| Transient behavior of the sodium–potassium alloy heat pipe in passive residual heat removal system of molten salt reactor C Wang, Z Guo, D Zhang, S Qiu, W Tian, Y Wu, G Su Progress in Nuclear Energy 68, 142-152, 2013 | 70 | 2013 |
| Optimal design of supercritical CO2 power cycle for next generation nuclear power conversion systems Z Guo, Y Zhao, Y Zhu, F Niu, D Lu Progress in Nuclear Energy 108, 111-121, 2018 | 57 | 2018 |
| Coupled neutronics/thermal-hydraulics for analysis of molten salt reactor Z Guo, J Zhou, D Zhang, KS Chaudri, W Tian, G Su, S Qiu Nuclear Engineering and Design 258, 144-156, 2013 | 35 | 2013 |
| Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor Z Guo, D Zhang, Y Xiao, W Tian, G Su, S Qiu Annals of Nuclear Energy 53, 309-319, 2013 | 27 | 2013 |
| Defect detection of nuclear fuel assembly based on deep neural network Z Guo, Z Wu, S Liu, X Ma, C Wang, D Yan, F Niu Annals of Nuclear Energy 137, 107078, 2020 | 24 | 2020 |
| Design of the Compact Integral Effects Test Facility and Validation of Best-Estimate Models for Fluoride Salt–Cooled High-Temperature Reactors PP Nicolas Zweibaum, Zhangpeng Guo, James Kendrick NUCLEAR TECHNOLOGY 196, 641-660, 2017 | 21* | 2017 |
| Optimal study of swordfish fin microchannel heat exchanger for the next generation nuclear power conversion system of lead-based reactor Y Lu, Z Guo, Y Gong, T Zhang, Y Huang, F Niu Annals of Nuclear Energy 165, 108679, 2022 | 13 | 2022 |
| Development of a kinetic model for safety studies of liquid-fuel reactors D Zhang, A Rineiski, C Wang, Z Guo, Y Xiao, S Qiu Progress in Nuclear Energy 81, 104-112, 2015 | 13 | 2015 |
| Global sensitivity analysis of passive safety systems of FHR by using meta-modeling and sampling methods Y Zhao, Z Guo, F Niu, Y Yu, S Wang Progress in Nuclear Energy 115, 30-41, 2019 | 12 | 2019 |
| Modeling analyses of two-phase flow instabilities for straight and helical tubes in nuclear power plants R Dong, F Niu, Y Zhou, Y Yu, Z Guo Nuclear Engineering and Design 307, 205-217, 2016 | 12 | 2016 |
| The measure on mitigating hydrogen risk during LOCA accident in nuclear power plant X Meng, X Lyu, B Wang, S Liu, Y Yu, Z Guo Annals of Nuclear Energy 136, 107032, 2020 | 10 | 2020 |
| Design, fabrication and startup testing in the compact integral effects test facility in support of fluoride-saltcooled, high-temperature reactor technology N Zweibaum, JE Bickel, Z Guo, JC Kendrick, PF Peterson International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH …, 2015 | 10 | 2015 |
| Numerical analysis for a molten salt reactor in the presence of localized perturbations Y Xiao, D Zhang, Z Guo, Y Wu, W Tian, G Su, S Qiu Progress in Nuclear Energy 60, 61-72, 2012 | 10 | 2012 |
| Global sensitivity analysis of the main steam line break accident by using sampling methods and surrogate models Q Sun, Z Guo, W Chen, Y Yu, Z Wang, J Guo, F Niu Annals of Nuclear Energy 150, 107787, 2021 | 9 | 2021 |
| Experimental Strategy for the Determination of Heat Transfer Coefficients in Pebble-Beds Cooled By Fluoride Salts L Huddar, PF Peterson, R Scarlat, Z Guo NURETH-16, Chicago, IL, August 30-September 4 2015, 1659-1675, 2015 | 8 | 2015 |
| Couple, a time-dependent coupled neutronics and thermal-hydraulics code, and its application to MSFR D Zhang, ZG Zhai, A Rineiski, Z Guo, C Wang, Y Xiao, S Qiu International Conference on Nuclear Engineering 45936, V003T05A019, 2014 | 8 | 2014 |
| Experimental analysis of steam mixing and thermal stratification phenomena related to small steel containment studies S Wang, Y Wang, W Zhuo, F Niu, Y Yu, Z Guo, Y Shen, W Chen, X Jiang Annals of Nuclear Energy 109, 103-112, 2017 | 7 | 2017 |
| Validation of best estimate models for fluoride-salt cooled, high-temperature reactors using data from the compact integral effects test (CIET 1.0) facility N Zweibaum, Z Guo, L Huddar, P Peterson 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics …, 2015 | 7 | 2015 |
| The effects of core zoning on optimization of design analysis of molten salt reactor Z Guo, C Wang, D Zhang, KS Chaudri, W Tian, G Su, S Qiu Nuclear Engineering and Design 265, 967-977, 2013 | 7 | 2013 |
| The influence of lower plenum and distribution plates to thermal hydraulics characteristics of MSR Z Jianjun, Z Guo, Q Suizheng, T Wenxi, S Guanghui Nuclear Engineering and Design 256, 235-248, 2013 | 7 | 2013 |
Khurrum Saleem ChaudriPakistan Institute of Engineering and Applied SciencesVerified email at pieas.edu.pk
