Simulation research on decay heat removal system in primary loop of pool-type sodium-cooled fast reactor

被引:0
|
作者
Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin [1 ]
150001, China
机构
来源
Yuanzineng Kexue Jishu | / 5卷 / 863-870期
关键词
D O I
10.7538/yzk.2015.49.05.0863
中图分类号
学科分类号
摘要
引用
收藏
相关论文
共 50 条
  • [21] Three-dimensional numerical research on natural circulation characteristics of decay heat removal system in pool-type fast reactor CEFR
    Liang, Jiangtao
    Lu, Daogang
    Fu, Jingpin
    Zhao, Haiqi
    Luo, Xinyue
    Zhang, Yuhao
    NUCLEAR ENGINEERING AND DESIGN, 2021, 383 (383)
  • [22] Analysis of the effect of thermal stratification on the natural circulation decay heat removal of sodium-cooled fast reactor
    Liu, Yapeng
    Zhang, Dalin
    Zhou, Lei
    Chen, Kailong
    Tian, Wenxi
    Qiu, Suizheng
    State, Su
    PROGRESS IN NUCLEAR ENERGY, 2024, 167
  • [23] IN-SERVICE INSPECTION OF LOOP SYSTEM SODIUM-COOLED FAST REACTOR
    PICKETT, AG
    HAWKESWO.W
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 120 - &
  • [24] Design and Analysis of Passive Decay Heat Removal System for Sodium-cooled Small Modular Reactor
    Chen Z.
    Yang H.
    Yu H.
    Hou B.
    Zhu L.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (08): : 1417 - 1423
  • [25] Model Development and Transient Analysis of Thermal Stratification Phenomenon in Pool-Type Sodium-Cooled Fast Reactors
    Du P.
    Shan J.
    Deng J.
    Liu Y.
    Ding S.
    Chen W.
    Yuan P.
    Wu Z.
    Hedongli Gongcheng/Nuclear Power Engineering, 2022, 43 (04): : 25 - 30
  • [26] CFD modeling and thermal-hydraulic analysis for the passive decay heat removal of a sodium-cooled fast reactor
    Hung, T. C.
    Dhir, V. K.
    Chang, J. C.
    Wang, S. K.
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (01) : 425 - 432
  • [27] Model development and transient analysis of thermal stratification phenomenon in pool-type sodium-cooled fast reactors
    Du, Peng
    Shan, Jianqiang
    Deng, Jian
    Xiong, Qingwen
    Li, Zhongchun
    Yuan, Peng
    ANNALS OF NUCLEAR ENERGY, 2022, 166
  • [28] Study on Inherent Safety Characteristic on Thermal-hydraulic of Pool-type Sodium-cooled Fast Reactors
    Zhou Z.
    Xue X.
    Yang Y.
    Yang H.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2023, 57 (07): : 1397 - 1405
  • [29] An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors
    Lu, Cihang
    Wu, Zeyun
    Morgan, Sarah
    Schneider, James
    Anderson, Mark
    Xu, Liangyu
    Baglietto, Emilio
    Bucknor, Matthew
    Weathered, Matthew
    Bilbao y Leon, Sama
    NUCLEAR TECHNOLOGY, 2020, 206 (10) : 1465 - 1480
  • [30] Model development and transient analysis of thermal stratification phenomenon in pool-type sodium-cooled fast reactors
    Du, Peng
    Shan, Jianqiang
    Deng, Jian
    Xiong, Qingwen
    Li, Zhongchun
    Yuan, Peng
    Annals of Nuclear Energy, 2022, 166