| Frictional pressure drop analysis for horizontal and vertical air-water two-phase flows in different pipe sizes C Lu, R Kong, S Qiao, J Larimer, S Kim, S Bajorek, K Tien, C Hoxie Nuclear Engineering and Design 332, 147-161, 2018 | 52 | 2018 |
| Fully ceramic microencapsulated fuel in prismatic high temperature gas-cooled reactors: analysis of reactor performance and safety characteristics C Lu, BD Hiscox, KA Terrani, NR Brown Annals of Nuclear Energy 114, 277-287, 2018 | 49 | 2018 |
| Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost C Lu, NR Brown Nuclear Engineering and Design 347, 108-121, 2019 | 28 | 2019 |
| A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors Z Wu, C Lu, S Morgan, SB y Leon, M Bucknor Progress in Nuclear Energy 125, 103369, 2020 | 27 | 2020 |
| Experimental study of interfacial structure of horizontal air-water two-phase flow in a 101.6 mm ID pipe R Kong, A Rau, C Lu, J Gamber, S Kim, S Bajorek, K Tien, C Hoxie Experimental Thermal and Fluid Science 93, 57-72, 2018 | 25 | 2018 |
| Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the … C Lu, T Koyanagi, Y Katoh, G Strydom, KA Terrani, NR Brown Nuclear Engineering and Design 345, 125-147, 2019 | 22 | 2019 |
| An efficient 1-D thermal stratification model for pool-type sodium-cooled fast reactors C Lu, Z Wu, S Morgan, J Schneider, M Anderson, L Xu, E Baglietto, ... Nuclear Technology 206 (10), 1465-1480, 2020 | 12 | 2020 |
| A new method to efficiently estimate the equilibrium state of pebble bed reactors C Lu, Z Wu Nuclear Technology 208 (10), 1577-1590, 2022 | 4 | 2022 |
| Enhancing the one-dimensional sfr thermal stratification model via advanced inverse uncertainty quantification methods C Lu, Z Wu, X Wu Nuclear Technology 207 (5), 692-710, 2021 | 4 | 2021 |
| A Preliminary Study on the Use of the Linear Regression Method for Multigroup Cross-Section Interpretation C Lu, Z Wu Nuclear Science and Engineering 195 (4), 437-452, 2021 | 4 | 2021 |
| A best estimate plus uncertainty safety analysis framework based on RELAP5-3D and RAVEN platform for research reactor transient analyses T Liu, Z Wu, C Lu, RP Martin Progress in Nuclear Energy 132, 103610, 2021 | 4 | 2021 |
| Sensitivity analysis of the 1-D SFR thermal stratification model via discrete adjoint sensitivity method C Lu, Z Wu Nuclear Engineering and Design 370, 110920, 2020 | 3 | 2020 |
| Thermal Stratification Analysis for Sodium-Cooled Fast Reactors: Development of the 1-D System Model C Lu, Z Wu, J Schneider, M Anderson, L Xu, E Baglietto, M Bucknor, ... Trans. Am. Nucl. Soc 121, 1703-1706, 2019 | 3 | 2019 |
| Uncertainty quantification of the 1-D SFR thermal stratification model via the Latin Hypercube Sampling Monte Carlo method C Lu, Z Wu Nuclear Technology 208 (1), 37-48, 2022 | 2 | 2022 |
| Joshua Larimer, Seungjin Kim, Stephen Bajorek, Kirk Tien, Chris Hoxie “Frictional Pressure Drop Analysis for Horizontal and Vertical Airwater Two-phase Flows in Different Pipe … C Lu, R Kong, S Qiao Nucl Eng. Des 332, 147-148, 2018 | 2 | 2018 |
| Neutronic Simulation of Curved Fuel Plate with Flat Plate Geometry C Lu, A Cuadra, P Kohut, LY Cheng Brookhaven National Lab.(BNL), Upton, NY (United States), 2022 | 1 | 2022 |
| Fully Ceramic Microencapsulated Fuel in High-Temperature Gas-Cooled Reactors C Lu The Pennsylvania State University, 2019 | 1 | 2019 |
| The Use of the High-density UN Fuel in Heat-pipe Microreactors C Lu, E Kardoulaki, NE Stauff, A Cuadra Brookhaven National Laboratory (BNL), Upton, NY (United States), 2023 | | 2023 |
| Status of Neutronic Model Improvements for the NBSR LEU Conversion-BNL Support C Lu, P Kohut, A Varuttamaseni, LY Cheng, A Cuadra Brookhaven National Laboratory (BNL), Upton, NY (United States), 2023 | | 2023 |
| Nuclear Data Uncertainty-Impact on keff for the NBSR C Lu, C Sears, A Cuadra, LY Cheng, P Kohut, A Varuttamaseni Brookhaven National Laboratory (BNL), Upton, NY (United States), 2023 | | 2023 |
Zeyun Wu (吴泽云）Virginia Commonwealth UniversityVerified email at vcu.edu
