Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Na-xiu Wang"'
Autor:
Zezhong Chen, Jian-Ping Liang, Li Jiang, De-Jun Wang, Zhijun Li, Li Ming, Na-xiu Wang, Jia Xiao, Xiang-Xi Ye
Publikováno v:
International Journal of Minerals, Metallurgy and Materials. 28:1811-1820
Publikováno v:
Annals of Nuclear Energy. 179:109390
Publikováno v:
Nuclear Science and Techniques. 32
The molten salt leakage accident is an important issue in the nuclear safety analysis of molten salt reactors. While the molten salt leaks from the pipeline or storage tank, it will contact the insulation layer outside; hence, the processes of penetr
Publikováno v:
Annals of Nuclear Energy. 132:504-511
In order to better understand the thermal performance and improve the thermal sizing design of molten salt-to-air heat exchanger, a serpentine coil cross flow heat exchanger with molten salt on tube side and air on shell side is designed and tested.
Publikováno v:
Annals of Nuclear Energy. 168:108876
Publikováno v:
Nuclear Science and Techniques. 31
To improve the reliability and reduce energy consumption, a conceptual design of a freeze valve is proposed for the thorium-based molten salt reactor (TMSR) concept. Fins were utilized in this new design to enhance heat transfer and realize passive s
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 902:190-196
To select a more appropriate cooling method for a reflection mirror of Spatial and Spin (S2 ) beam-line at SSRF (Shanghai Synchrotron Radiation Facility), both of the internal cooling method and side cooling method were proposed and compared at vario
Autor:
Qiang Sun, Na-Xiu Wang, Zhong-Feng Tang, Y.S. Chen, Hai-Hua Zhu, Jian Tian, Shen-De Sun, Yuan Fu
Publikováno v:
Applied Thermal Engineering. 125:995-1001
In this paper, laminar convective heat transfer performance of molten salt with Reynolds number of 300–2300 and Grashof number of 8.56 × 104–3.95 × 106 in a concentric tube heat exchanger is reported. The effects of temperature on the heat tran
Autor:
Na-Xiu Wang, Qiang Niu
Publikováno v:
Nuclear Science and Techniques. 30
The pebble-bed reactor is one of the most promising designs for the nuclear energy industry. In this paper, a discrete element method–computational fluid dynamics (DEM–CFD) approach that includes thermal conduction, radiation, and natural convect
Publikováno v:
Nuclear Science and Techniques. 30
Carbonic composite materials and ceramics appear to be excellent structural materials for parts subjected to very high temperatures in molten salt reactors (MSRs), in which the reactor core outlet temperature is normally above 700 °C. Because of the