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
  • [1] Transient analysis of the main heat-transfer system of the pool-type sodium-cooled fast reactor
    Yang H.
    Qi S.
    Yang J.
    Ye S.
    Xue X.
    Zhongguo Kexue Jishu Kexue/Scientia Sinica Technologica, 2022, 52 (10): : 1521 - 1542
  • [2] Heat transfer in the argon space of pool-type sodium-cooled fast reactor: Numerical simulation and experimental validation
    Lu, Daogang
    Feng, Jiaqi
    Yu, Zongyu
    Wang, Han
    Zhang, Yuhao
    ANNALS OF NUCLEAR ENERGY, 2024, 197
  • [3] A practical methodology devoted to pool-type phenomena simulation in safety analysis for sodium-cooled fast reactor
    Wang, Shibao
    Zhang, Dalin
    Qiu, Suizheng
    Su, Guanghui
    Tian, Wenxi
    INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 45 (08) : 11868 - 11881
  • [4] Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor
    Zhang, D. L.
    Song, P.
    Wang, S.
    Wang, X.
    Chen, J.
    Liang, Y.
    Qiu, S. Z.
    KERNTECHNIK, 2018, 83 (03) : 232 - 236
  • [5] DESIGN STUDY OF AN IHX SUPPORT STRUCTURE FOR A POOL-TYPE SODIUM-COOLED FAST REACTOR
    Park, Chang-Gyu
    Kim, Jong-Bum
    Lee, Jae-Han
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2009, 41 (10) : 1323 - 1332
  • [6] A study on reliability assessment of a decay heat removal system for a sodium-cooled fast reactor
    Kim, Jintae
    Jae, Moosung
    ANNALS OF NUCLEAR ENERGY, 2018, 120 : 534 - 539
  • [7] Review on Three-dimensional Numerical Simulation Research of Flow and Heat Transfer Characteristics in Complex Space of Pool-type Sodium-cooled Fast Reactor
    Zhang, Yuhao
    Zhao, Haiqi
    Shen, Xihao
    Yuan, Xiaoxiao
    Song, Haijie
    Lu, Daogang
    Sui, Danting
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2024, 58 : 271 - 283
  • [8] Thermal hydraulic characteristics of intermediate heat exchanger with coaxial bending tubes in a pool-type sodium-cooled fast reactor
    Li, Zeng-Yao
    Yu, Guang-Lei
    NUCLEAR ENGINEERING AND DESIGN, 2021, 375
  • [9] Preliminary Study on Core Melt In-vessel Retention of Pool-type Sodium-cooled Fast Reactor
    Xue, Fangyuan
    Zhang, Donghui
    Liu, Yizhe
    Zhang, Xisi
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2024, 58 (03): : 689 - 697
  • [10] Numerical investigation on the core thermal hydraulic behavior of pool-type sodium-cooled fast reactor (SFR)
    Wang, X.A.
    Liang, Ximei
    Xu, RongShuan
    He, DongYu
    Wang, Ting
    Zhang, Dalin
    Frontiers in Energy Research, 2024, 12