Heat Transfer and Safety Analysis Laboratory
Working for what's next in nuclear reactors

Publications

Selected journal papers

Look at a full publication list on Google Scholar.

  1. Hurley, P. and Duarte, J.P., “A recurrent neural network for modeling natural circulation density wave instabilities“, Nuclear Engineering and Technology, 103407, 2024.
  2. Hurley, P., Liu, Y.,  Kozlowski, T., Duarte, J.P., “TRACE assessment of density wave instability onset with void reactivity feedback under natural circulation“, Nuclear Engineering and Technology, 2024.
  3. Hurley, P. Pigg, C., Liu, Y.,  Kozlowski, T., Duarte, J.P., “TRACE Assessment for Simulating Density Wave Oscillations in a Full-Scale BWR Rod Bundle Under Natural Circulation“, Nuclear Technology, 1-14, 2024.
  4. Sahin, E., Lattimer, B., Allaf, M.A., Duarte, J.P., “Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks“, Journal of Nuclear Science and Technology, 2024.
  5. Hurley, P., Kim, K.M., Duarte, J.P., “Modeling of quenching temperature with the effects of axial conduction resulting from quench front propagation“, Nuclear Engineering and Design, 416, 112785, 2024.
  6. Serrao, B.P., Kim, K.M., and Duarte, J.P., “Analysis of the Effects of Different Nanofluids on Critical Heat Flux Using Artificial Intelligence”, Energies, 16(12), 4762, 2023.
  7. Sahin, E., Lattimer, B., and Duarte, J.P., “Assessing spill fire characteristics through machine learning analysis”, Annals of Nuclear Energy, 192, 109961, 2023.
  8. Sahin, E., Leite, V.C., Kim, K.M., Burns, N., Duarte, J.P., Discrete-Time Bayesian Networks Applied to Flexible Coping Strategies of Nuclear Power Plant Systems, Nuclear Science and Engineering, Selected papers for the PSA 2021 Special Issue, 2023.
  9. Kim, K.M., Hurley, P., Duarte, J.P., Physics-informed machine learning-aided framework for prediction of minimum film boiling temperature, International Journal of Heat and Mass Transfer, v.191, 122839, 2022.
  10. 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.
  11. 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.
  12. Hurley, P., and Duarte, J.P., Implementation of Fiber Optic Temperature Sensors in Quenching Heat Transfer Analysis, Applied Thermal Engineering, 117257, 2021.
  13. 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.
  14. 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.
  15. 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.
  16. 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.
  17. 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.
  18. 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.
  19. 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.
  20. 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.
  21. 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.
  22. 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.
  23. 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.
  24. 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.
  25. 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.

 

Thesis / Dissertation

Hurley, P. R., Density-Wave Instability Characterization in Boiling Water Reactors under MELLLA+ Domain during ATWS, Ph.D. dissertation, Nuclear Engineering, Virginia Tech, 2023.

Shakhatreh, A. I., Investigation of Chloride-induced Stress Corrosion Cracking for Long-Term Storage of Spent Nuclear Fuel in Dry Storage Systems, M.Sc. thesis, Nuclear Engineering, Virginia Tech, 2022.

Karabacak, A. H., Design of the high Pressure HIgh temperature annuLUS flow (PHILUS) Facility, M.Sc. thesis, Nuclear Engineering, Virginia Tech, 2022.

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.Sc. thesis, University of Sao Paulo, Brazil, 2014 (in Portuguese).

Duarte, J.P., Atmospheric Dispersion and Dose Evaluation due to Package Drop containing Low and Intermediate Level Waste, B.Sc. thesis, Federal University of Rio de Janeiro, Brazil, 2012 (in Portuguese).