General Lab Information

Cihang Lu

Research Staff 4 Nuclear Engineer, Nuclear Science and Security S, Nuclear Science & Security Department

Cihang Lu

Brookhaven National Laboratory

Nuclear Science & Security Department
Bldg. 490D, Room 3-6
P.O. Box 5000
Upton, NY 11973-5000

(631) 344-5617
(814) 777-7792
 clu@bnl.gov

Dr. Cihang Lu is a nuclear engineer specializing in advanced reactor design, core safety analysis, accident-tolerant fuel design, and fuel cycle optimization. He has extensive experience in conducting sensitivity and uncertainty analysis using various neutronics and thermal-hydraulics codes.

Education | Publications

Education

2015 - 2019. Ph.D. in the Department of Nuclear Engineering at the Pennsylvania State University.

2013 - 2014.  Master of Science in Nuclear Engineering at National Institute of Nuclear Science and Technology/Atomic Energy and Alternative Energies Commission, France.

2009 - 2015. Combined Bachelor’s/Master’s Degree in Energy and Environment Engineering at National Institute of Applied Sciences of LYON, France.

Selected Publications

  • Lu C, Hiscox BD, Terrani KA, Brown NR (2018) Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: Analysis of reactor performance and safety characteristics. Annals of Nuclear Energy 114:277–287. https://doi.org/10.1016/j.anucene.2017.12.021
  • Lu C, Kong R, Qiao S, et al (2018) Frictional pressure drop analysis for horizontal and vertical air-water two-phase flows in different pipe sizes. Nuclear Engineering and Design 332:147–161. https://doi.org/10.1016/j.nucengdes.2018.03.036
  • Wu Z, Lu C, Morgan S, et al (2020) A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors. Progress in Nuclear Energy 125:103369. https://doi.org/10.1016/j.pnucene.2020.103369
  • Lu C, Brown NR (2019) Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost. Nuclear Engineering and Design 347:108–121. https://doi.org/10.1016/j.nucengdes.2019.03.022
  • Kong R, Rau A, Lu C, et al (2018) Experimental study of interfacial structure of horizontal air-water two-phase flow in a 101.6?mm ID pipe. Experimental Thermal and Fluid Science 93:57–72. https://doi.org/10.1016/j.expthermflusci.2017.12.016
  • Lu C, Cuadra A (2025) Feasibility of Recycling Discharged Microreactor Heavy Metal in Light Water and Sodium-Cooled Fast Reactors: A Neutronics Analysis. Nuclear Technology 1–16. https://doi.org/10.1080/00295450.2025.2494312
  • Lu C, Kardoulaki E, Stauff NE, Cuadra A (2024) The Use of High-Density UN Fuel in Heat-Pipe Microreactors. Nuclear Technology 211:690–707. https://doi.org/10.1080/00295450.2024.2348732
  • Lu C, Wu Z (2022) A New Method to Efficiently Estimate the Equilibrium State of Pebble Bed Reactors. Nuclear Technology 208:1577–1590. https://doi.org/10.1080/00295450.2022.2049966
Cihang Lu

Brookhaven National Laboratory

Nuclear Science & Security Department
Bldg. 490D, Room 3-6
P.O. Box 5000
Upton, NY 11973-5000

(631) 344-5617
(814) 777-7792
 clu@bnl.gov

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