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Publications

Selected Journal Publications

  1. 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.
  2. 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 modelNuclear Engineering and Design, v. 351, p. 94-105, 2019.
  3. 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 methodologyAnnals of Nuclear Energy, v. 124, p. 69-79, 2019.
  4. 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 transferNuclear Engineering and Design, v. 337, p. 17-26, 2018.
  5. 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 energiesInternational Journal of Heat and Mass Transfer, v. 127, p. 414-421, 2018.
  6. 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.
  7. 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 reactorsNuclear Engineering and Design, v. 317, p. 220-231, 2017.
  8. 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.
  9. 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.
  10. Gomes, E.C., DUARTE, J.P., Frutuoso e Melo, P.F., Human Reliability Modeling of Radiotherapy Procedures by Bayesian Networks and Expert Opinion ElicitationNuclear Technology, v. 194, p. 73-96, 2016.
  11. 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 approachSafety Science, v. 87, p. 269-279, 2016.
  12. 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 RodsNuclear Technology, v. 185, p. 109-126, 2014.

Selected Conference Publications

  1. 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.
  2. 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.
  3. 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.
  4. 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.
  5. 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

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).