Wenjie Zeng

Ministry of Education — Taiwan

Engineering · Physical Sciences

15h-index792citations62works3.42yr avg
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Research Topics

Nuclear reactor physics and engineering(30), Fault Detection and Control Systems(16), Nuclear Engineering Thermal-Hydraulics(14), Energy Efficient Wireless Sensor Networks(9), Advanced Control Systems Optimization(8)

Publications62 total

Homogenization-based irradiation performance analysis of U-Mo/Al dispersion fuel plates
Journal of Nuclear Materials·2026
A variable universe fuzzy control method for the HCOTSG feedwater system of small pressurized water reactor
Nuclear Engineering and Technology·2026Open Access
Quantitative assessment for core power flexible switching control system of small PWR with uncertainty analysis framework
Progress in Nuclear Energy·2025
Adaptive learning observer based fixed-time stable controller for load following of a Pressurized Water Reactor
Annals of Nuclear Energy·2025· 4 cited
Adaptive learning observer and radial basis function neural networks based fixed-time fault-tolerant control of load following for a MHTGR with CRDM faults
Nuclear Engineering and Design·2025· 2 cited
Design and simulation of the primary frequency regulation for a small pressurized water reactor under load change
Nuclear Engineering and Technology·2025Open Access
A dynamic performance assessment of coordinated control system of small pressurized water reactor based on uncertainty quantification and sensitivity analysis
Reliability Engineering & System Safety·2024· 11 cited
Development and uncertainty analysis of the dynamic simulation for HFETR with BMUS framework
Reliability Engineering & System Safety·2024· 6 cited
Dynamic simulation of core power control for SPWR based on dynamic model bank
Annals of Nuclear Energy·2024· 2 cited
A multi-objective co-optimization method of controller parameters for the overall system of small pressurized water reactor
Energy·2024· 7 cited
RBF-based event-triggered fixed-time stable and chattering-free controller for load following of the pressurized water reactor
Energy·2024· 8 cited
Rbf-Based Event-Triggered Fixed-Time Stable and Chattering-Free Controller for Load Following of the Pressurized Water Reactor ∗
SSRN Electronic Journal·2024· 1 citedOpen Access
A coordinated control methodology for small pressurized water reactor with steam dump control system
Energy·2023· 17 cited
Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method
Nuclear Engineering and Technology·2023· 11 citedOpen Access
PCTran-Cloud: an Accident Simulator for Nuclear Power Plants Based on Cloud Technology
2022· 1 cited
Sensitivity analysis of heat transfer coefficient in primary system for LMSR core power control system based on Sobol’s method
Annals of Nuclear Energy·2022· 9 cited
A Model Predictive Controller for the Core Power Control System of a Lead-Cooled Fast Reactor
Frontiers in Energy Research·2022· 5 citedOpen Access
Uncertainty propagation analysis of ionization chamber sensitivity in core power control system of a small PWR
Annals of Nuclear Energy·2022· 1 cited
Uncertainty quantification of the power control system of a small PWR with coolant temperature perturbation
Nuclear Engineering and Technology·2022· 11 citedOpen Access
Sensitivity Analysis of Heat Transfer Coefficient in Primary System for Lmsr Core Power Control System Based on Sobol Method
SSRN Electronic Journal·2022Open Access
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Frequent Co-authors

Jinsen Xie(14), Tao Yu(11), Xiaoping Tan(8), Anish Arora(8), Qingfeng Jiang(7), Yinuo Liu(6), Tianyu Hui(6), Linna Wang(6), Genfu Zhao(4), Tingying Zhang(4), Tuan‐Wu Cao(3), Ting Huang(3), Liang Chen(3), Junpeng Wang(3), Yuanyuan Ren(3), Chuqi Chen(3), Lekang Chen(3), Zheng Li(3), Pengcheng Zhao(3), Mukundan Sridharan(3)