Thermal-hydraulic analysis of lead-bismuth cooled reactors core based on single channel model

被引：0
|
作者：
Mei, Huaping [1 ]
Liu, Shuyong [1 ,2 ]
Chen, Chao [1 ,2 ]
Zhang, Jiansong [1 ,2 ]
Li, Taosheng [1 ,2 ]
机构：
[1] Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Anhui Province, Hefei, China
[2] University of Science and Technology of China, Anhui, Hefei, China
来源：
International Journal of Nuclear Energy Science and Technology | 2024年 / 17卷 / 2-3期
关键词：
Compendex;
D O I：
10.1504/IJNEST.2024.142757
中图分类号：
学科分类号：
摘要：
Uranium dioxide
引用
收藏
页码：180 / 196
相关论文
共 50 条
  • [31] Conceptual design and thermal-hydraulic analysis of a megawatt-level lead-bismuth cooling reactor for deep-sea exploration
    Yang, Qing
    Sun, Qizheng
    Liu, Xiaojing
    He, Hui
    Zhang, Tengfei
    Chai, Xiang
    Luo, Yuejian
    PROGRESS IN NUCLEAR ENERGY, 2022, 145
  • [32] Determination of the maximum core power of natural circulation lead-bismuth reactors
    Xiao Y.
    Peng L.
    Zhao P.
    Li Q.
    Luo W.
    Yu T.
    He Jishu/Nuclear Techniques, 2023, 46 (09):
  • [33] Research on single channel and subchannel in thermal-hydraulic analysis of TP-1 sodium cooled TWR
    Wei, Hong-Yang
    Tian, Wen-Xi
    Cong, Teng-Long
    Huang, Hao
    Su, Guang-Hui
    Qiu, Sui-Zheng
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (12): : 2261 - 2266
  • [34] Thermal-Hydraulic and Neutronic Analysis of a Reentrant Fuel-Channel Design for Pressure-Channel Supercritical Water-Cooled Reactors
    Peiman, W.
    Pioro, I.
    Gabriel, K.
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2015, 1 (02):
  • [35] Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors
    Zhang, Yan
    Wang, Chenglong
    Lan, Zhike
    Wei, Shiying
    Chen, Ronghua
    Tian, Wenxi
    Su, Guanghui
    RENEWABLE & SUSTAINABLE ENERGY REVIEWS, 2020, 120
  • [36] Transient thermal-hydraulic simulations of direct cycle gas cooled reactors
    Tauveron, N
    Saez, M
    Marchand, M
    Chataing, T
    Geffraye, G
    Bassi, C
    NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (23) : 2527 - 2545
  • [37] Innovative nuclear technology based on modular multi-purpose lead-bismuth cooled fast reactors
    Zrodnikov, A. V.
    Toshinsky, G. I.
    Komlev, O. G.
    Dragunov, Yu. G.
    Stepanov, V. S.
    Klimov, N. N.
    Generalov, V. N.
    Kopytov, I. I.
    Krushelnitsky, V. N.
    PROGRESS IN NUCLEAR ENERGY, 2008, 50 (2-6) : 170 - 178
  • [38] Analysis of cell configuration effects on nuclear characteristics in a lead-bismuth cooled core for TRU incineration
    Kim, YN
    Kim, JK
    Park, WS
    Park, YS
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2005, 42 (10) : 916 - 926
  • [39] Polonium evaporation and adhesion experiments for the development of polonium filter in lead-bismuth cooled reactors
    Obara, Toru
    Koga, Takeru
    Miura, Terumitsu
    Sekimoto, Hiroshi
    PROGRESS IN NUCLEAR ENERGY, 2008, 50 (2-6) : 556 - 559
  • [40] Optimization of Oxygen Control Strategy for Corrosion Mitigation in Lead-Bismuth Cooled Fast Reactors
    Chen, Jiajie
    Wang, Shiwei
    He, Hui
    Liu, Xiaojing
    Xiong, Jinbiao
    Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 (06): : 280 - 289
12345