Results 11 to 20 of about 1,546,971 (249)
Experimental Study of Pressure Loss in a 5 × 5–Rod Bundle With the Mixing Vane Spacer Grid [PDF]
Frontiers in Energy Research, 2021 Axial and lateral pressure loss in a 5 × 5 rod–bundle with a split-type mixing vane spacer grid was experimentally measured using differential pressure transmitters at different sub-channel Reynolds numbers (Re) and orienting angles.
Wenhai Qu +3 more
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Experimental Study on Heat Transfer Characteristics of Rod Bundle Channel in Natural Circulation under Rolling Motion Condition [PDF]
Yuanzineng kexue jishuAffected by sea wind and waves, the floating nuclear power plant (FNPP) would be in rolling motion during operation. The rolling motion will introduce fluctuated inertial force periodically, resulting in periodic thermal and hydraulic parameters ...
LI Xin1, WANG Shuang1, TAN Sichao1, , QIAO Shouxu1, TIAN Ruifeng1, CHENG Kun2
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Numerical Study of Deposition Characteristic of Corrosion Product in Lead-bismuth Cooled Wire-wrapped Rod Bundle [PDF]
Yuanzineng kexue jishuLead-based reactor using liquid lead-bismuth alloys as coolant has many advantages and is a promising type of fourth-generation reactors for a wide range of applications.
HUANG Rui, SUN Yubo, FU Junsen, XIAO Yao, GU Hanyang
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He jishuBackgroundThe floating nuclear power plant (FNPP) is a vital energy supply method for future ocean exploitation and island construction. The typical fuel type of FNPP is similar to the onshore nuclear power plant, i.e., the rod bundle fuel assembly.
LI Xin +4 more
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Prediction of critical heat flux in a rod bundle channel with spacer grids based on the Eulerian two-fluid model [PDF]
Frontiers in Energy ResearchThe critical heat flux (CHF) is a vital parameter influencing the safety and efficiency of reactor cores. In this study, the Eulerian two-fluid model coupled with the extended wall boiling model in STAR-CCM+ was employed to simulate the departure from ...
Li Kejia +7 more
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Numerical simulation to study mixing vane spacer effects on heat transfer performance of supercritic
Journal of Thermal Engineering, 2023 The spacer represents an essential part in the nuclear fuel rod. Spacer grid with mixing vanes in fuel rod bundle of nuclear reactor core has a significant impact on heat transfer performance in downstream to grid spacer.
Satish Kumar DHURANDHAR +2 more
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Yuanzineng kexue jishu, 2022 There is mixing and second flow in sub-channels of the rod bundle. The flow and heat transfer characteristics in rod bundle are more complex than those in rectangular channel and round pipes.
BI Jingliang;XIE Feng;HUANG Yanping;XU Jianjun;YUAN Dewen;ZAN Yuanfeng
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Turbulent-Prandtl-number models for liquid lead-bismuth in triangular rod bundles
He jishu, 2022 BackgroundIn order to accurately predict the heat transfer characteristics in the sub-channel of fuel assembly for the low Prandtl number fluid, it is necessary to select a suitable turbulent-Prandtl-number model.PurposeThis study aims at the ...
LIU Shuyong +5 more
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Modeling and Simulation Analysis on Mixing Characteristics of Two-Phase Flow Around Spacer Grid
Frontiers in Energy Research, 2022 The spacer grid has a significant impact on the thermal-hydraulic characteristics of the rod bundle channel, which directly determines the possibility of a boiling crisis.
Y. Xiao +5 more
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Journal of Mechanical Engineering and Sciences, 2022 Spacer is a vital component in assembly of nuclear fuel rod bundles. It is used to support and maintain suitable distance between the rods in assembly of nuclear fuel bundle.
Satish Kumar Dhurandhar +2 more
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