning based on optical fiber temperature measurement, International Journal of Heat and Mass Transfer, v.184, 122338, 2022.
  3. Hurley, P., and Duarte, J.P., Implementation of Fiber Optic Temperature Sensors in Quenching Heat Transfer Analysis, Applied Thermal Engineering, 117257, 2021. 
  4. Moreira, T.A., DUARTE, J.P., Nascimento, F.J., and Ribatski, G., Flow boiling heat transfer coefficient of DI water and nanofluids inside microscale channels under conditions near the critical heat flux (CHF), Journal of the Brazilian Society of Mechanical Sciences and Engineering, v.43, 308, 2021. 
  5. DUARTE, J.P., Yarsky, P., Zaki, T., Corradini, M.L., Full-scale dryout/rewet instability tests in a BWR rod bundle and TRACE assessment, Nuclear Engineering and Design, v.370, 1-11, 2020.
  6. Zhao, D., DUARTE, J.P., Liu, W., Corradini, M.L., Wang, J., Bi, J., DNB type critical heat flux prediction in rod bundles with simplified grid spacer based on Liquid Sublayer Dryout model, Nuclear Engineering and Design, v. 351, p. 94-105, 2019.
  7. Zhang, R., DUARTE, J. P., Cong, T., Corradini, M. L., Investigation on the critical heat flux in a 2 by 2 fuel assembly under low flow rate and high pressure with a CFD methodology. Annals of Nuclear Energy, v. 124, p. 69-79, 2019.
  8. DUARTE, J.P., Zhao, D., Jo, H., Corradini, M.L., Critical heat flux experiments and a post-CHF heat transfer analysis using 2D inverse heat transfer. Nuclear Engineering and Design, v. 337, p. 17-26, 2018.
  9. Jo, H., Yeom, H., Yoon, D.S., DUARTE, J.P., Corradini, M.L., Minimum heat flux (MHF) behavior with different surface characteristics including structured surfaces and different surface energies. International Journal of Heat and Mass Transfer, v. 127, p. 414-421, 2018.
  10. Dong, X., DUARTE, J.P., Liu, D., Wang, J., Zhang, Z., Tian, Z., Numerical investigation of azimuthal heat conduction effects on CHF phenomenon in rod bundle channel. Technical Note, Annals of Nuclear Energy, v. 121, p. 203-209, 2018.
  11. Greenwood, M.S., DUARTE, J.P., Corradini, M., Presentation and comparison of experimental critical heat flux data at conditions prototypical of light water small modular reactors. Nuclear Engineering and Design, v. 317, p. 220-231, 2017.
  12. Dong, X., DUARTE, J.P., Zhang, Z., Corradini, M.L., Tian, Z., Chen, G., Numerical investigation of single-phase heat transfer in a 2×2 rod bundle with spacer grids for a High Pressure Heat Transfer Facility. Nuclear Technology, v. 199, p. 174-186, 2017.
  13. DUARTE J.P., Corradini, M.L., Hydraulic and Heated Equivalent Diameters Used in Heat Transfer Correlations. Technical Note, Nuclear Technology, v. 201, p. 1-4, 2017.
  14. Gomes, E.C., DUARTE, J.P., Frutuoso e Melo, P.F., Human Reliability Modeling of Radiotherapy Procedures by Bayesian Networks and Expert Opinion Elicitation. Nuclear Technology, v. 194, p. 73-96, 2016.
  15. Ribeiro, A.C.O., Sousa, A.L., DUARTE, J. P., Frutuoso e Melo, P.F., Human reliability analysis of the Tokai-Mura accident through a THERP-CREAM and expert opinion auditing approach. Safety Science, v. 87, p. 269-279, 2016.
  16. DUARTE, J.P., Rivero, J.J., Frutuoso e Melo, P.F.F., Alvim, A.C.M., Coupling of a Lumped Parameter and a Finite Difference Model for Estimation of a Reactivity-Induced Transient in a PWR with Annular Fuel Rods. Nuclear Technology, v. 185, p. 109-126, 2014.

 

Selected Conference Publications

  1. Kim, K.M., Hurley, P., Duarte, J.P., “Machine Learning Approach for Prediction of High-Resolution Quenching Heat Transfer”, American Nuclear Society (ANS) Winter Meeting, Washington D.C., USA, November 30-December 3, 2021.
  2. Hurley, P., Alblooshi, A., Kim, K.M., Duarte, J.P., “Vapor Film Collapse and Quench Front Propagation Analysis using Optical Fiber Temperature Sensors”, American Nuclear Society (ANS) Winter Meeting, Washington D.C., USA, November 30-December 3, 2021.
  3. Sahin, E., Leite, V.C., Duarte, J.P., “Discrete-time Bayesian Networks Applied to Reliability of Flexible Coping Strategies of Nuclear Power Plants”, 2021 International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021), virtual meeting, November 7-12, 2021.
  4. Seo, K., Yoon, H., Kim, In G., Kim, S-H., Duarte, J.P., Corradini, M., “The Analysis and Comparison for Air-Water flow phenomena using TRACE”, American Nuclear Society ANS Winter Meeting, Virtual Meeting, 2020.
  5. Hurley, P., Duarte, J.P., “Fiber Optic Sensing Application in Quenching Temperature Measurement”. American Nuclear Society (ANS) Winter Meeting, Washington, D.C., USA, November 17-21, 2019.
  6. Duarte, J.P., Yarsky, P., Zaki, T., Corradini, M. L., “Rod Bundle Post-CHF Heat Transfer Analysis at BWR Prototypical Conditions – Part 1: Inverse Heat Transfer”.  18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, Oregon, USA, August 18-23, 2019.
  7. Duarte, J.P., Yarsky, P., Zaki, T., “Rod Bundle Post-CHF Heat Transfer Analysis at BWR Prototypical Conditions – Part 2: Heat Transfer Coefficients”.  18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, Oregon, USA, August 18-23, 2019.
  8. Yarsky, P., Zaki, T., Duarte, J.P., “Preliminary Analysis of Measured Data from a Simulated BWR Fuel Assembly Undergoing Power and Flow Oscillations Representative of Anticipated Transient without SCRAM Conditions”. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18), Portland, Oregon, USA, August 18-23, 2019.
  9. Duarte, J.P., Jo, H., Corradini, M.L., “Using Inverse Heat Transfer in the Analysis of Two-Phase Flow Post-CHF Experiments”. American Nuclear Society (ANS) Winter Meeting, Orlando, Florida, USA, November 11-15, 2018.

Thesis / Dissertation

Sahin, E., Discrete-Time Bayesian Networks Applied to Reliability of Flexible Coping Strategies of Nuclear Power Plants,  M.Sc. thesis, Nuclear Engineering, Virginia Tech, 2021.

Hurley, P.R., Application of Optical Fiber Sensors for Quenching Temperature Measurement, M.Sc. thesis, Nuclear Engineering, Virginia Tech, 2020.

Dr. Duarte:

DUARTE, J. P., Understanding the Minimum Film Boiling Temperature in Two-Phase Flow, Ph.D. dissertation, Engineering Physics Department, University of Wisconsin-Madison, 2018.

DUARTE, J. P., A design of experiments for evaluating the critical heat flux of small-scale pressurized water reactors, M.S. thesis, University of Sao Paulo, Brazil, 2014 (in Portuguese).