Shuyang Jia, Guifeng Zhu, Zhenghao Xu, Changqing Yu, Yang Zou, Hongjie Xu (2026). Analysis of fast neutron flux rebound and burnup under once-through fuel cycle mode in a continuous zoning molten salt reactor. Nuclear Engineering and Design.DOI
Tingjing Dong, Hui-Qing Fan, Yang Zou, Hongjie Xu (2026). Hydraulic optimization of a high-temperature molten salt canned motor pump using an ANN-NSGA-II approach. Nuclear Engineering and Technology.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
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
Ziye Wang, Gui-Feng 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
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
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
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
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, Gui-Feng 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
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
Shuaiyu Xue, Peng 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
Guoyu Chen, Minghai Li, Yang Zou, Hongjie Xu (2022). Analysis of load-following operation characteristics of liquid fuel molten salt reactor. Progress in Nuclear Energy.DOI
Ke Li, Yantao Gao, Haipeng Zhang, Guohao Du, Hefei Huang, Hongjie Xu, Tiqiao Xiao (2021). Efficient three-dimensional characterization of C/C composite reinforced with densely distributed fibers via X-ray phase-contrast microtomography. Chinese Optics Letters.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
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
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
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
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
Guifeng Zhu, Yang Zou, Hongjie Xu (2016). Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor. EPJ Nuclear Sciences & Technologies.DOI
邱杰,邹杨,俞国军,何上明,刘文冠,贾彦彦,李志军,徐洪杰 (2015). Speciation study of chromium corrosion product in molten LiF-NaF-KF salt. Nuclear Science and Techniques.
于海生,魏向军,李炯,顾颂琦,张硕,汪丽华,马静远,李丽娜,高倩,司锐,孙凡飞,王宇,宋飞,徐洪杰,余笑寒,邹杨,王建强,姜政,黄宇营 (2015). The XAFS beamline of SSRF. Nuclear Science and Techniques.
Te Ji, Yajun Tong, Huachun Zhu, Zengyan Zhang, Weiwei Peng, Min Chen, Tiqiao Xiao, Hongjie Xu (2015). The status of the first infrared beamline at Shanghai Synchrotron Radiation Facility. Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment.DOI
刘文冠,韩晗,任翠兰,阴慧琴,怀平,邹杨,徐洪杰 (2014). The effect of Nb additive on Te-induced stress corrosion cracking in Ni alloy: a first-principles calculation. Nuclear Science and Techniques.
Heng Liu, Yongnian Zhou, Zheng Rong Jiang, Songqi Gu, Xiangjun Wei, Yuying Huang, Yang Zou, Hongjie Xu (2012). QXAFS system of the BL14W1 XAFS beamline at the Shanghai Synchrotron Radiation Facility. Journal of Synchrotron Radiation.DOI
邓彪,余笑寒,徐洪杰(2007). 采样间隔和投影数对SR-XFMT重构质量的影响(英文). Chinese Physics C.
邓彪,余笑寒,徐洪杰(2007). 同步辐射微束X射线荧光CT的计算机模拟. 《核技术》.
Hongjie Xu, Zhong Zhao, Hongfa Ding (2007). Current Status of the SSRF Project. AIP conference proceedings.DOI
Qianyu Zhou, N. Chen, M. Zhang, zuhan dai, Jie He, X. H. Yu, Zhong Zhao, Hongjie Xu (2007). First Group of Insertion Devices for SSRF. AIP conference proceedings.DOI
Zhong Zhao, Hongjie Xu, Hongxin Ding (2006). Status of the Shanghai Synchrotron Radiation Facility. Particle Accelerator Conference (PAC).DOI
Danhua Zeng, Tiqiao Xiao, Guohao Du, Wen Li, Hongxin Luo, Xia Shaojian, Hongjie Xu (2006). New long trace profiler based on phase plate diffraction for optical metrology of SSRF. Review of Scientific Instruments.DOI
Zheng-Hao Xu, Gui-Feng Zhu, Liang Chen, Shuyang Jia, Chang-Qing Yu, Yun-Fei Zhang, Yang Zou, Hongjie Xu. The decay heat distribution calculation in molten salt reactor experiment based on the nuclide flow-transfer-burnup coupling method. Progress in nuclear energy (New series).DOI