Study on in-core physical design limit zone for lead bismuth eutectic cooled long-life cycle reactor

被引：0
|
作者：
Liu, Xiao-Li [1 ]
Xian, Chun-Yu [1 ]
机构：
[1] National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu 610041, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2008年 / 29卷 / 04期
关键词：
Life cycle;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：1 / 4
相关论文
共 50 条
  • [31] Study on Jet Mixing Characteristics of Lead-Bismuth Eutectic Cooled Reactor Assembly Head Based on CFD Method
    Zhang, Ji
    Wang, Yingjie
    Wang, Mingjun
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    Hedongli Gongcheng/Nuclear Power Engineering, 2024, 45 (04): : 77 - 86
  • [32] Conceptual Design study of Small Long-life Gas Cooled Fast Reactor With Modified CANDLE Burn-up Scheme
    Asiah, Nur A.
    Su'ud, Zaki
    Ferhat, A.
    Sekimoto, H.
    2ND INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING - ICANSE 2009, 2010, 1244 : 31 - +
  • [33] Physical design of a thorium fuel-based long life reactor core
    Yu, Gang-Lin
    Wang, Kan
    Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (SUPPL. 2): : 116 - 120
  • [34] Design study of long-life Pb-Bi cooled fast reactor with natural uranium as fuel cycle input using modified CANDLE burn-up scheme
    Su'ud Z.
    Sekimoto H.
    International Journal of Nuclear Energy Science and Technology, 2010, 5 (04) : 347 - 368
  • [35] STUDY OF JET CHARACTERISTICS AND STRUCTURAL FATIGUE IN THE UPPER CHAMBER OF A LEAD-BISMUTH EUTECTIC COOLED REACTOR BASED ON FLUIDSTRUCTURE COUPLING METHODS
    Zhang, Ji
    Wang, Mingjun
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 11, ICONE31 2024, 2024,
  • [36] Conceptual Design Study of Small Long-Life PWR based on Thorium Cycle Fuel
    Subkhi, M. Nurul
    Su'ud, Zaki
    Waris, Abdul
    Permana, Sidik
    4TH INTERNATIONAL CONFERENCE ON ADVANCES IN NUCLEAR SCIENCE AND ENGINEERING (ICANSE 2013), 2014, 1615 : 61 - 64
  • [37] RETRACTION: Core design and analysis of a lead-bismuth cooled small modular reactor (Retraction of Vol 133, Pg 511, 2019)
    Wang, Chenglong
    Wei, Shiying
    Tian, Wenxi
    Qiu, Suizheng
    Su, G. H.
    ANNALS OF NUCLEAR ENERGY, 2022, 179
  • [38] Design and optimization of intermediate heat exchanger for lead-bismuth cooled fast reactor coupled with supercritical carbon dioxide Brayton cycle
    Qiao, Jianxin
    Liu, Shenghui
    Meng, Jiatao
    Zhu, Xiaoliang
    Xing, Tianyang
    Jiang, Mudi
    Huang, Yanping
    Yang, Liu
    NUCLEAR ENGINEERING AND DESIGN, 2023, 414
  • [39] Optimization of core design to achieve ultra-long core life in alternative ways for modular gas cooled fast reactor
    Islam, Shohanul
    ANNALS OF NUCLEAR ENERGY, 2025, 215
  • [40] A conceptual design study of a small natural convection lead-bismuth-cooled reactor without refueling for 30 years
    Chikazawa, Y
    Konomura, M
    Mizuno, T
    Mito, M
    Tanji, M
    NUCLEAR TECHNOLOGY, 2006, 154 (02) : 142 - 154
12345