Research and development of real-time thermal-hydraulic simulation code for plate type fuel reactors

被引：0
|
作者：
Zhang, Zhi-Jian [1 ]
Li, Lei [1 ]
Guo, Yun [1 ]
机构：
[1] National Defense Key Subject Laboratory for Safety and Simulation Technology, Harbin Engineering University, Harbin, 150001, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2010年 / 31卷 / 06期
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：56 / 63
相关论文
共 50 条
  • [1] DEVELOPMENT OF REAL-TIME THERMAL-HYDRAULIC ANALYSIS CODE FOR PLATE TYPE FUEL REACTOR
    Li Lei
    Zhang Zhijian
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 2, 2011, : 497 - 505
  • [2] Development and validation of thermal-hydraulic analysis code for plate type fuel research reactors
    Lu, Qing
    Zhang, Zhi-Jian
    Qiu, Sui-Zheng
    Su, Guang-Hui
    Tian, Wen-Xi
    Hedongli Gongcheng/Nuclear Power Engineering, 2009, 30 (05): : 26 - 29
  • [3] Development of a thermal-hydraulic analysis code for research reactors with plate fuels
    State Key Laboratory of Multi Phase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China
    不详
    Ann Nucl Energy, 4 (433-447):
  • [4] Development of a thermal-hydraulic analysis code for research reactors with plate fuels
    Lu, Qing
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2009, 36 (04) : 433 - 447
  • [5] Development of Thermal-Hydraulic Analysis Code for Plate Type Fuel Reactor
    Li Lei
    Zhang Zhijian
    2010 ASIA-PACIFIC POWER AND ENERGY ENGINEERING CONFERENCE (APPEEC), 2010,
  • [6] Application of Water Properties Table Lookup Method to Development of Thermal-Hydraulic Analysis Code in Real-time for Plate Type Fuel Reactor
    Li Lei
    Zhang Zhijian
    2010 ASIA-PACIFIC POWER AND ENERGY ENGINEERING CONFERENCE (APPEEC), 2010,
  • [7] Development and validation of a general two-fluid thermal-hydraulic analysis code for reactors with plate-type fuel assemblies
    Xia, Jianhua
    He, Hui
    Liu, Xiaojing
    Yang, Ting
    PROGRESS IN NUCLEAR ENERGY, 2023, 160
  • [8] Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies
    Castellanos-Gonzalez, Duvan A.
    Losada Moreira, Joao Manoel
    Maiorino, Jose Rubens
    Carajilescov, Pedro
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2018, 2018
  • [9] Development and Verification of Thermal-Hydraulic Transient Analysis Code in Plate-Type Fuel Nuclear Reactor
    Liu W.
    Zhang Y.
    Jiang X.
    Zhang C.
    Zhang D.
    Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (05): : 18 - 22
  • [10] THERMAL-HYDRAULIC FORTRAN PROGRAM FOR STEADY-STATE CALCULATIONS OF PLATE-TYPE FUEL RESEARCH REACTORS
    Khedr, Ahmed
    NUCLEAR TECHNOLOGY & RADIATION PROTECTION, 2008, 23 (01): : 19 - 30
12345