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Numerical study of thermal-hydraulic characteristics in pipe of floating nuclear reactor under pulsating flow
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Yao YAO1, Chao LI2, Peiyao QI1, Ruixiang ZHANG1, Lin YE2, Chongxi CHANG2, Xiqiang MA2
Thermal Power Generation | 2024, 53(2) : 93 - 100
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Thermal Power Generation | 2024, 53(2): 93-100
Thermal energy science research
Numerical study of thermal-hydraulic characteristics in pipe of floating nuclear reactor under pulsating flow
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Yao YAO1, Chao LI2, Peiyao QI1, Ruixiang ZHANG1, Lin YE2, Chongxi CHANG2, Xiqiang MA2
Affiliations
  • 1.Xi’an Thermal Power Research Institute Co., Ltd., Xi’an 710054, China
  • 2.Huaneng Shandong Shidao Bay Nuclear Power Co., Ltd., Weihai 264312, China
Published: 2024-02-25 doi: 10.19666/j.rlfd.202306114
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Under oceanic conditions, the coolant in the loop of a floating nuclear reactor (FNR) experiences periodic fluctuations, which affects the system’s thermal and hydraulic characteristics. A combination of theoretical derivation and numerical simulation is employed to investigate the velocity and temperature distribution characteristics within a pipe under pulsating flow conditions. Moreover, the influence of different numerical simulation boundary conditions on the velocity and temperature distribution in a circular tube under pulsating flow is compared. The results show that, under high-frequency pulsating flow conditions, laminar flow inside the pipe will experience backflow near the wall, and the wall effect will increase with the pulsation frequency. Using pulsating velocity inlet and pressure outlet as numerical simulation boundary conditions fails to predict this backflow phenomenon. However, employing fluctuating pressure inlet and flow outlet effectively captures the backflow occurrence in high-frequency pulsating flow. Concurrently, the temperature within the pipe fluctuates under pulsating flow conditions, and the amplitude of temperature fluctuations gradually decreases when the pulsation frequency increases. Numerical simulation can well simulate the temperature distribution in the pipe under pulsating flow conditions, with an error of less than 2%.The research results can provide reference for non-stationary numerical simulation methods.

pulsating flow  /  numerical simulation  /  velocity distribution  /  temperature distribution  /  floating nuclear reactor
Yao YAO, Chao LI, Peiyao QI, Ruixiang ZHANG, Lin YE, Chongxi CHANG, Xiqiang MA. Numerical study of thermal-hydraulic characteristics in pipe of floating nuclear reactor under pulsating flow[J]. Thermal Power Generation, 2024 , 53 (2) : 93 -100 . DOI: 10.19666/j.rlfd.202306114
  • Natural Science Foundation of Shaanxi Province(2023-JC-QN-0611)
Year 2024 volume 53 Issue 2
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Article Info
doi: 10.19666/j.rlfd.202306114
  • Receive Date:2023-06-27
  • Online Date:2025-12-31
  • Published:2024-02-25
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  • Received:2023-06-27
Funding
Natural Science Foundation of Shaanxi Province(2023-JC-QN-0611)
Affiliations
    1.Xi’an Thermal Power Research Institute Co., Ltd., Xi’an 710054, China
    2.Huaneng Shandong Shidao Bay Nuclear Power Co., Ltd., Weihai 264312, China
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https://castjournals.cast.org.cn/joweb/rlfd/EN/10.19666/j.rlfd.202306114
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表12种不同金属材料的力学参数

Family
属数
Number of
genus
种数
Number of
species
占总种数比例
Percentage of
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Genus
种数
Number of
species
占总种数比例
Percentage of total
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鹅膏菌科Amanitaceae 2 11 5.26 鹅膏菌属 Amanita 10 4.78
小菇科 Mycenaceae 2 12 5.74 丝盖伞属 Inocybe 5 2.39
多孔菌科 Polyporaceae 8 14 6.70 蜡蘑属 Laccaria 5 2.39
红菇科 Russulaceae 3 23 11.00 小皮伞属 Marasmius 6 2.87
小菇属 Mycena 11 5.26
光柄菇属 Pluteus 5 2.39
红菇属 Russula 17 8.13
栓菌属 Trametes 5 2.39
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