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Juliana Pacheco Duarte

Juliana Pacheco Duarte

Assistant Professor

Prof. Juliana Pacheco Duarte is an Assistant Professor in the Department of Nuclear Engineering & Engineering Physics at the University of Wisconsin-Madison. Her research focuses on safety analysis, thermal-hydraulics, and risk assessment of advanced nuclear systems. Dr. Duarte’s expertise encompasses safety analysis, experimental design for studying two-phase heat transfer phenomena at high-pressure conditions, and computational thermal-hydraulic analysis using subchannel codes (COBRA, CTF) and system safety codes (TRACE, MELCOR). Her expertise encompasses several machine learning and statistical methods in safety, fire data, and reliability analysis. Before coming to the U.S., Dr. Duarte worked as a graduate student at the Brazilian Navy’s thermal-hydraulics division, designing critical heat flux experiments for nuclear propulsion reactors. She currently applies her expertise to the design of fusion machines.

Department

Nuclear Engineering & Engineering Physics

Contact

425, Engineering Research Building
1500 Engineering Dr
Madison, WI

  • PhD 2018, University of Wisconsin-Madison
  • BS 2016, State University of Campinas (UNICAMP)
  • MS 2014, University of São Paulo (USP)
  • BS 2013, Federal University of Rio de Janeiro (UFRJ)

  • Safety analysis
  • Thermal-hydraulics
  • Post-critical heat flux
  • Two-phase flow

  • 2023 DOE Nuclear Energy University Program, Distinguished Early Carrer Program Award
  • 2022 American Nuclear Society, ATH’22 Best Paper Award
  • 2019 US Nuclear Regulatory Commission Nuclear Education Program, Faculty Development award
  • 2014 Regional Council of Engineering and Agronomy of Rio de Janeiro State (CREA/RJ), IV OSCAR NIEMEYER Award for Scientific and Technological Projects
  • 2014 CAPES, Science without Borders Fellowship for Ph.D. studies
  • 2013 Navy Technological Center in São Paulo (CTMSP), Fellowship
  • 2012 Foundation for Research Support of the State of Rio de Janeiro (FAPERJ), Scholarship
  • 2010 National Institute of Science and Technology of Innovative Nuclear Reactors – INCT/CNPq, Scholarship
  • 2008 National Council for Scientific and Technological Development (PIBIC/CNPq) Scholarship, Scholarship

  • I SY E 574 - Methods for Probabilistic Risk Analysis of Nuclear Power Plants (Spring 2025)
  • N E 574 - Methods for Probabilistic Risk Analysis of Nuclear Power Plants (Spring 2025)
  • N E 790 - Master's Research and Thesis (Spring 2025)
  • N E 890 - Pre-Dissertator's Research (Spring 2025)
  • N E 990 - Research and Thesis (Spring 2025)
  • N E 790 - Master's Research and Thesis (Fall 2024)
  • N E 890 - Pre-Dissertator's Research (Fall 2024)
  • N E 990 - Research and Thesis (Fall 2024)
  • N E 890 - Pre-Dissertator's Research (Summer 2024)
  • N E 990 - Research and Thesis (Summer 2024)
  • E M A 471 - Intermediate Problem Solving for Engineers (Spring 2024)
  • E P 471 - Intermediate Problem Solving for Engineers (Spring 2024)
  • N E 790 - Master's Research and Thesis (Spring 2024)
  • N E 890 - Pre-Dissertator's Research (Spring 2024)
  • N E 990 - Research and Thesis (Spring 2024)
  • N E 999 - Advanced Independent Study (Spring 2024)
  • N E 411 - Nuclear Reactor Engineering (Fall 2023)
  • N E 890 - Pre-Dissertator's Research (Fall 2023)
  • N E 699 - Advanced Independent Study (Summer 2023)
  • N E 790 - Master's Research and Thesis (Summer 2023)
  • N E 890 - Pre-Dissertator's Research (Summer 2023)