Enping Zhu, Tao Li, Jinbiao Xiong, Xiang Chai, Tengfei Zhang, Xiaojing Liu (2026). A digital twin framework for real-time operation monitoring and its future prediction for space nuclear power. Reliability Engineering & System Safety, Vol. 267.DOI
Xiaojing Liu, Shanghai Jiao (2026). Breaking silos, building bridges—Welcome to Open Nuclear Energy. Open Nuclear Energy.DOI
Sheng-Dian Zou, Qing-Quan Pan, Xiaojing Liu (2026). Refined Multiphysics Coupling Analysis in Optimized Isotope Production. Nuclear Engineering and Technology.DOI
Yun-Geng Li, Qing-Quan Pan, Xiaojing Liu (2026). Optimized design of Mixed-Loaded fuel bundle for Mo-99 production in CANDU reactors. Annals of Nuclear Energy.DOI
Qing-Quan Pan, Lian-Jie Wang, Bang-Yang Xia, Yun Cai, Xiaojing Liu (2026). Optimal neutron spectrum dataset for medical isotopes production. Advanced Engineering Informatics.DOI
Yong-Peng Chen, Qing-Quan Pan, Xiaojing Liu, Jian Lu, Xiao-Lin Zhao (2026). Efficient Reactor Irradiation Production Technology for Ra-223. Nuclear Engineering and Technology.DOI
Qing-Quan Pan, Lian-Jie Wang, Yun Cai, Xiaojing Liu (2026). Optimal neutron spectra for Californium-252 production. Radiation Physics and Chemistry.DOI
Guo Lv, Qing-Quan Pan, Xiaojing Liu (2026). Composite fuel-bundle design for Mo-99 production in CANDU reactors using natural molybdenum. Nuclear Engineering and Design.DOI
Jian Li, Qing-Quan Pan, Xiaojing Liu (2026). Co-production of Fission-Activation methods for Mo-99. Annals of Nuclear Energy.DOI
Yue-Hang Li, D. He, Xiaojing Liu, Qing-Quan Pan (2026). Verification of the Transient Fission Matrix Combination Method in the C5G7-TD Benchmark.DOI
Qing-Quan Pan, Lian-Jie Wang, Bang-Yang Xia, Yun Cai, Xiaojing Liu (2026). Conceptual design of an ultra-high flux fast reactor with strong irradiation capability. Science China Technological Sciences.DOI
Honglong Li, Xinxiang Long, Yunxin Zhang, D. He, Xiaojing Liu (2026). The validation of fission response function neutron transport code FLASH in AP1000 reactor core. Nuclear Engineering and Design.DOI
Lv Guo, Qingquan Pan, Xiaojing Liu (2026). Neutron spectrum optimization for reactor-based production of Ac-225 and impurity control. Nuclear Engineering and Technology.DOI
Guangchao Yang, Xinzhong Zhou, Xiaojing Liu, Jinbiao Xiong, Xiang Chai, Tengfei Zhang, Hui Zhu He (2026). Reverse design of fluid-solid interfacial bumps for passive heat transfer enhancement. Communications Engineering.DOI
Longchang Tang, Wei Xu, Yan Liu, Xiaojing Liu (2026). Experimental study on the influence of epoxy patterns of bi-conductive surfaces on Pool boiling. Nuclear Engineering and Design.DOI
Meiqi Song, Yunzhi Shi, Guiying Li, Haozhe Li, Wei Xu, Xiaojing Liu (2026). Development of a multi-fluid and multi-condition heat transfer model for supercritical fluids based on incremental learning. Annals of Nuclear Energy.DOI
Shuning Chen, Zhu Liu, Teng Zhang, Lang Wang, Wei Tian, Wen Su, Wei Liu, Xiaojing Liu (2026). Dynamic mode decomposition for multi-cycle burnup distribution prediction in the high-temperature gas-cooled reactor. Nuclear Engineering and Design.DOI
Yingying Huo, Qing Yang, Xiaojing Liu (2026). Natural Convection Heat Transfer Analysis With Different DHX Operation Conditions of Sodium‐Cooled Fast Reactor Using ATHLET Code. Science and Technology of Nuclear Installations.DOI
Xiao Xiao, Meiqi Song, Xiaojing Liu (2025). A reliable and adaptive prediction framework for nuclear power plant system through an improved Transformer model and Bayesian uncertainty analysis. Reliability Engineering & System Safety, Vol. 261.DOI
Qing-Quan Pan, Liao-Yuan He, Xiaojing Liu (2025). Pointing Probability Driven Semi-Analytic Monte Carlo Method (PDMC) - Part II: Correction of Exponential Approximation for Higher Accuracy. Computer Physics Communications.DOI
Dongyuan Li, Qing-Quan Pan, Xiaojing Liu (2025). High-Resolution Rapid Calculation Method of Neutron Spectrum based on Energy Response. Nuclear Engineering and Technology.DOI
Qing-Quan Pan, Xiaojing Liu, Yun Cai (2025). Optimal Neutron Spectrum Database for In‐reactor 238Pu Production. Advancement of science.DOI
Dongyuan Li, Qing-Quan Pan, Xiaojing Liu (2025). Independent Nuclide Simulation Method (INSM) – A depletion algorithm for simulating the intermediate process of nuclide transmutation. Progress in nuclear energy (New series).DOI
Dongyuan Li, Qing-Quan Pan, Lian-Jie Wang, Bang-Yang Xia, Yun Cai, Xiaojing Liu (2025). Bidirectional transmutation method for optimal reactor radionuclide production. Annals of Nuclear Energy.DOI
Yun-Geng Li, Qing-Quan Pan, Xiaojing Liu (2025). Reactor multi-physics internal coupling method based on STL unified dynamic mesh. Annals of Nuclear Energy.DOI
D. He, Honglong Li, Ruishuang Gao, Yue-Hang Li, Li-Jian Fan, Xinxiang Long, Xiaojing Liu (2025). INSL-FLASH: A Fission Response Function Based Low-Cost Adaptive Reactor Physics Code for High-Fidelity Simulation. Nuclear science and engineering.DOI
Yunzhi Shi, Meiqi Song, Hongtao Bi, Wei Xu, Xiaojing Liu (2025). Hybrid symbolic regression for data-driven discovery: Governing dimensionless numbers in supercritical heat transfer. Energy.DOI
Guangchao Yang, Xiaojing Liu, Decao Wu, Jinbiao Xiong, Tengfei Zhang, Xiang Chai, Hui Zhu He (2025). Study on the photoacoustic method for accurate, online, in-situ, non-contact measurement of corrosion-related unidentified deposit thickness. Nuclear Engineering and Design.DOI
Hongtao Bi, Meiqi Song, Tengfei Zhang, Xiaojing Liu (2025). FC-PINNs: Physics-informed neural networks for solving neutron diffusion eigenvalue problem with interface considerations. Journal of Computational Physics.DOI
Kangkang Jin, Shiwei Wang, Xiaojing Liu, Tengfei Zhang, Xiang Chai, Hui Zhu He (2025). Numerical simulation of grid-to-rod fretting wear coupling with fuel properties during burnup. Annals of Nuclear Energy.DOI
Yunzhi Shi, Meiqi Song, Haozhe Li, Xiaojing Liu (2025). Research on near-critical/trans-critical flow and heat transfer in engineering applications: A review. Renewable and Sustainable Energy Reviews.DOI
Yu Xing, Jiaqiang Wang, Shizhu Cui, Xiaojing Liu, Meiqi Song (2025). Interpretable Bayesian-optimized Autoencoder for fault detection and diagnosis with application in nuclear power plants. Progress in Nuclear Energy.DOI
Chuandong Liu, Yan Liu, Hui Zhu He, Tengfei Zhang, Xiaojing Liu (2025). Critical heat flux on boiling induced self-assembly surfaces. International Journal of Heat and Mass Transfer.DOI
Jian Hao Zhou, Wei Da Xu, Ningkang Zhao, Xiaojing Liu (2025). The radiation-induced effects on the surface structure, wettability and boiling characteristics of heat transfer surfaces: a review. Annals of Nuclear Energy.DOI
Yanjie Tuo, Houde Song, Xiao Xiao, Meiqi Song, Xiaojing Liu (2025). Application of data-driven modeling and calibration methods in nuclear power plant prognosis digital twins. Annals of Nuclear Energy.DOI
Kangkang Jin, Xiaojing Liu, Jinbiao Xiong, Xiang Chai, Hui He (2025). On the Factors Affecting the Flow-Induced Vibration Characteristics of PWR Fuel Assemblies. Springer proceedings in physics.DOI
Shiwei Wang, Jiajie Chen, Xiaojing Liu, Tengfei Zhang, Xiang Chai, Qi Lu, Danhong Shen, Hui Zhu He (2025). Kriging to Kolmogorov-Arnold Network model accelerated discovery of oxygen control strategy in lead-based fast reactors. Nature Communications.DOI
Chixu Luo, Sicheng Wang, Xiaojing Liu, Xiang Chai, Hui Zhu He, Tengfei Zhang (2025). Sensor Placement Optimization and Online Power Reconstruction in Nuclear Reactors via Hyper-Reduction. IEEE Sensors Journal.DOI
Wei Da Xu, Ningkang Zhao, Meiqi Song, Xiaojing Liu (2025). Surface Modification of Zirconium Alloy with Nanocrystalline Diamond: Enhancing Quenching Performance for Accident Tolerant Fuel. Small.DOI
Tian-Shi Wang, Jinyu Wang, Zhongchun Li, Dongchuan Su, Xiang Chai, Jiaolong Deng, Hui Zhu He, Tengfei Zhang, Xiaojing Liu (2025). Experimental investigation on flow and heat transfer characteristics of high temperature helium-xenon mixture in monoblock fuel element. International Journal of Heat and Mass Transfer.DOI
Chaoyuan Zhang, Han Yin, Yan Liu, Hui Zhu He, Xiaojing Liu, Tengfei Zhang, Sicheng Wang (2025). High-Resolution Multiphysics Analysis of CRUD Effects in Reactor Assemblies. PRX Energy.DOI
Haoyu Yin, Xiaojing Liu, Xiang Chai, Hui Zhu He, Lianjie Wang, Bin Zhang, Tengfei Zhang (2025). A numerical stabilization model for the half-boundary method in solving heat conduction problems. Annals of Nuclear Energy.DOI
Xiang Chai, Xinyue Liu, Chaoran Guan, Xiaojing Liu, Tengfei Zhang, Hui Zhu He (2025). Conceptual design of small innovative helium-xenon cooled mobile nuclear power system. Nuclear Engineering and Design.DOI
Qingquan Pan, Lianjie Wang, Bangyang Xia, Yun Cai, Xiaojing Liu (2025). High-resolution neutron spectrum regulation for promoting transuranic isotope production. Nuclear Science and Techniques.DOI
Lin Zhang, Chang Deng, Xu Ji, Xiaojing Liu (2025). Liquid metals power advanced nuclear energy systems. The Innovation.DOI
Hui Zhu He, Yan Liu, Yan Liu, Shiwei Wang, Tengfei Zhang, Xiang Chai, Xiaojing Liu (2025). Review on corrosion-related unidentified deposit of pressurized water reactors. Nuclear Engineering and Design.DOI
Meiqi Song, Haozhe Li, Zuokai Chen, Xiang Chai, Xu We, Xiaojing Liu (2025). Analysis of space nuclear reactor under accident conditions with CFD simulation and interpretable machine learning algorithm. Annals of Nuclear Energy.DOI
Long Fei Ji, Xiaojing Liu, Wei Da Xu, Wei Zeng, Jie Wang, Hui Zhu He (2025). Experimental investigation on quenching behavior across spacer grid during reflooding transient. Nuclear Engineering and Design.DOI
Junda Zhang, Junda Zhang, Y. Chen, Xiaojing Liu, Xiang Chai, Hui Zhu He, Jinbiao Xiong, Tengfei Zhang (2025). Optimizing thermal stress distribution in heat-pipe-cooled microreactors using multi-physics data-driven methods. Energy.DOI
Fukun Chen, Qingyu Huang, Meiqi Song, Xiaojing Liu, Wei Zeng, Houde Song, Kun Cheng (2025). A study on the development of digital model of digital twin in nuclear power plant based on a hybrid physics and data-driven approach. Applied Thermal Engineering.DOI
Xuan Zhang, Meiqi Song, Xiao Xiao, Xiaojing Liu (2025). EXP-Transformer time series prediction model for accident scenarios in high-reliability energy systems: Nuclear power plants case. Energy.DOI
Long Fei Ji, Minglin Ma, Xiaojing Liu, Xiang Chai, Tengfei Zhang, Hui Zhu He (2025). Experimental investigation of the coupling interaction between nucleate boiling and boric acid migration. Applied Thermal Engineering.DOI
Xinyu Li, Chaoran Guan, Xiang Chai, Xiaojing Liu (2025). Study on the load-following ability of HeXe cooled SMR with close Brayton cycle for renewable energy integration. Energy.DOI
Yun-Geng Li, Qing-Quan Pan, Yi Han, Xiaojing Liu (2024). CAD/CSG dual-layer hybrid geometric Monte Carlo particle transport method. Annals of Nuclear Energy.DOI
D. He, Ruishuang Gao, Honglong Li, Qing-Quan Pan, Xiaojing Liu (2024). The development of a high-performance combined fission matrix neutron transport and depletion coupled calculation. Progress in nuclear energy (New series).DOI
Yue-Hang Li, D. He, Qing-Quan Pan, Xiaojing Liu (2024). Development and verification of the transient fission matrix combination method for the efficient neutron kinetic simulations. Progress in nuclear energy (New series).DOI
Qing-Quan Pan, Xiaojing Liu, Yi Xia, Guohua Wang (2024). Spectrum Importance Model for Heavy Nuclei Synthesis in Reactors: Taking 252Cf as an Example. Nuclear Engineering and Technology.DOI
Yu Xin, Qing-Quan Pan, Lian-Jie Wang, Bang-Yang Xia, Yun Cai, Xiaojing Liu, Jin-Biao Xiong (2024). Neutron single-flow method for efficient production of Cf-252 in high-flux fast reactor. Nuclear Engineering and Design.DOI
Yue-Hang Li, D. He, Xiaojing Liu (2024). Application of Combined Fission Matrix to Plate-type Research Reactor. EPJ Web of Conferences.DOI
Qing-Quan Pan, Song-Chuan Zheng, Xiaojing Liu (2024). Deep-coupling neural network and genetic algorithm based on Sobol-PR for reactor lightweight optimization. Applied Soft Computing.DOI
D. He, Yue-Hang Li, Qing-Quan Pan, Xiaojing Liu (2024). Development of a Predictor-Corrector Quasi-Static Transient Fission Matrix combination method for the neutronics transient simulation. Nuclear Engineering and Design.DOI
Yun-Geng Li, Qing-Quan Pan, Xiaojing Liu, Jin-Biao Xiong (2024). Monte Carlo CAD geometric transport acceleration method based on octree neighbor searching. Nuclear Engineering and Design.DOI
Song-Chuan Zheng, Qing-Quan Pan, D. He, Xiaojing Liu (2024). Reactor lightweight shielding optimization method based on parallel embedded genetic particle-swarm hybrid algorithm. Progress in nuclear energy (New series).DOI
Yanjie Tuo, Xiaojing Liu (2024). Predicting nuclear power plant operational parameters using clustering and mutual information for feature selection and Transformer neural network optimized by TPE. Frontiers in Energy Research.DOI
Wei Xiao, Xiaojing Liu, Jianhua Zu, Xiang Chai, Hui Zhu He, Tengfei Zhang (2024). Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method. Nuclear Science and Engineering.DOI
Haozhe Li, Meiqi Song, Xiaojing Liu (2024). Interpretable machine learning-based prediction and analysis of supercritical fluid heat transfer characteristics at different boundary conditions. Energy.DOI
Yan Liu, Xiaojing Liu, Hui Zhu He, Tengfei Zhang, Xiang Chai (2024). Study on Thermal Conductivity Model for Porous PWR CRUD Depositions.DOI
Chaoran Guan, Xiang Chai, Tengfei Zhang, Xiaojing Liu (2024). Design of a He-Xe Gas-Cooled Nuclear Microreactor System Based on Detailed Models of the Cycle Components.DOI
Yanjie Tuo, Xiaojing Liu (2024). Enhancing Nuclear Power Plant Operational Forecasting With Transformer Neural Networks: a Time-Series Data Approach.DOI
Wei Xiao, Xiaojing Liu, Jianhua Zu, Xiang Chai, Hui He, Tengfei Zhang (2024). Operator inference driven data assimilation for high fidelity neutron transport. Computer Methods in Applied Mechanics and Engineering.DOI
Qizheng Sun, Xiaojing Liu, Xiang Chai, Hui He, Tengfei Zhang (2024). A discrete-ordinates variational nodal method for heterogeneous neutron Boltzmann transport problems. Computers & Mathematics with Applications.DOI
Xu Cheng, Xiaojing Liu, H Gu (2024). Fluid-to-Fluid Scaling of Heat Transfer in Supercritical Fluids. Canadian Nuclear Society Proceedings.DOI
Qizheng Sun, Xiaojing Liu, Xiang Chai, Hui Zhu He, Lianjie Wang, Bin Zhang, Tengfei Zhang (2024). Hybrid discontinuous Galerkin method for the hyperbolic linear Boltzmann transport equation for multiscale problems. Physical review. E.DOI
Jiaolong Deng, Chaoran Guan, Xiaojing Liu, Xiang Chai (2024). Dynamic Modeling of a HeXe-Cooled Mobile Nuclear Reactor with Closed Brayton Cycle. Energies.DOI
Chaoran Guan, Xiang Chai, Tengfei Zhang, Hui Zhu He, Xiaojing Liu (2024). Design optimization and performance analysis of a dry-cooled Helium-Xenon Brayton cycle for nuclear microreactor based on detailed models of the cycle components. Applied Thermal Engineering.DOI
Chixu Luo, Mingrui Yang, Qing Zhu, Chaoyuan Zhang, Xiaojing Liu, Tengfei Zhang (2024). Neutronics analysis of a research reactor using a two-step method with the superhomogenization method. Annals of Nuclear Energy.DOI
Xu Ji, Xiaojing Liu, Tengfei Zhang, Hui Zhu He (2024). Numerical investigation on the Multi-Physics coupling characteristics of Lead-Bismuth reactor fuel assembly based on oxidation corrosion behaviors. Nuclear Engineering and Design.DOI
Longchang Tang, Xiaojing Liu, Wei Xu, Luyao Tang (2024). Pool Boiling Heat Transfer Enhancement Using Bi-Conductive Surfaces.DOI
Han Yin, Tengfei Zhang, Xiaojing Liu (2024). Research and Preliminary Verification of the Resonance Self-Shielding Calculation Method for the High-Fidelity Neutronics Code VITAS.DOI
Chixu Luo, Zikang Li, Haoyu Yin, Lianjie Wang, Bin Zhang, Bin Zhang, Xiaojing Liu, Xiang Chai, Hui Zhu He, Tengfei Zhang (2024). Application of full-core three-dimensional multi-physics calculation to the EBR-II SHRT-45R benchmark. Annals of Nuclear Energy.DOI
Xiao Xiao, Xuan Zhang, Meiqi Song, Xiaojing Liu, Qingyu Huang (2024). NPP accident prevention: Integrated neural network for coupled multivariate time series prediction based on PSO and its application under uncertainty analysis for NPP data. Energy.DOI
Tengfei Zhang, Qizheng Sun, Wei Xiao, Chixu Luo, Xiaojing Liu (2024). A review on emerging mixed-spectrum nuclear reactors for safety and sustainability of nuclear energy systems. Renewable and Sustainable Energy Reviews.DOI
Jiaolong Deng, Chaoran Guan, Yujie Sun, Xiaojing Liu, Tengfei Zhang, Hui Zhu He, Xiang Chai (2024). Techno-economic analysis and dynamic performance evaluation of an integrated green concept based on concentrating solar power and a transportable heat pipe-cooled nuclear reactor. Energy.DOI
Qiuxia Xie, Xiang Chai, Xiaojing Liu (2024). Multi-physical coupling study of neutronics/thermal-hydraulics/material corrosion based on the unified coupling framework. Nuclear Engineering and Design.DOI
Jiaolong Deng, Chaoran Guan, Tianshi Wang, Xiaojing Liu, Xiang Chai (2024). Evaluation of start-up characteristics for heat pipe-cooled nuclear reactor coupled with recuperated open-air brayton cycle using hardware-in-the-loop. Energy.DOI
Qingquan Pan, Qing-Fei Zhao, Lianjie Wang, Bangyang Xia, Yun Cai, Jinbiao Xiong, Xiaojing Liu (2024). High-resolution neutronics model for 238Pu production in high-flux reactors. Nuclear Science and Techniques.DOI
Chaoran Guan, Xiang Chai, Tengfei Zhang, Xiaojing Liu, Hui Zhu He (2024). The investigation of thermo-economic performance for dry-cooled closed Brayton cycle coupled to nuclear microreactors using different coolants. Journal of Cleaner Production.DOI
Long Fei Ji, Xiaojing Liu, Xiang Chai, Tengfei Zhang, Hui Zhu He (2024). Experimental investigation of local boron concentration in a 2 × 2 rod bundle channel under subcooled boiling flow. Nuclear Engineering and Design.DOI
Shiwei Wang, Jiajie Chen, Xiaojing Liu, Tengfei Zhang, Xiang Chai, Hui Zhu He (2024). Multi-physical effects induced by spatiotemporal corrosion of T91 cladding in oxygen-controlled LBE environment. Corrosion Science.DOI
Han Yin, Xiaojing Liu, Tengfei Zhang (2024). An efficient parallel algorithm of variational nodal method for heterogeneous neutron transport problems. Nuclear Science and Techniques.DOI
Shiwei Wang, Xiaojing Liu, Xiang Chai, Tengfei Zhang, Hui Zhu He (2024). CRUD deposition induced multi-physics effects analysis in PWR. Nuclear Engineering and Design.DOI
Derjew Ayele Ejigu, Yanjie Tuo, Xiaojing Liu (2024). Application of artificial intelligence technologies and big data computing for nuclear power plants control: a review. Frontiers in Nuclear Engineering.DOI
Guolian Wang, Yan Liu, Xiaojing Liu, Xiaojing Liu, Hui Zhu He (2024). Study on coupling effect of CRUD growth and heat transfer on fuel rod. International Journal of Thermal Sciences.DOI
Yan Liu, Xiaojing Liu, Tengfei Zhang, Hui Zhu He (2024). Understanding Flow Fouling Deposition and Solute Hideout–Return Behavior at the Phase Change Interface. ACS Applied Materials & Interfaces.DOI
Yan Liu, Xiaojing Liu, Hui Zhu He, Tengfei Zhang, Xiang Chai (2024). Synthesizing nuclear power plant fouling with fractal characteristics enables an in-depth study of concerned nuclear safety issues. iScience.DOI
Qing-Fei Zhao, Qing-Quan Pan, Lian-Jie Wang, Bang-Yang Xia, Yun Cai, Xiaojing Liu, Jin-Biao Xiong (2023). Neutron spectrum optimization for Cf-252 production based on key nuclides analysis. Radiation Physics and Chemistry.DOI
Qing-Quan Pan, Huan-Wen Lv, Song-Qian Tang, Xiaojing Liu (2023). MAGIC-GPS global variance reduction method for large-scale shielding calculation. Nuclear Engineering and Design.DOI
Xiang Chai, Xinyue Liu, Chaoran Guan, Tengfei Zhang, Xiaojing Liu (2023). Investigation of reactivity control strategies for a micro-transportable gas-cooled thermal reactor. Nuclear Engineering and Design.DOI
Jiaolong Deng, Tian-Shi Wang, Enping Zhu, Shujian Yuan, Xiaojing Liu, Xiang Chai (2023). Dynamic evaluation of a scaled-down heat pipe-cooled system during start-up/shut-down processes using a hardware-in-the-loop test approach. Nuclear Science and Techniques.DOI
Lin Zhang, Chang Deng, Xiaojing Liu (2023). Experimental investigation on the interaction characteristics of lead‑bismuth liquid metal and water. International Communications in Heat and Mass Transfer.DOI
Qingquan Pan, Lianjie Wang, Yun Cai, Xiaojing Liu, Jinbiao Xiong (2023). Density-extrapolation Global Variance Reduction (DeGVR) method for large-scale radiation field calculation. Computers & Mathematics with Applications.DOI
Houde Song, Xiaojing Liu, Meiqi Song (2023). Comparative study of data-driven and model-driven approaches in prediction of nuclear power plants operating parameters. Applied Energy.DOI
Qing Yang, Qingquan Pan, Xiaojing Liu (2023). Analysis of lead–bismuth eutectic-cooled solid reactor under flow blockage accident by 3D neutronics thermal-hydraulics coupling method. Nuclear Engineering and Design.DOI
Tao Li, Jinbiao Xiong, Tengfei Zhang, Xiang Chai, Xiaojing Liu (2023). Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system. Annals of Nuclear Energy.DOI
Qingquan Pan, Qing-Fei Zhao, Lianjie Wang, Bangyang Xia, Yun Cai, Xiaojing Liu (2023). Rapid diagnostic method for transplutonium isotope production in high flux reactors. Nuclear Science and Techniques.DOI
Meiqi Song, Xiaojing Liu, Cheng Xu (2023). Modelling and experimental validation of heat transfer behavior during trans-critical transients. Annals of Nuclear Energy.DOI
Qizheng Sun, Wei Xiao, Xiangyue Li, Han Yin, Tengfei Zhang, Xiaojing Liu (2023). A variational nodal formulation for multi-dimensional unstructured neutron diffusion problems. Nuclear Engineering and Technology.DOI
Wei Xiao, Han Yin, Xiaojing Liu, Hui He, Tengfei Zhang (2023). On the transient models of the VITAS code: applications to the C5G7-TD pin-resolved benchmark problem. Nuclear Science and Techniques.DOI
Qiuxia Xie, Wei Li, Chaoran Guan, Qizheng Sun, Xiang Chai, Xiaojing Liu (2023). Development of 3D transient neutronics and thermal-hydraulics coupling procedure and its application to a fuel pin analysis. Nuclear Engineering and Design.DOI
Wei Li, Qiuxia Xie, Qingquan Pan, Tengfei Zhang, Xiang Chai, Xiaojing Liu (2023). A multi-region algorithm for N-TH coupling calculation and its application to nuclear thermal propulsion reactor. Annals of Nuclear Energy.DOI
Xiangyue Li, Xiaojing Liu, Xiang Chai, Hui Zhu He, Bin Zhang, Tengfei Zhang (2023). Multi-physics coupling simulation of small mobile nuclear reactor with finite element-based models. Computer Physics Communications.DOI
Mingrui Yang, Chixu Luo, Dan Wang, Tianxiong Wang, Xiaojing Liu, Tengfei Zhang (2023). Development and Preliminary Verification of a Neutronics-Thermal Hydraulics Coupling Code for Research Reactors with Unstructured Meshes. Springer proceedings in physics.DOI
Chaoran Guan, Xiang Chai, Tengfei Zhang, Xiaojing Liu, Hui Zhu He (2023). Mass and efficiency optimization of a He-Xe Brayton cycle for mobile, land-based nuclear microreactors. Energy Conversion and Management.DOI
Lin Zhang, Chang Deng, Xiaojing Liu (2023). Energy transfer and interaction between liquid metal with water. Energy.DOI
Lin Zhang, Chang Deng, Xiaojing Liu (2023). Bubble fragmentation characteristics during the injection of subcooled water jet into hot liquid pool. International Journal of Heat and Mass Transfer.DOI
Long Fei Ji, Tingpu Ye, Xiaojing Liu, Hui Zhu He (2023). Experimental investigation on distribution of boric acid in a vertical 1 × 2 rod array channel. Nuclear Engineering and Design.DOI
Qiuxia Xie, Xiang Chai, Xiaojing Liu (2023). Steady-state and transient simulations of the MTR research reactor using the high-fidelity N-TH coupling method. Progress in Nuclear Energy.DOI
Junda Zhang, Tao Li, Zhirui Shen, Xiangyue Li, Jinbiao Xiong, Xiang Chai, Xiaojing Liu, Tengfei Zhang (2023). Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches. Nuclear Science and Engineering.DOI
Qing Yang, Qingquan Pan, Xiaojing Liu (2023). Burnup-control drum coupling characteristics investigation of lead–bismuth eutectic-cooled solid reactor. Annals of Nuclear Energy.DOI
Qingquan Pan, Huanwen Lv, Songqian Tang, Jinbiao Xiong, Xiaojing Liu (2023). Pointing probability Driven semi-analytic Monte Carlo Method (PDMC) – Part I: Global variance reduction for large-scale radiation transport analysis. Computer Physics Communications.DOI
Jiaolong Deng, Tianshi Wang, Xiaojing Liu, Tengfei Zhang, Hui Zhu He, Xiang Chai (2023). Experimental study on transient heat transfer performance of high temperature heat pipe under temperature feedback heating mode for micro nuclear reactor applications. Applied Thermal Engineering.DOI
Cheng Xu, Xiaojing Liu (2023). Some recent progress in reactor core thermal-hydraulics modelling. Nuclear Engineering and Design.DOI
Derjew Ayele Ejigu, Xiaojing Liu (2023). Predictive modeling of pressurized water reactor transients using nonlinear autoregressive with exogenous input neural network. Progress in Nuclear Energy.DOI
Qingquan Pan, Yun Cai, Lianjie Wang, Xiaojing Liu, Hui Xia He, Kan Wang (2022). Improved Wielandt method with real-time error tolerance based on NLSP3 code. Annals of Nuclear Energy.DOI
Donghao He, Yuehang Li, Tengfei Zhang, Xiaojing Liu (2022). The development of the combined fission matrix method in small advanced reactor design and optimization. Annals of Nuclear Energy.DOI
Houde Song, Meiqi Song, Xiaojing Liu (2022). Online autonomous calibration of digital twins using machine learning with application to nuclear power plants. Applied Energy.DOI
Qing Yang, Qingquan Pan, Hui Xia He, Tengfei Zhang, Xiaojing Liu (2022). Improved design of LBE cooled solid reactor using 3D neutronics thermal-hydraulics coupling method. Annals of Nuclear Energy.DOI
Wei Li, Chaoran Guan, Houde Song, Xiang Chai, Xiaojing Liu (2022). Numerical investigation of heat transfer characteristics of moderator assembly employed in a low-enriched uranium nuclear thermal propulsion reactor. Frontiers in Energy Research.DOI
Qizheng Sun, Tengfei Zhang, Xiaojing Liu, Xiang Chai, Jinbiao Xiong (2022). A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh.DOI
Tengfei Zhang, Wei Xiao, Han Yin, Qizheng Sun, Xiaojing Liu (2022). VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods. Annals of Nuclear Energy.DOI
Wei Xiao, Qizheng Sun, Xiaojing Liu, Hui He, Donghao He, Qingquan Pan, Tengfei Zhang (2022). Application of stiffness confinement method within variational nodal method for solving time-dependent neutron transport equation. Computer Physics Communications.DOI
Qingquan Pan, Nan An, Tengfei Zhang, Xiaojing Liu, Yun Cai, Lianjie Wang, Kan Wang (2022). Single-step Monte Carlo criticality algorithm. Computer Physics Communications.DOI
Derjew Ayele Ejigu, Xiaojing Liu (2022). Dynamic modeling and intelligent hybrid control of pressurized water reactor NPP power transient operation. Annals of Nuclear Energy.DOI
Derjew Ayele Ejigu, Xiaojing Liu (2022). Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation. Nuclear Science and Engineering.DOI
Xiang Chai, Chaoran Guan, Jiaolong Deng, Tengfei Zhang, Xiaojing Liu (2022). Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe. Annals of Nuclear Energy.DOI
Jiaolong Deng, Xiang Chai, Tengfei Zhang, Xiaojing Liu (2022). Conceptual Multi-Physic Coupling Simulation on Transient Operations Of a He-Xe Cooled Mobile Nuclear Power Plant.DOI
Wei Xiao, Tengfei Zhang, Xiaojing Liu, Donghao He, Qingquan Pan (2022). Application of Stiffness Confinement Method on Pin Resolved Variational Nodal Method and Its Implementation to C5G7-TD Benchmark Problem.DOI
Yuanli Sun, Zhihao Song, Houde Song, Xiaojing Liu, Hui Zhu He (2022). Experimental Study on Statistical Properties of Two-Phase Flow Instability for Boiling.DOI
Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui Zhu He, Tengfei Zhang (2022). 3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core.DOI
Lin Zhang, Hanzhou Liu, Xiaojing Liu, Deqi Chen (2022). Prediction of sliding bubble coalescence rate during subcooled flow boiling in narrow rectangular channel. International Journal of Heat and Mass Transfer.DOI
Chaoran Guan, Xiang Chai, Tengfei Zhang, Xiaojing Liu (2022). Preliminary lightweight core design analysis of a micro‐transportable gas‐cooled thermal reactor. International Journal of Energy Research.DOI
Chaoran Guan, Xiang Chai, Tengfei Zhang, Xiaojing Liu (2022). Transient coupling analysis of loss-of-coolant accidents in HTR-PM based on CFD approaches. Annals of Nuclear Energy.DOI
Meiqi Song, Xiaojing Liu, Cheng Xu (2022). A new correlation for post-dryout heat transfer in upward vertical flow. Nuclear Engineering and Design.DOI
Hui Zhu He, Xiaojing Liu, Qingquan Pan, Qi Lu, Quan-yao Ren, Liangming Pan (2022). Experimental and theoretical study on formation of interfacial waves on liquid film of annular two-phase flow. Nuclear Engineering and Design.DOI
Qing Yang, Qizheng Sun, Xiaojing Liu, Hui Zhu He, Tengfei Zhang, Xiang Chai, Yuejian Luo (2022). Conceptual design and thermal-hydraulic analysis of a megawatt-level lead-bismuth cooling reactor for deep-sea exploration. Progress in Nuclear Energy.DOI
Han Yin, Tengfei Zhang, Donghao He, Xiaojing Liu (2022). A quasi-transport integral variational nodal method for homogeneous nodes based on the 2D/1D method. Computer Physics Communications.DOI
Derjew Ayele Ejigu, Xiaojing Liu (2021). Gradient descent-particle swarm optimization based deep neural network predictive control of pressurized water reactor power. Progress in Nuclear Energy.DOI
Donghao He, Tengfei Zhang, Xiaojing Liu (2021). The Application of the Combined Fission Matrix Theory in Fast Reactors. Frontiers in Energy Research.DOI
Wei Da Xu, Kun Ouyang, Jiuyuan Guo, Hui Zhu He, Xiaoqiang He, Xiaojing Liu (2021). Experimental and numerical investigations on heat transfer and flow behavior of flow blockage in narrow rectangular channel with protrusions. Applied Thermal Engineering.DOI
Meiqi Song, Xiaojing Liu (2021). Assessment of CHF and Post-CHF Heat Transfer Models for High-Pressure Condition. Frontiers in Energy Research.DOI
Danwei Zhang, Win Jonhson, Tun Seng Herng, Xi Xu, Xiaojing Liu, Liangming Pan, Hui Zhu He, Jun Ding (2021). High temperature co-firing of 3D-printed AlZnO/Al2O3 multi-material two-phase flow sensor. Journal of Materiomics.DOI
Qingquan Pan, Teng-Fei Zhang, Xiaojing Liu, Hui Zhu He, Kan Wang (2021). SP3-coupled global variance reduction method based on RMC code. Nuclear Science and Techniques.DOI
Qingquan Pan, Yun Cai, Lianjie Wang, Tengfei Zhang, Xiaojing Liu, Kan Wang (2021). Source extrapolation scheme for Monte Carlo fission source convergence based on RMC code. Annals of Nuclear Energy.DOI
Qingquan Pan, Tengfei Zhang, Xiaojing Liu, Yun Cai, Lianjie Wang, Kan Wang (2021). Optimal Batch Size Growth for Wielandt Method and Superhistory Method. Nuclear Science and Engineering.DOI
Wei Xiao, Xiangyue Li, Peijie Li, Tengfei Zhang, Xiaojing Liu (2021). High-fidelity multi-physics coupling study on advanced heat pipe reactor. Computer Physics Communications.DOI
Tengfei Zhang, Han Yin, Xiangyue Li, Ding She, Qingquan Pan, Donghao He, Xiaojing Liu (2021). Studies on calculation models of ASTRA critical facility benchmark using OpenMC. Annals of Nuclear Energy.DOI
Meiqi Song, Xiaojing Liu, Cheng Xu (2021). Prediction of critical heat flux (CHF) for the high-pressure region in uniformly heated vertical round tubes. Annals of Nuclear Energy.DOI
Wei Da Xu, Yonghao Deng, Dan T-c Wu, Jiuyuan Guo, Shuhua Ding, Xiaojing Liu (2021). Experimental study on combined reflooding phenomenon and RELAP5 simulation analysis in narrow rectangular channel. Nuclear Engineering and Design.DOI
Wei Da Xu, Yonghao Deng, Xiaojing Liu, Cheng Xu, Dan Wu (2020). Mechanism research of two-phase flow regimes during bottom reflooding in narrow rectangular channel. Annals of Nuclear Energy.DOI
Dongmei Yang, Xiaojing Liu, Tengfei Zhang, Cheng Xu (2020). A comparison of three algorithms applied in thermal-hydraulics and neutronics codes coupling for lbe-cooled fast reactor. Annals of Nuclear Energy.DOI
Xiang Chai, Wei Li, Bin Chen, Xiaojing Liu, Jinbiao Xiong, Cheng Xu (2020). Numerical simulation of turbulent natural convection in an enclosure with a curved surface heated from below. Progress in Nuclear Energy.DOI
Jinbiao Xiong, Wenhai Qu, Tengfei Zhang, Xiang Chai, Xiaojing Liu, Yanhua Yang (2020). Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly. Annals of Nuclear Energy.DOI
Tengfei Zhang, Xiaojing Liu, Jinbiao Xiong, Xu Cheng (2020). Comparisons of Reduced Moderation Small Modular Reactors With Heavy Water Coolant. Frontiers in Energy Research.DOI
Xiaojing Liu, Ting Yang, Xiang Chai, Jinbiao Xiong, Tengfei Zhang, Cheng Xu (2019). Preliminary safety analysis for the SCWR‐FQT facility. International Journal of Energy Research.DOI
Xiang Chai, Lei Zhao, Wenjun Hu, Yun Hui Yang, Xiaojing Liu, Jinbiao Xiong, Cheng Xu (2019). Numerical investigation of flow blockage accident in SFR fuel assembly. Nuclear Engineering and Design.DOI
Tengfei Zhang, Jinbiao Xiong, Xiaojing Liu, Xiang Chai, Wei Li, Xu Cheng (2019). Conceptual design of an innovative reduced moderation thorium‐fueled small modular reactor with heavy‐water coolant. International Journal of Energy Research.DOI
Danhong Shen, Xiaojing Liu, Cheng Xu (2019). A study on geometric shape factors for turbulent mixing coefficents in rod bundles. Nuclear Engineering and Design.DOI
Tomasz Skorek, A. de Crécy, Andriy Kovtonyuk, Alessandro PETRUZZI, Rafael Mendizábal, Elsa de Alfonso, Francesc Reventos, Jordi Freixa, Christine Sarrette, Miloš Kynčl, Rostislav Pernica, Jean Baccou, Fabrice Fouet, Pierre Probst, Bub-Dong Chung, Tran Tranh Tram, Deog-Yeon Oh, Alexey Gusev, A. A. Fal’kov, Yuri Shvestov, Dong Li, Xiaojing Liu, Jinzhao Zhang, Torsti Alku, Joona Kurki, Wadim Jäger, Víctor Hugo Sánchez-Espinoza, Damar Wicaksono, Omar Zerkak, Andreas Pautz (2019). Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark. Nuclear Engineering and Design.DOI
Xiang Chai, Xiaojing Liu, Jinbiao Xiong, Cheng Xu (2019). Numerical investigation of thermal-hydraulic behaviors in a LBE-cooled 19-pin wire-wrapped rod bundle. Progress in Nuclear Energy.DOI
Wei Da Xu, Jiuyuan Guo, Xiaojing Liu, Jinbiao Xiong, Xiang Chai, Tengfei Zhang, Cheng Xu, Wei Zeng (2019). Predictions of quench temperature and quench velocity in narrow rectangular channel of novel plate-type reactor. Annals of Nuclear Energy.DOI
Shengzhe Li, Dongmei Yang, Tengfei Zhang, Xiaojing Liu (2019). A Combined Method for Predicting the Boron Deposited Mass and the CIPS Risk. Science and Technology of Nuclear Installations.DOI
Xiaojing Liu, Qi Wang, Zhaozhong He, Kun Chen, Cheng Xu (2019). Phenomena identification and ranking table exercise for thorium based molten salt reactor-solid fuel design. Frontiers in Energy.DOI
Xiang Chai, Xiaojing Liu, Jinbiao Xiong, Cheng Xu (2019). CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle. Nuclear Engineering and Design.DOI
Xiaojing Liu, Jinbiao Xiong, X. Cheng (2019). Multi-scale thermal-hydraulics analysis on SCWR fuelqualification test loop. Zhongguo kexue. Wulixue Lixue Tianwenxue.DOI
Dongmei Yang, Xiaojing Liu, Jinbiao Xiong, Xiang Chai, Cheng Xu (2018). Coupling of neutronics and thermal-hydraulics codes for the simulation of reactivity insertion accident for LFR. Progress in Nuclear Energy.DOI
Wei Da Xu, Jianhua Xia, Xiaojing Liu, Cheng Xu, Wei Zeng (2018). Experimental investigation of bottom reflooding and modeling of quench velocity in a narrow rectangular channel. Progress in Nuclear Energy.DOI
Yuejian Luo, Xiaojing Liu, Cheng Xu (2018). IVR-ERVC study of 1700 MW class PWR based on MAAP simulation and coupled analysis. Annals of Nuclear Energy.DOI
ShengZhe Li, Xiaojing Liu (2018). Development of boron tracking and boron hideout (CRUD) model based on subchannel approach. Nuclear Engineering and Design.DOI
Jinbiao Xiong, Ruiqi Cheng, Chuan Jing Lu, Xiang Chai, Xiaojing Liu, Cheng Xu (2018). CFD simulation of swirling flow induced by twist vanes in a rod bundle. Nuclear Engineering and Design.DOI
Yuejian Luo, Xiaojing Liu, Cheng Xu (2018). In- and ex-vessel coupled analysis for in-vessel retention. Progress in Nuclear Energy.DOI
Danhong Shen, Xiaojing Liu, Cheng Xu (2018). A new turbulent mixing modeling approach for sub-channel analysis code. Annals of Nuclear Energy.DOI
Wei Da Xu, Jianhua Xia, Xiaojing Liu, Cheng Xu, Wei Zeng (2018). Study of Bottom Reflooding in a Narrow Rectangular Channel. Nuclear Technology.DOI
Aurelian F. Badea, Meng Zhao, Cheng Xu, F. Feuerstein, Xiaojing Liu (2018). Consistency considerations on a large databank and wide range heat transfer prediction for supercritical water in circular tubes. Nuclear Engineering and Design.DOI
Xiaojing Liu, Yuejian Luo, Zhen Cao, Rui Hong Guo, Cheng Xu (2018). Safety research of IVR-ERVC for advanced water cooled reactor. Energy.DOI
姬建业，许巍，柴翔，刘晓晶，曾未（2017）. 矩形窄通道再淹没现象实验和数值研究. 《核技术》.
宋美琪，刘晓晶，程旭（2017）. 跨临界泄压瞬态传热特性的模型敏感性分析. 《核科学与工程》.
Wei Da Xu, Jun Yao, Jianye Ji, Xiaojing Liu, Cheng Xu, Wei Zeng, Hongxing Yu (2017). Bottom Reflooding Experiments in a Thin Rectangular Channel. Energy Procedia.DOI
Ting Yang, Xiaojing Liu, Cheng Xu (2017). A circumferentially non-uniform fuel model and its application to thermal-hydraulic code. International Journal of Energy Research.DOI
Dong Li, Xiaojing Liu, Yanhua Yang (2017). Investigation of uncertainty quantification method for BE models using MCMC approach and application to assessment with FEBA data. Annals of Nuclear Energy.DOI
Xiaojing Liu, Shuo Ren, Cheng Xu (2016). Development of a transverse mixing model for large scale impulsion phenomenon in tight lattice. Annals of Nuclear Energy.DOI
Dong Li, Xiaojing Liu, Yanhua Yang (2016). Improvement of reflood model in RELAP5 code based on sensitivity analysis. Nuclear Engineering and Design.DOI
Xiang Chai, Xiaojing Liu, Jinbiao Xiong, Cheng Xu (2016). Numerical investigation of bubble wake properties in the moving liquid with LES model. Journal of Nuclear Science and Technology.DOI
Rui Guo, Wei Da Xu, Zhen Cao, Xiaojing Liu, Cheng Xu (2015). A new method to study the transient feasibility of IVR-ERVC strategy. Progress in Nuclear Energy.DOI
Zhen Cao, Xiaojing Liu, Cheng Xu (2015). Accident analysis on supercritical water-cooled reactor during design basis and beyond design-basis condition. Journal of Nuclear Science and Technology.DOI
Zhen Cao, Xiaojing Liu, Cheng Xu (2015). A two dimensional approach for temperature distribution in reactor lower head during severe accident. Annals of Nuclear Energy.DOI
Zidi Wang, Zhen Cao, Xiaojing Liu (2015). Thermal-Hydraulic Analysis of SWAMUP Facility Using ATHLET-SC Code. Frontiers in Energy Research.DOI
Yue Jin, Wei Da Xu, Xiaojing Liu, Cheng Xu (2015). In- and ex-vessel coupled analysis of IVR-ERVC phenomenon for large scale PWR. Annals of Nuclear Energy.DOI
Fei Li, Zhaocan Meng, Xiaojing Liu, Linsen Li, Feng Man Shen, X. Cheng (2015). ICONE23-1046 MODELLING OF LOW-PRESSURE SUBCOOLED FLOW BOILING USING ATHLET CODE. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Xiaojing Liu, Cheng Xu (2009). CORE AND SUB-CHANNEL EVALUATION OF A THERMAL SCWR. Nuclear Engineering and Technology.DOI
Cheng Xu, Xiaojing Liu (2009). The design analysis for a mixed neutron spectrum supercritical water-cooled reactor core. Chinese Journal of Nuclear Science and Engineering.
程旭，刘晓晶（2008）. 超临界水冷堆国内外研发现状与趋势. 《原子能科学技术》.
Xiaojing Liu, Cheng Xu (2008). Steady-state thermal-hydraulic analysis of SCWR assembly. Frontiers of Energy and Power Engineering in China.DOI
Cheng Xu, Xiaojing Liu (2008). Research status and prospect of supercritical water-cooled reactor. Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms.
Hanyang Gu, Cheng Xu, Xiaojing Liu (2008). Numerical Analysis of Thermal-Hydraulic Behavior of Supercritical Water in Vertical Upward/Downward Flow Channels. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition.DOI
Yu Xin, Qing-Quan Pan, Xiaojing Liu. Layered target design method for global spectrum optimization of radioisotope production. Annals of Nuclear Energy.DOI
预印本
Haoyu Yin, Chixu Luo, Tengfei Zhang, Sicheng Wang, Xiaojing Liu (2026). Accelerating the Stiffness Confinement Method through inter-step slope continuity. SSRN Electronic Journal.DOI
Tianhao Rui, Yulin Lan, Zhuangzhuang Ma, Ke Zhang, Linkang Zhong, Congyi Li, Xiaojing Liu, Haibin Zhang (2026). Interfacial Bonding Mechanism of Nife2o4 On M-Zro2 And Α-Cr2O3 Surfaces for CRUD-Resistant Coatings. SSRN Electronic Journal.DOI
Tengfei Zhang, Mingrui Yang, Chixu Luo, Hui Zhu He, Xiang Chai, Xiaojing Liu (2023). Multi-Physics Coupled Analyzes of Research Nuclear Reactors Based on Steady-State and Kinetics Models. SSRN Electronic Journal.DOI
Wei Xu, Kun Ouyang, Yonghao Deng, Xiaojing Liu (2021). Experimental and Mechanical Research on Chf Characteristics During Combined/Bottom Quenching in Narrow Rectangular Channel. SSRN Electronic Journal.DOI
书籍章节
Ruishuang Gao, Xiaojing Liu, Donghao He (2023). The Development of the Combined Fission Matrix Theory in Burnup Calculation. Springer proceedings in physics.DOI