Jianhui Wu

Hunan Institute of Science and Technology — China

Engineering · Physical Sciences

12h-index561citations67works1.92yr avg
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Research Topics

Nuclear reactor physics and engineering(46), Nuclear Materials and Properties(36), Graphite, nuclear technology, radiation studies(18), Nuclear Physics and Applications(11), Fusion materials and technologies(7)

Publications67 total

ADSPA: Decoupling hyperspectral features for photosensitive and non-photosensitive water quality parameter inversion
Journal of Water Process Engineering·2025
Thermal neutron shielding properties of rare-earth nickel alloy materials
Nuclear Materials and Energy·2025· 1 citedOpen Access
Economic Analysis of Nuclear Energy Cogeneration: A Comprehensive Review on Integrated Utilization
Energies·2025· 5 citedOpen Access
PGA-Net: progressive granularity-aware training network for fine-grained image recognition
Soft Computing·2025· 2 cited
Influence of narrow gaps between the adjacent components on graphite lifetime in molten salt reactors
Annals of Nuclear Energy·2025
Oriented ice eddy detection network based on the Sentinel-1 dual-polarization data
Frontiers in Marine Science·2025· 2 citedOpen Access
Nonlinear terminal sliding mode trajectory tracking control algorithm for industrial robots based on dung beetle optimizer
Journal of Physics Conference Series·2024Open Access
Improvements of the dynamics code TMSR3D for molten salt reactor leveraging triangular prism nodal method
Progress in Nuclear Energy·2024· 1 cited
High-fidelity lensless imaging with single hologram based on physics-guided frequency-aware network
Applied Physics Letters·2024· 9 cited
Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor
2024Open Access
Preliminarysafety analysis for a heavy water-moderated molten salt reactor
Nuclear Science and Techniques·2024· 4 cited
Core Optimization for Extending the Graphite Irradiation Lifespan in a Small Modular Thorium-Based Molten Salt Reactor
Journal of Nuclear Engineering·2024· 1 citedOpen Access
Correction to: Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium
Nuclear Science and Techniques·2024Open Access
Xenon behavior modeling for molten salt reactors by using multiple transport mechanisms
Progress in Nuclear Energy·2023· 6 cited
Conceptual Design of a Novel Megawatt Molten Salt Reactor Cooled by He-Xe Gas
International Journal of Energy Research·2023· 2 citedOpen Access
Research on Initiating Events Analysis of Small Helium-Xenon Gas Cooled Nuclear Reactor
Energies·2023· 6 citedOpen Access
Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium
Nuclear Science and Techniques·2023· 4 citedOpen Access
Impacts of core parameters on the capability of Cf-252 production in an MSR
Annals of Nuclear Energy·2023· 1 cited
Xenon Behavior Modeling for Molten Salt Reactors by Using Multiple Transport Mechanisms
SSRN Electronic Journal·2023Open Access
Minor Actinides Transmutation in Thermal, Epithermal and Fast Molten Salt Reactors with Very Deep Burnup
Springer proceedings in physics·2023· 2 citedOpen Access
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Frequent Co-authors

Jingen Chen(32), Chunyan Zou(29), X. Z. Cai(28), Chenggang Yu(22), Yuwen Ma(8), X.X. Li(6), Yong Cui(6), J.G. Chen(5), Ao Zhang(5), Y. Oka(4), Chen Wu(4), Jianlong Han(3), Shaopeng Xia(3), Deyang Cui(3), Hongkai Zhao(3), Jun Zhou(3), Xiang Zhang(3), Yijia Zheng(3), Xuzhong Kang(2), Ming Dai(2)