Selected journal publication

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.

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.

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.

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.

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 channelAnnals of Nuclear Energy, v. 121, p. 203-209, 2018.

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.

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.

DUARTE J.P.; Corradini, M.L., Hydraulic and Heated Equivalent Diameters Used in Heat Transfer CorrelationsNuclear Technology, v. 201, p. 1-4, 2017.

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.

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.

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 Publication

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.

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.

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.

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.

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

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).

    Laboratory address:

    Department of Mechanical Engineering
    302 Goodwin Hall
    College of Engineering, Virginia Tech
    635 Prices Fork Road, Blacksburg, VA 24061