Thermal-Hydraulic Performance Analysis of Horizontal Spiral Tube Steam Generator for European Lead-Cooled Fast Reactor

被引：0
|
作者：
Zhang, Wei [1 ,2 ]
Li, Jingsong [1 ,2 ]
Shi, Huilie [1 ,2 ]
Qiao, Pengrui [3 ]
Wang, Cong [1 ,2 ]
Zhang, Tianqing [1 ]
He, Yingzhao [1 ]
机构：
[1] China Nuclear Power Operation Technology Corporation, Wuhan,430074, China
[2] Research Institute of Nuclear Power Operation, Wuhan,430074, China
[3] China Institute of Atomic Energy, Beijing,102413, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2022年 / 43卷 / 03期
关键词：
Cooled systems - Horizontal spiral tube - Lead cooled fast reactor - Performances analysis - Spiral tubes - Steam generator - Thermal and hydraulic performance - Thermal hydraulics - Thermal-hydraulic performance - Tube steam generators;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Taking the horizontal spiral tube steam generator (HST-SG) of European lead-cooled system (ELSY) as the research object, combined with its structural and operating parameters, this paper selects an appropriate heat transfer resistance model and develops a one-dimensional steady-state thermal hydraulic calculation program. Firstly, the program is used to check and calculate ELSY HST-SG to verify the accuracy of the program calculation. Then, combined with the calculation results, the thermal and hydraulic performance of ELSY HST-SG is analyzed in detail, and the comparative analysis and research is carried out for different operation parameters. The analysis results show that the selection of various parameters of ELSY HST-SG is reasonable, the thermal and hydraulic performance is excellent, and the purpose of compact structure is achieved. Therefore, this program can be used for design development and performance analysis of ELSY HST-SG. © 2022, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
引用
收藏
页码：38 / 45
相关论文
共 50 条
  • [11] Development and Performance Analysis of an Electromagnetic Pump for a Thermal Hydraulic Experimental Loop of a Lead-Cooled Fast Reactor
    Li, Zi'ang
    Yuan, Lanfei
    Wang, Chenglong
    Qiu, Suizheng
    Li, Ying
    ENERGIES, 2025, 18 (03)
  • [12] On the neutronics of European lead-cooled fast reactor
    Cetnar, Jerzy
    Oettingen, Mikolaj
    Domanska, Grazyna
    NUKLEONIKA, 2010, 55 (03) : 317 - 322
  • [13] STUDY ON BUBBLE MIGRATION CHARACTERISTICS IN A LEAD-COOLED FAST REACTOR AFTER STEAM GENERATOR TUBE RUPTURE ACCIDENT
    Feng, Zhenyu
    Zhang, Dalin
    Jiao, Haoyu
    Chen, Yutong
    Lin, Yue
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 11, ICONE31 2024, 2024,
  • [14] Helical coil thermal-hydraulic model for supercritical lead cooled fast reactor steam generators
    Caramello, Marco
    Bertani, Cristina
    De Salve, Mario
    Panella, Bruno
    APPLIED THERMAL ENGINEERING, 2016, 101 : 693 - 698
  • [15] Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor
    Yu, Qifan
    Zhang, Yan
    Wang, Chenglong
    Guo, Chao
    Deng, Jian
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2021, 153
  • [16] Thermal-hydraulic analysis of an innovative decay heat removal system for lead-cooled fast reactors
    Giannetti, Fabio
    Di Maio, Damiano Vitale
    Naviglio, Antonio
    Caruso, Gianfranco
    NUCLEAR ENGINEERING AND DESIGN, 2016, 305 : 168 - 178
  • [17] Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor
    Yu, Qifan
    Zhang, Yan
    Wang, Chenglong
    Guo, Chao
    Deng, Jian
    Zhang, Dalin
    Tian, Wenxi
    Qiu, Suizheng
    Su, G.H.
    Annals of Nuclear Energy, 2021, 153
  • [18] Conceptual design of a bayonet-tube steam generator for the ALFRED lead-cooled reactor
    Damiani, Lorenzo
    Montecucco, Massimo
    Prato, Alessandro Pini
    NUCLEAR ENGINEERING AND DESIGN, 2013, 265 : 154 - 163
  • [19] Modeling of the Wear of Tube–Spacer Comb Interfacing in the Steam Generator of a Lead-Cooled Reactor
    V. V. Lemekhov
    V. D. Sizarev
    S. V. Stolotnyuk
    Yu. V. Lemekhov
    B. Ya. Sachek
    A. M. Mezrin
    T. I. Murav’eva
    I. A. Soldatenkov
    Atomic Energy, 2020, 127 : 202 - 206
  • [20] Modeling of the Wear of Tube-Spacer Comb Interfacing in the Steam Generator of a Lead-Cooled Reactor
    Lemekhov, V. V.
    Sizarev, V. D.
    Stolotnyuk, S. V.
    Lemekhov, Yu. V.
    Sachek, B. Ya.
    Mezrin, A. M.
    Murav'eva, T. I.
    Soldatenkov, I. A.
    ATOMIC ENERGY, 2020, 127 (04) : 202 - 206
12345