Zhouyu Liu

Xi'an Jiaotong University — China

Engineering · Physical Sciences

14h-index791citations84works1.22yr avg
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Research Topics

Nuclear reactor physics and engineering(67), Nuclear Physics and Applications(30), Nuclear Materials and Properties(26), Nuclear Engineering Thermal-Hydraulics(17), Fusion materials and technologies(8)

Publications84 total

Research advances in high-fidelity neutronics computational methods and applications for advanced nuclear reactors
Chinese Science Bulletin (Chinese Version)·2025Open Access
Group condensation method for the transport calculation of PWR with dispersed-particle fuel
Annals of Nuclear Energy·2025
A neutron transport calculation approach via the coupling of 2D/1D and 3D SN nodal methods
Annals of Nuclear Energy·2025· 1 cited
Simulation of the fuel-assembly bowing in PWR based on the coupling of pin-resolved neutronics and pin-by-pin subchannel
Annals of Nuclear Energy·2025· 3 cited
The neutron transport equation in exact differential form
Science China Physics Mechanics and Astronomy·2025· 2 cited
Deep learning-based prediction of transient power variation in pressurized water reactors
Progress in Nuclear Energy·2025
A simulation approach for start-up without secondary neutron sources of Hualong One: A Monte-Carlo-deterministic framework
Nuclear Engineering and Technology·2025Open Access
Group Condensation Method for the Transport Calculation of Pwr With Dispersed-Particle Fuel
SSRN Electronic Journal·2025Open Access
Calculation and Analysis of Self-Shielded Cross Sections for the High-Fidelity Neutronics Calculation of Fast Reactors
SSRN Electronic Journal·2025Open Access
Flexible strain sensors based on carbon nanotubes/polydimethylsiloxane composites with a segregated structure prepared by sustainable emulsion method
Polymer Engineering and Science·2024· 5 citedOpen Access
A porous carbon nanotube/polydimethylsiloxane strain sensor with low strain monitoring limit prepared by sustainable emulsion method
Sensors and Actuators A Physical·2024· 4 cited
Resonance Calculation of FCM Fuel Based on the Global-Local Method
Nuclear Science and Engineering·2024· 2 cited
Count Rate Analysis of the Source-range Detector for M310
EPJ Web of Conferences·2024Open Access
Deep Learning-Based Prediction of Transient Power Variation in Pressurized Water Reactors
SSRN Electronic Journal·2024Open Access
Development of Fuel Performance Analysis Code for Liquid Metal Coole Fast Reactor Based on MOOSE Platform
Springer proceedings in physics·2023· 1 cited
SN-MscaleDNN: A coupling approach for rapid shielding-scheme evaluation of micro gas-cooled reactor in the large design-parameter space
Annals of Nuclear Energy·2023· 2 cited
Monte Carlo analyses and experimental investigation of the vanadium self-powered neutron detector in 60Co source and research pulsed reactor
Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment·2023· 4 cited
Development of high-fidelity neutronics/thermal-hydraulics coupling system for the hexagonal reactor cores based on NECP-X/CTF
Annals of Nuclear Energy·2023· 3 citedOpen Access
A flexible strain sensor of porous conductive silicone rubber composites prepared from high internal phase emulsion
Journal of Applied Polymer Science·2023· 11 citedOpen Access
Development and Verification of a New Depletion, Activation and Radiation Source Term Calculation Code
Springer proceedings in physics·2023Open Access
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Frequent Co-authors

Liangzhi Cao(37), Hongchun Wu(32), Qingming He(15), Tiejun Zu(8), Chen Zhao(6), Thomas Downar(5), Brendan Kochunas(5), Lu Cao(5), Jun Chen(4), Yunzhao Li(4), Benjamin Collins(4), Xingjian Wen(4), Xinyu Zhou(4), Wei Shen(3), Jess C Gehin(3), Andrew Godfrey(3), Daniel Jabaay(3), Blake W. Kelley(3), Kang Kim(3), Edward W. Larsen(3)