Decoupled thermal-hydraulic analysis of an air-cooled separated heat pipe for spent fuel pools under natural convection

被引:1
|
作者
Xue, Hui-Lin [1 ]
Cheng, Jian-Jie [1 ]
Ji, Wei-Hao [1 ]
Li, Wen-Jin [1 ]
Tao, Han-Zhong [2 ]
Li, Wei [1 ]
机构
[1] Nanjing Tech Univ, Coll Urban Construct, Nanjing 211800, Peoples R China
[2] Nanjing Tech Univ, Sch Energy Sci & Engn, Nanjing 211800, Peoples R China
关键词
Decoupled analysis; Separated heat pipe; CAP1400; Finned tube radiator; Passive cooling; PASSIVE COOLING SYSTEM; RESIDUAL HEAT; REMOVAL SYSTEM; OVAL TUBES; EXCHANGERS; DESIGN; PERFORMANCE; REACTOR; FIN;
D O I
10.1007/s41365-023-01244-w
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
An investigation of the decoupled thermal-hydraulic analysis of a separated heat pipe spent fuel pool passive cooling system (SFS) is essential for practical engineering applications. Based on the principles of thermal and mass balance, this study decoupled the heat transfer processes in the SFS. In accordance with the decoupling conditions, we modeled the spent fuel pool of the CAP1400 pressurized water reactor in Weihai and used computational fluid dynamics to explore the heat dissipation capacity of the SFS under different air temperatures and wind speeds. The results show that the air-cooled separated heat pipe radiator achieved optimal performance at an air temperature of 10 & DEG;C or wind speed of 8 m/s. Fitted equations for the equivalent thermal conductivity of the separated heat pipes with the wind speed and air temperature we obtained according to the thermal resistance network model. This study is instructive for the actual operation of an SFS.
引用
收藏
页数:15
相关论文
共 50 条
  • [1] Decoupled thermal–hydraulic analysis of an air-cooled separated heat pipe for spent fuel pools under natural convection
    Hui-Lin Xue
    Jian-Jie Cheng
    Wei-Hao Ji
    Wen-Jin Li
    Han-Zhong Tao
    Wei Li
    Nuclear Science and Techniques, 2023, 34
  • [2] Decoupled thermal–hydraulic analysis of an air?cooled separated heat pipe for spent fuel pools under natural convection
    Hui?Lin Xue
    Jian?Jie Cheng
    Wei?Hao Ji
    Wen?Jin Li
    Han?Zhong Tao
    Wei Li
    Nuclear Science and Techniques, 2023, 34 (06) : 54 - 68
  • [3] Thermal Hydraulic Analysis of the Convective Heat Transfer of an Air-cooled BWR Spent Fuel Assembly
    Partmann, Christine
    Schuster, Christoph
    Hurtado, Antonio
    ATW-INTERNATIONAL JOURNAL FOR NUCLEAR POWER, 2018, 63 (6-7): : 397 - +
  • [4] Analysis of natural convection heat transfer in spent fuel pool cooled with heat pipe
    Zheng, Wen-Long
    Wang, Wen
    Zhuan, Rui
    Kuang, Yi-Wu
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2014, 48 (12): : 2250 - 2256
  • [5] A review on the thermal hydraulic characteristics of the air-cooled heat exchangers in forced convection
    Kumar, Ankur
    Joshi, Jyeshtharaj B.
    Nayak, Arun K.
    Vijayan, Pallippattu K.
    SADHANA-ACADEMY PROCEEDINGS IN ENGINEERING SCIENCES, 2015, 40 (03): : 673 - 755
  • [6] A review on the thermal hydraulic characteristics of the air-cooled heat exchangers in forced convection
    ANKUR KUMAR
    JYESHTHARAJ B JOSHI
    ARUN K NAYAK
    PALLIPPATTU K VIJAYAN
    Sadhana, 2015, 40 : 673 - 755
  • [7] Investigation of the Thermal-Hydraulic Behavior of Dry Spent Fuel Casks under Forced Convection
    Helmy, S.
    Hamza, A.
    Elnaggar, S.
    ARAB JOURNAL OF NUCLEAR SCIENCES AND APPLICATIONS, 2019, 52 (01): : 145 - 153
  • [8] Uncertainty Analysis of Thermal-hydraulic Characteristics of Silent Heat Pipe Cooled Reactor
    Han R.
    Wang C.
    Guo K.
    Su G.
    Qiu S.
    Tian W.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2023, 57 (05): : 998 - 1006
  • [9] Thermal-hydraulic and load following performance analysis of a heat pipe cooled reactor
    Jiao, Guanghui
    Xia, Genglei
    Wang, Jianjun
    Peng, Minjun
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2024, 56 (05) : 1698 - 1711
  • [10] Thermal-hydraulic analysis of air cooled finned heat transfer tubes
    Suzuki, Daisuke
    Mochizuki, Hiroyasu
    ANNALS OF NUCLEAR ENERGY, 2016, 95 : 1 - 11