Yinan Zhu, Guifeng Zhu, Rui Yan, Changqing Yu, Shuyang Jia, Haiyan Yu, Ye Dai, Yang Zou (2026). Energy Deposition Mechanism and Distribution Characteristics in a Liquid Fuel Molten Salt Reactor Under a Static Fuel Salt Approximation. Journal of Nuclear Engineering.DOI
Zhenghao Xu, Guifeng Zhu, Shuyang Jia, Liang Chen, Changqing Yu, Yang Zou (2026). Delayed fission γ transport calculation in molten salt reactor experiment considering the precursor migration and deposition. Progress in Nuclear Energy.DOI
Haiyan Yu, Guifeng Zhu, Changqing Yu, Yinan Zhu, Y Sophia Dai, Xuzhong Kang, Rui Yan, X H Yu, Yang Zou (2026). The Impact of Delayed Neutron Precursor Migration on the Activation of Structural Material and Coolant in Molten Salt Reactor Heat Exchangers. Journal of Nuclear Engineering.DOI
Minyu Peng, zj Song, Yuhan Fan, Yang Zou, Yafen Liu, Rui Yan (2026). Preliminary Physical and Thermal Design of a Small Chloride Salt Fast Reactor Based on Transmutation. Energies.DOI
Fangyuan Zhang, Rui Yan, Ye Dai, Yang Zou (2026). Design Optimization of a Prismatic Compact High-Power Molten-Salt Reactor Based on Graphite Lifetime and Fuel Efficiency. Energies.DOI
Shuaiyu Xue, Chong Zhou, Hongxiang Yu, Pinyan Huang, Yang Zou (2026). Transient performance evaluation of passive residual heat removal system in liquid molten salt reactor. Annals of Nuclear Energy.DOI
Honghui Xu, Rui Yan, Yuhan Fan, Naiwen Zhang, Liang Chen, Xuechao Zhao, Yang Zou (2026). A gas-driven passive reactivity control device and its application to heat pipe space nuclear reactor. Progress in Nuclear Energy.DOI
Chenrui Mao, Jian Guo, Yang Zou, Rui Yan (2025). Preliminary Study of Transient Simulations in the MSRE Primary Loop with Modelica/TRANSFORM. Energies.DOI
Jin-Tong Cao, Guifeng Zhu, Changqing Yu, Yafen Liu, Yang Zou, Rui Yan, Hongjie Xu (2025). Conceptual design and preliminary feasibility study of fluid-driven suspended control rods for molten salt reactors. Nuclear Science and Techniques.DOI
Changqing Yu, Guifeng Zhu, Jin-Tong Cao, Yang Zou, Rui Yan, Xiaohan Yu (2025). Extension of the formula between reactivity and concentrations of fissile and non-fissile nuclide in the fuel salt for thermal neutron spectrum molten salt reactors. Nuclear Engineering and Technology.DOI
Xiaolin Liang, Guifeng Zhu, Yang Zou, Ziye Wang, Liang Chen (2025). Numerical simulation of noble metal particles deposition in shell-tube heat exchangers of MSRs based on RSM-DPM model. Nuclear Engineering and Design.DOI
Shuaiyu Xue, Chong Zhou, Pinyan Huang, Yang Zou (2025). Secondary side system design: A new calculation method for passive residual heat removal of liquid fuel molten salt reactors. Annals of Nuclear Energy.DOI
Yang Yang, Yang Zou (2025). Thermal‐Hydraulic Performance and Entropy Generation Analysis of Turbulent Mixed Convection Chloride Salt Absorber Tube. Annalen der Physik.DOI
Zhenghao Xu, Guifeng Zhu, Liang Chen, Shuyang Jia, Changqing Yu, Yunfei Zhang, Yang Zou, Hongjie Xu (2025). The decay heat distribution calculation in molten salt reactor experiment based on the nuclide flow-transfer-burnup coupling method. Progress in Nuclear Energy.DOI
Qi-Ming Li, Yao Fu, Jian Tian, Chong Zhou, Yang Zou, Yuan Fu, Jie Hou, Xiaohan Yu, Hongjie Xu (2025). Experimental heat transfer performance of a drainage-integrated fluoride salt-to-salt heat exchanger. Results in Engineering.DOI
Maoying Xu, Jian Tian, Yali Chen, Chong Zhou, Yang Zou (2025). Research on measurement method for the core flow distribution experiment in molten salt reactors based on conductivity fluid tracking technology. IET conference proceedings..DOI
Yang Yang, Yang Zou (2025). Thermal-hydraulic and irreversibility analysis of laminar mixed convection of molten salt with internal heat source. International Communications in Heat and Mass Transfer.DOI
Shuaiyu Xue, Chong Zhou, Pinyan Huang, Yang Zou (2025). Review of conceptual design and fundamental research related to the passive residual heat removal system in molten salt reactors. Nuclear Engineering and Design.DOI
Yang Yang, Yang Zou (2025). Performance evaluation of laminar mixed convection of molten salt in a horizontal circular tube with non-uniform heat flux. Journal of Energy Storage.DOI
Yang Yang, Yang Zou (2025). Evaluation of the thermal hydraulic behavior of laminar developing fuel salt with combined internal heat generation and wall heat flux. Thermal Science and Engineering Progress.DOI
Yang Yang, Yang Zou (2025). Thermal‐Hydraulic Performance and Entropy Generation Analysis of a Square Molten Salt Absorber Tube with Wavy‐Tape Insert at Low Reynolds Number. Annalen der Physik.DOI
Xingwei Chen, Zhizhe Xu, Ye Dai, Yang Zou (2025). Experimental research on heat transfer in a molten salt-heat pipe-thermoelectric generator system based on micro-MSR. Nuclear Engineering and Design.DOI
Yang Yang, Yang Zou (2025). Evaluation of the thermo-hydraulic performance of molten salt in laminar flow with a uniform internal heating in a circular pipe. Applied Thermal Engineering.DOI
Ziye Wang, Guifeng Zhu, Yang Zou, Xiaolin Liang, Liang Chen, Hongjie Xu (2025). Numerical Simulation of Entrained Bubbles Flow in the Shell‐Tube Heat Exchanger of MSRs Based on Population Balance Model. International Journal of Energy Research.DOI
Yunfei Zhang, Jian Ping Guo, Guifeng Zhu, Rui Yan, Yang Zou, Bo Zhou, Ying Chen (2025). Decay heat capability of MACT and its application to molten salt reactors. Nuclear Engineering and Design.DOI
Qiaohui Su, Ye Dai, Fangyuan Zhang, Yang Zou (2025). Optimization design of core flow distribution for 45MW solid fuel molten salt reactor. IET conference proceedings..DOI
Guobin Jia, Yang Zou, Ye Dai, Jian Tian, Heng Lu, Xiaofeng Yuan, Chong Zhou (2025). Integrated small modular molten salt reactors and pre-compression supercritical carbon dioxide Brayton cycle for ship propulsion: preliminary system performance analysis and optimization. IET conference proceedings..DOI
Yunfei Zhang, Yang Zou, Rui Yan, Guifeng Zhu, Qian Zhang (2025). A comprehensive depletion code MACT for molten salt reactors. Annals of Nuclear Energy.DOI
Jian Xin Guo, Yang Zou, Xuechao Zhao, Rui Yan (2025). Octant overlapping and angle-energy group expanded KBA parallelism of three-dimensional discrete ordinate method. Frontiers in Energy Research.DOI
Guancong Jia, Guifeng Zhu, Yuwen Ma, Jingen Chen, Yang Zou (2024). Thermodynamic Analysis and Optimization of Mobile Nuclear System. Energies.DOI
Yang Yang, Yang Zou (2024). Performance assessment of a high temperature chloride salt absorber tube with a novel half wavy-strip. Renewable Energy.DOI
Zhenghao Xu, Guifeng Zhu, Shuyang Jia, Yafen Liu, Changqing Yu, Yuhan Fan, Zhong Jun Yu, Rui Yan, Yang Zou, Hongjie Xu (2024). Calculation acceleration for fuel cycle simulation of molten salt reactor based on multi-group cross section method. Progress in Nuclear Energy.DOI
Minyu Peng, Yafen Liu, Yuhan Fan, Liang Chen, Yang Zou, Shaopeng Xia (2024). Preliminary study of transuranic transmutation in a small modular chloride salt fast reactor. Annals of Nuclear Energy.DOI
Yang Yang, Yang Zou, Zhijun Li (2024). Performance evaluates of flow and mixed convective heat transfer of Hitec salt in inclined tube with single surface heating. Solar Energy.DOI
Xuzhong Kang, Guifeng Zhu, Jianhui Wu, Rui Yan, Yang Zou, Yafen Liu (2024). Core Optimization for Extending the Graphite Irradiation Lifespan in a Small Modular Thorium-Based Molten Salt Reactor. Journal of Nuclear Engineering.DOI
Y.S. Chen, Ye Dai, Yang Zou, Junying Zhang, Y.W. Guo, H. Lu (2024). Experimental study on convective heat transfer characteristics of fluoride salt outside the tube bundle in hairpin heat exchanger. Annals of Nuclear Energy.DOI
Deyang Cui, X.X. Li, Ye Dai, Yang Zou, J.G. Chen, X. Z. Cai (2024). Accident scenario analysis and control scheme design for a micro Molten Salt Reactor. Progress in Nuclear Energy.DOI
Yang Yang, Yang Zou, Zhijun Li (2024). Numerical investigation on mixed convection for laminar molten salt in horizontal square tubes. Applied Thermal Engineering.DOI
Xue-Chao Zhao, Rui Yan, Guifeng Zhu, Yafen Liu, Jian Guo, X. Z. Cai, Yang Zou (2024). Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme. Nuclear Science and Techniques.DOI
Yuhan Fan, Rui Yan, Shihe Yu, Liang Chen, Yang Zou (2024). Conceptual design and feasibility analysis of a heat pipe cooled cermet fuel space nuclear reactor for mars surface application. Progress in Nuclear Energy.DOI
Shanwu Wang, Chong Zhou, N.X. Wang, Chuangxiong Cai, Haiyan Zhu, Yang Zou (2024). Numerical analysis and validation on heat transfer characteristics and correlation of molten salt in pebble bed channel. Nuclear Engineering and Design.DOI
Shuyang Jia, Guifeng Zhu, Yang Zou, Jian Guo, Zhenghao Xu, Siqin Hu, Hongjie Xu (2024). The Study of Continuous Core Zoning to Extend the Graphite Component Irradiation Lifespan in Molten Salt Reactor. International Journal of Energy Research.DOI
Liang Chen, Liao-Yuan He, Shaopeng Xia, Minyu Peng, Guifeng Zhu, Rui Yan, Yang Zou, Hongjie Xu (2024). Development and Verification of a Multi-Physics Transport Code of Molten Salt Reactor Fission Products. Energies.DOI
Yunfei Zhang, Qian Zhang, Yang Zou, Bo Zhou, Rui Yan, Guifeng Zhu, Jian Guo, Ao Zhang (2024). Evaluation of Transport–Burnup Coupling Strategy in Double-Heterogeneity Problem. Energies.DOI
Yunfei Zhang, Qian Zhang, Qiang Zhao, Yang Zou, Jian Guo, Rui Yan, Guifeng Zhu (2024). Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library. Science and Technology of Nuclear Installations.DOI
Jian Xin Guo, Zhu Guifeng, Yan Rui, Yang Zou (2024). Method of characteristics with a new Macro-track transport acceleration for complex general geometry. Annals of Nuclear Energy.DOI
Jiajun Wang, Ye Dai, Yang Zou, Hongjie Xu (2023). Uncertainty analysis of heat transfer of TMSR-SF0 simulator. Nuclear Engineering and Technology.DOI
Fang-Yuan Zhang, Guifeng Zhu, Yang Zou, Rui Yan, Hongjie Xu (2023). Core nuclear design and heat transfer analysis of a megawatt-level SiC coated particle based vehicular micro reactor. Nuclear Engineering and Design.DOI
Yang Yang, Yang Zou, Chong Zhou (2023). Conceptual design of narrow annular channel heater with rectangular wire coil for the simulator of solid-fuel thorium molten salt reactor. Nuclear Engineering and Design.DOI
Liang Chen, Liao-Yuan He, Bo Zhou, Guifeng Zhu, Yuhan Fan, Hongjie Xu, Rui Yan, Yang Zou (2023). Evaluation on 131I production based on molten salt reactor off-gas extraction. Annals of Nuclear Energy.DOI
Minyu Peng, Yafen Liu, Yang Zou, Ye Dai (2023). Preliminary Design and Study of a Small Modular Chlorine Salt Fast Reactor Cooled by Supercritical Carbon Dioxide. Energies.DOI
Changqing Yu, Guifeng Zhu, Yafen Liu, Rui Yan, Yang Zou (2023). Comparative Study on the Neutronic Performance of Thermal and Fast Molten Salt Reactors under Once-Through Fuel Cycle. International Journal of Energy Research.DOI
Liao-Yuan He, Yong Cui, Liang Chen, Shaopeng Xia, Lin-Yi Hu, Yang Zou, Rui Yan (2023). Effect of reprocessing on neutrons of a molten chloride salt fast reactor. Nuclear Science and Techniques.DOI
Haiyan Yu, Guifeng Zhu, Yang Zou, Rui Yan, Yafen Liu, Xuzhong Kang, Ye Dai (2023). Neutron/Gamma Radial Shielding Design of Main Vessel in a Small Modular Molten Salt Reactor. Journal of Nuclear Engineering.DOI
Chunyan Zou, Chenggang Yu, Jun Zhou, J.G. Chen, Shuning Chen, Shaopeng Xia, Yang Zou, X. Z. Cai, Jianhui Wu, Jingen Chen (2023). Impacts of core parameters on the capability of Cf-252 production in an MSR. Annals of Nuclear Energy.DOI
Xue-Chao Zhao, Yang Zou, Rui Yan, X. Z. Cai (2023). Analysis of burnup performance and temperature coefficient for a small modular molten-salt reactor started with plutonium. Nuclear Science and Techniques.DOI
Chunyan Zou, Chenggang Yu, Jun Zhou, J.G. Chen, Jianhui Wu, Yang Zou, X. Z. Cai, Jingen Chen (2023). Minor Actinides Transmutation in Thermal, Epithermal and Fast Molten Salt Reactors with Very Deep Burnup. Springer proceedings in physics.DOI
Shuaiyu Xue, Pengrong Qu, Chong Zhou, Yang Zou, Hongjie Xu (2023). NATURAL CIRCULATION CHARACTERISTICS OF THE MAIN CIRCUIT AFTER MOLTEN SALT REACTOR SHUTDOWN. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Shuaiyu Xue, Qiang Sun, Chong Zhou, Yang Zou, Hongjie Xu (2023). TRANSIENT CHARACTERIZATION OF FORCED CYCLE TO NATURAL CYCLE PROCESS IN LIQUID FUEL MOLTEN SALT REACTORS. The Proceedings of the International Conference on Nuclear Engineering (ICONE).DOI
Yang Zou, Fang Zhao, Shoulong Xu, Shuliang Zou (2022). Evaluation of Emergency Response Measures for the LOCA of A Marine Reactor. Sustainability, Vol. 14, No. 21.DOI
Liao-Yuan He, Liang Chen, Shaopeng Xia, Yang Zou (2022). Minor Actinides Transmutation and 233U Breeding in a Closed Th-U Cycle Based on Molten Chloride Salt Fast Reactor. Energies.DOI
Liao-Yuan He, Liang Chen, Yong Cui, Shaopeng Xia, Yang Zou (2022). Minor Actinides Transmutation Performance in a Closed Th–U Cycle Based on Molten Chloride Salt Fast Reactor. Materials.DOI
Deyang Cui, X.X. Li, Ye Dai, G. Hu, X. Z. Cai, Yang Zou, J.G. Chen (2022). An improved core design of a 50 kWth heat pipe cooled micro Molten Salt Reactor (micro-MSR). Progress in Nuclear Energy.DOI
Xingwei Chen, Yang Zou, Zehan Chen, Ye Dai (2022). Effect of core configuration on natural convection and heat transfer in heat pipe cooled micro-MSRs. Nuclear Engineering and Design.DOI
Fang-Yuan Zhang, Guifeng Zhu, Yang Zou, Rui Yan, Hongjie Xu (2022). Conceptual design and neutronic analysis of a megawatt-level vehicular microreactor based on TRISO fuel particles and S-CO2 direct power generation. Nuclear Science and Techniques.DOI
Yang Yang, Yang Zou, Chong Zhou (2022). Conjugate heat transfer analysis of molten salt in annular heater with rectangular wire coil. Results in Engineering.DOI
Menglu Tan, Guifeng Zhu, Zheng-De Zhang, Yang Zou, Xiaohan Yu, Chenggang Yu, Ye Dai, Rui Yan (2022). Burnup optimization of once-through molten salt reactors using enriched uranium and thorium. Nuclear Science and Techniques.DOI
Shi-Chen Xie, Yang Zou, Zhao Li, Jian-Fa Yang, Feng-Cai Zou, Xing-Quan Zhu (2021). Molecular detection and genotyping of Enterocytozoon bieneusi in black goats in Yunnan province,southwestern China. 《2021中国畜牧兽医学会兽医寄生虫学分会第二届青年科学家学术论坛》.DOI
Wen-Bin Zheng, Yang Zou, Jun-Jun He, Guo-Hua Liu, Min-Hua Hu, Xing-Quan Zhu (2021). Proteomic alterations in the plasma of Beagle dogs induced by Toxocara canis infection. 《2021中国畜牧兽医学会兽医寄生虫学分会第16次学术研讨会》.DOI
Pei Wang, Sen Li, Yang Zou, Zhao-Wei Hong, Ping Wang, Xing-Quan Zhu, De-Ping Song, Xiao-Qing Chen (2021). Prevalence and Subtype Distribution of Blastocystis sp.in Diarrheic Pigs in Southern China. 《2021中国畜牧兽医学会兽医寄生虫学分会第二届青年科学家学术论坛论文集》.
Shanwu Wang, Chong Zhou, Chuangxiong Cai, Haiyan Zhu, N.X. Wang, Yang Zou (2021). Experimental research on convective heat transfer characteristics of molten salt in a pebble bed channel with internal heat source. Nuclear Engineering and Design.DOI
Yang Yang, Minghai Li, Yang Zou, Jingen Chen (2021). Numerical study on heat transfer characteristics of molten salt in annular channel with wire coil. Applied Thermal Engineering.DOI
Yu Peng, Guifeng Zhu, Yang Zou, Miaomiao Niu, Hongjie Xu (2021). Spent fuel characteristics for thorium‐uranium recycle in fluoride‐salt‐cooled solid‐fuel fast reactor. International Journal of Energy Research.DOI
Liang Chen, Rui Yan, Xuzhong Kang, Guifeng Zhu, Bo Zhou, Liao-Yuan He, Yang Zou, Hongjie Xu (2021). Study on the production characteristics of 131I and 90Sr isotopes in a molten salt reactor. Nuclear Science and Techniques.DOI
Deyang Cui, Ye Dai, X. Z. Cai, Yuan Fu, X.X. Li, Yang Zou, J.G. Chen (2021). Preconceptual nuclear design of a 50 kWth heat pipe cooled micro molten salt reactor (micro-MSR). Progress in Nuclear Energy.DOI
Shihe Yu, Yafen Liu, Pu Yang, Rui-Min Ji, Guifeng Zhu, Bo Zhou, Xuzhong Kang, Rui Yan, Yang Zou, Ye Dai (2021). Neutronics analysis for MSR cell with different fuel salt channel geometries. Nuclear Science and Techniques.DOI
Yong Wang, Wei Guo, Guifeng Zhu, Ye Dai, Zhong Jun Yu, Yang Zou, Jingen Chen, X. Z. Cai (2021). A new structure design to extend graphite assembly lifespan in small modular molten salt reactors. International Journal of Energy Research.DOI
Yu Peng, Guifeng Zhu, Yang Zou, Hongjie Xu (2020). Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies. International Journal of Energy Research.DOI
Lianjie Wang, Wei Sun, Bangyang Xia, Yang Zou, Rui Yan (2020). Preferred core conceptual design of pebble bed advanced high temperature reactor. Annals of Nuclear Energy.DOI
Guifeng Zhu, Wei Guo, Xuzhong Kang, Chunyan Zou, Yang Zou, Rui Yan, Ye Dai (2020). Neutronic effect of graphite dimensional change in a small modular molten salt reactor. International Journal of Energy Research.DOI
Liao-Yuan He, Xia Shaopeng, Chen Jin-Gen, Liu Guimin, Wu Jian-hui, Yang Zou (2020). Th-U Breeding Performances in an Optimized Molten Chloride Salt Fast Reactor. Nuclear Science and Engineering.DOI
Jiajun Wang, Ye Dai, Yang Zou, Hongjie Xu (2020). Transient analysis of TMSR-SF0 simulator. Journal of Nuclear Science and Technology.DOI
Wen Yu, Jian Ruan, Long He, James Kendrick, Yang Zou, Hongjie Xu (2020). Development of TREND dynamics code for molten salt reactors. Nuclear Engineering and Technology.DOI
Liao-Yuan He, Shaopeng Xia, Xuemei Zhou, Chen Jin-Gen, Guimin Liu, Yang Zou, Rui Yan (2020). Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors. Nuclear Science and Techniques.DOI
Xuzhong Kang, Guifeng Zhu, Rui Yan, Yafen Liu, Yang Zou, Ye Dai, X. Z. Cai (2020). Evaluation of 99Mo production in a small modular thorium based molten salt reactor. Progress in Nuclear Energy.DOI
Liao-Yuan He, Guangchao Li, Shaopeng Xia, Chen Jin-Gen, Yang Zou, Guimin Liu (2020). Effect of $$^{{\textbf{37}}}{\textbf{Cl}}$$ enrichment on neutrons in a molten chloride salt fast reactor. Nuclear Science and Techniques.DOI
Yafen Liu, Rui Yan, Yang Zou, Shihe Yu, Bo Zhou, Xuzhong Kang, Jifeng Hu, X. Z. Cai (2020). Sensitivity/uncertainty comparison and similarity analysis between TMSR-LF1 and MSR models. Progress in Nuclear Energy.DOI
Bo Zhou, Xiaohan Yu, Yang Zou, Pu Yang, Shihe Yu, Yafen Liu, Xuzhong Kang, Guifeng Zhu, Rui Yan (2020). Study on dynamic characteristics of fission products in 2 MW molten salt reactor. Nuclear Science and Techniques.DOI
Bo Zhou, Xiaohan Yu, Yafen Liu, Yang Zou, Pu Yang, Shihe Yu, Xuzhong Kang, Guifeng Zhu, Rui Yan (2020). Study on dynamic characteristics of activated products source term in secondary loop of integrated molten salt reactor. Radiation Physics and Chemistry.DOI
Yu Peng, Guifeng Zhu, Yang Zou, Sijia Liu, Hongjie Xu (2020). Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor. International Journal of Energy Research.DOI
Yafen Liu, Wenjiang Li, Rui Yan, Yang Zou, Shihe Yu, Bo Zhou, X. Z. Cai (2020). Effect of FLiBe thermal neutron scattering on reactivity of molten salt reactor. EPJ Web of Conferences.DOI
Bo Zhou, Rui Yan, Xiaohan Yu, Yang Zou, Shihe Yu, Pu Yang, Yafen Liu (2020). Study on Kinetic Characteristics of Krypton and Xenon radioactive source term in molten salt reactor. EPJ Web of Conferences.DOI
Sen Li, Ping Wang, Yang Zou, Xing-Quan Zhu, Xiao-Qing Chen (2019). Prevalence and multilocus genotyping of Giardia duodenalis in the cattles of different breeds in Jiangxi,China. 《中国畜牧兽医学会兽医寄生虫学分会第一届青年科学家学术论坛摘要集》.DOI
Xingwei Chen, Ye Dai, Rui Yan, Mudan Mei, Jie Zhang, Yang Zou, Xiangzhou Cai (2019). Experimental study on the vibration behavior of the pebble bed in PB-FHR. Annals of Nuclear Energy.DOI
Menglu Tan, Guifeng Zhu, Yang Zou, Xiaohan Yu, Ye Dai (2019). Research on the effect of the heavy nuclei amount on the temperature reactivity coefficient in a small modular molten salt reactor. Nuclear Science and Techniques.DOI
Yafen Liu, Rui Yan, Yang Zou, Xuzhong Kang, Bo Zhou, Shihe Yu (2019). Neutron flux distribution and conversion ratio of Critical Experiment Device for molten salt reactor research. Annals of Nuclear Energy.DOI
Guifeng Zhu, Yang Zou, Rui Yan, Menglu Tan, Chunyan Zou, Xuzhong Kang, Jingen Chen, Wei Guo, Ye Dai (2019). Low enriched uranium and thorium fuel utilization under once‐through and offline reprocessing scenarios in small modular molten salt reactor. International Journal of Energy Research.DOI
Pu Yang, Ye Dai, Yang Zou, Rui Yan, Bo Zhou, Shihe Yu, Yuwen Ma (2019). Application of global variance reduction method to calculate a high-resolution fast neutron flux distribution for TMSR-SF1. Nuclear Science and Techniques.DOI
Guifeng Zhu, Sijia Liu, Yang Zou, Rui Yan, Menglu Tan, Xuzong Kang, Minghai Li, Bo Zhou, Ye Dai (2019). Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor. Progress in Nuclear Energy.DOI
Mudan Mei, Xingwei Chen, Sheng-De Sun, Rui Yan, Yang Zou (2019). Design and flow field analysis for visualization experiment facility of pebble bed based on molten salt reactor. Nuclear Science and Techniques.DOI
Yang Zou, Shuliang Zou, Changming Niu (2018). The Optimization of Emergency Evacuation from Nuclear Accidents in China. Sustainability, Vol. 100, No. 80.DOI
Yafen Liu, Rui Guo, X. Z. Cai, Rui Yan, Yang Zou, Bo Zhou (2018). Breeding Properties Study on High-Power Thorium Molten Salt Reactor. Journal of Nuclear Engineering and Radiation Science.DOI
Guifeng Zhu, Rui Yan, Ming Dai, Shihe Yu, Xuzhong Kang, Xiaohan Yu, X. Z. Cai, Guimin Liu, Yang Zou (2018). Monte Carlo burnup code development based on multi-group cross section method. Progress in Nuclear Energy.DOI
Chunyan Zou, Guifeng Zhu, Chenggang Yu, Yang Zou, Jingen Chen (2018). Preliminary study on TRUs utilization in a small modular Th-based molten salt reactor (smTMSR). Nuclear Engineering and Design.DOI
Yang Jun Zhong, Xiong Yang, Dong Ding, Yang Zou, D.K.L. Tsang (2018). Numerical study of the dynamic characteristics of a single-layer graphite core in a thorium molten salt reactor. Nuclear Science and Techniques.DOI
Xingwei Chen, Yang Zou, Rui Yan, Fengrui Liu, Jie Zhang, Mudan Mei, X. Z. Cai (2018). The packing factor of the pebble bed in molten salt reactor. Annals of Nuclear Energy.DOI
Kaichao Sun, Jarod Wilson, Sara Hauptman, Rui-Min Ji, Akshay J. Dave, Yang Zou, Lin-Wen Hu (2018). Neutronics modeling and analysis of the TMSR-SF1 fuel lattice and full core with explicit fuel particle distribution and random pebble loadings. Progress in Nuclear Energy.DOI
Yafen Liu, Rui Yan, Yang Zou, Xuzhong Kang, Ruimin Ji, Bo Zhou, Shihe Yu (2018). Criticality Properties and Control Rod Worth of the Critical Experiment Device for MSR Research. Nuclear Technology.DOI
Yang Jun Zhong, Xiong Yang, Dong Ding, Yang Zou, D.K.L. Tsang (2018). Dynamic characteristics identification of two graphite bricks in molten salt reactor considering fluid-structure interaction. Nuclear Engineering and Design.DOI
Guangchao Li, P. Cong, Chenggang Yu, Yang Zou, Jian Sun, J.G. Chen, Hongjie Xu (2018). Optimization of Th-U fuel breeding based on a single-fluid double-zone thorium molten salt reactor. Progress in Nuclear Energy.DOI
Rui Yan, Shihe Yu, Yang Zou, Qun Yang, Bo Zhou, Pu Yang, Honghua Peng, Yafen Liu, Ye Dai, Rui-Min Ji, Xuzhong Kang, Xingwei Chen, Minghai Li, Xiaohan Yu (2018). Study on neutronics design of ordered-pebble-bed fluoride-salt-cooled high-temperature experimental reactor. Nuclear Science and Techniques.DOI
Rui-Min Ji, Cheng-Gang Yu, Minghai Li, Rui Yan, Yang Zou, Guimin Liu (2018). Study on inherent neutron sources in MSR. Nuclear Science and Techniques.DOI
Xingwei Chen, Jie Zhang, Ye Dai, Mudan Mei, Rui-Min Ji, Rui Yan, Yang Zou, X. Z. Cai (2018). Experimental investigation of the bed structure in liquid salt cooled pebble bed reactor. Nuclear Engineering and Design.DOI
Yu Peng, Guifeng Zhu, Yang Zou, Sijia Liu, Hongjie Xu (2017). Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel. Nuclear Science and Techniques.DOI
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Yu Peng, Guifeng Zhu, Yang Zou, Yafen Liu, Xiaohan Yu, X. Z. Cai, Hongjie Xu (2017). The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant. Progress in Nuclear Energy.DOI
Jian Ruan, Bo Xu, Minghai Li, Yang Yang, Yang Zou, Hongjie Xu (2017). A specialized code for operation transient analysis and its application in fluoride salt-cooled high-temperature reactors. Nuclear Science and Techniques.DOI
Ruan Jian, Yang Zou, Minghai Li, Hongjie Xu (2017). Control Scheme Research of 10MW Fluoride Salt Cooled High Temperature Experiment Reactor.DOI
Yao Fu, Qiang Sun, Chong Zhou, Yang Zou (2017). Thermal Hydraulics Analysis of the Fluoride-Salt-Cooled, High-Temperature Reactor.DOI
Guangchao Li, Yang Zou, Chenggang Yu, Jianlong Han, Chen Jin-Gen, Hongjie Xu (2017). Influences of 7Li enrichment on Th–U fuel breeding for an Improved Molten Salt Fast Reactor (IMSFR). Nuclear Science and Techniques.DOI
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