Development of Code for Steady-State Thermal-Hydraulic Analysis in Bimodal Space Nuclear Reactor with Heat Pipe

被引：0
|
作者：
State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, Xi'an [1 ]
710024, China
机构：
来源：
Hedongli Gongcheng | 1600年 / 5卷 / 34-39期
关键词：
Compilation and indexing terms; Copyright 2024 Elsevier Inc;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Code development - Space nuclear reactors - Space reactors - Steady state - Thermal hydraulic parameters - Thermal hydraulics - Thermal-hydraulic analysis - Thermal-hydraulic model
引用
收藏
相关论文
共 50 条
  • [21] 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
  • [22] Analysis of Thermal-hydraulic Characteristic of Solid Heat Pipe Reactor Simulator Device
    Zhang Y.
    Wang C.
    Tang S.
    Li J.
    Zhang D.
    Qiu S.
    Tian W.
    Su G.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2021, 55 (06): : 984 - 990
  • [23] Thermal-hydraulic analysis of heat pipe reactor experimental device with thermoelectric generators
    Zhang, Yin
    Chai, Xiaoming
    Wang, Chenglong
    Tang, Simiao
    Zhang, Dalin
    Tian, Wenxi
    Su, G.H.
    Qiu, Suizheng
    Progress in Nuclear Energy, 2022, 146
  • [24] Preliminary feasibility analysis of Heat Pipe Cooled Bimodal Space Nuclear Reactor
    Tian, Xiaoyan
    Li, Huaqi
    Jiang, Duoyu
    Zhu, Lei
    Chen, Sen
    Kang, Xiaoya
    PROGRESS IN NUCLEAR ENERGY, 2021, 138
  • [25] Steady state thermal-hydraulic analysis for the ETRR-2 Research Reactor
    Abdelrazek, ID
    Khalil, MY
    Shaat, MK
    Shokr, AM
    KERNTECHNIK, 2004, 69 (03) : 116 - 121
  • [26] 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
  • [27] UKAP - A CODE FOR THERMAL-HYDRAULIC ANALYSIS OF A REACTOR CORE
    HUHN, J
    KERNENERGIE, 1989, 32 (05): : 193 - 198
  • [28] Thermal-hydraulic Analysis of Pellet Bed Reactor for Space Nuclear Electric Propulsion
    Zhang R.
    Wang C.
    Qiu S.
    Tian W.
    Su G.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (07): : 1245 - 1254
  • [29] Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor
    Hu, B. X.
    Wu, Y. W.
    Tian, W. X.
    Su, G. H.
    Qiu, S. Z.
    ANNALS OF NUCLEAR ENERGY, 2013, 55 : 302 - 311
  • [30] Thermal-hydraulic analysis of pellet bed reactor for space nuclear electric propulsion
    Zhang, Ran
    Liang, Yu
    Liu, Xiao
    Wang, Chenglong
    Zhang, Dalin
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2020, 143
12345