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

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, Cuadra A (2026) Design-informed neutronics assessment of long-lived fission product transmutation in a tokamak fusion reactor blanket. Annals of Nuclear Energy 238:112552. https://doi.org/10.1016/j.anucene.2026.112552
• Lu C, Kohut P, Cheng L-Y, et al (2026) Fuel Fabrication Specification Impact Analysis for NBSR LEU Conversion. Nuclear Technology 1–14. https://doi.org/10.1080/00295450.2026.2669438
• Walker S, Stewart R, Dim O, et al (2026) Exploring diversion-pathway analysis of a generic molten-salt fast reactor using multiphysics informed signatures. Progress in Nuclear Energy 191:106047. https://doi.org/10.1016/j.pnucene.2025.106047
• 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
• Wu Z, Lu C, Liu T (2023) Demonstrating Computational Equivalence Between Continuous and Discrete Adjoint Methods by Calculating Time-Dependent Adjoint Solutions with Neutron Diffusion Models. Nuclear Science and Engineering 197:1213–1238. https://doi.org/10.1080/00295639.2022.2143207
• 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
• Lu C, Wu Z (2021) Uncertainty Quantification of the 1-D SFR Thermal Stratification Model via the Latin Hypercube Sampling Monte Carlo Method. Nuclear Technology 208:37–48. https://doi.org/10.1080/00295450.2021.1874779
• Lu C, Wu Z, Wu X (2020) Enhancing the One-Dimensional SFR Thermal Stratification Model via Advanced Inverse Uncertainty Quantification Methods. Nuclear Technology 207:692–710. https://doi.org/10.1080/00295450.2020.1805259
• Lu C, Wu Z (2020) Sensitivity analysis of the 1-D SFR thermal stratification model via discrete adjoint sensitivity method. Nuclear Engineering and Design 370:110920. https://doi.org/10.1016/j.nucengdes.2020.110920
• Lu C, Wu Z, Morgan S, et al (2020) An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors. Nuclear Technology 206:1465–1480. https://doi.org/10.1080/00295450.2020.1719799
• 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
• Liu T, Wu Z, Lu C, Martin RP (2021) A best estimate plus uncertainty safety analysis framework based on RELAP5-3D and RAVEN platform for research reactor transient analyses. Progress in Nuclear Energy 132:103610. https://doi.org/10.1016/j.pnucene.2020.103610
• Lu C, Koyanagi T, Katoh Y, et al (2019) Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process. Nuclear Engineering and Design 345:125–147. https://doi.org/10.1016/j.nucengdes.2019.02.012
• 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
• 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
• 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