Experimental study and kinetic analysis of sodium-water chemical reaction mechanism in steam generator of sodium-cooled fast reactor

被引：0
|
作者：
Kikuchi, Shin [1 ]
Seino, Hiroshi [1 ]
Kurihara, Akikazu [1 ]
Ohshima, Hiroyuki [1 ]
机构：
[1] Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Higashi-ibaraki-gun, Ibaraki, 311-1393, Japan
来源：
Nihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B | 2013年 / 79卷 / 799期
关键词：
D O I：
10.1299/kikaib.79.271
中图分类号：
学科分类号：
摘要：
引用
收藏
页码：271 / 275
相关论文
共 50 条
  • [41] A summary of sodium-cooled fast reactor development
    Aoto, Kazumi
    Dufour, Philippe
    Yang Hongyi
    Glatz, Jean Paul
    Kim, Yeong-il
    Ashurko, Yury
    Hill, Robert
    Uto, Nariaki
    PROGRESS IN NUCLEAR ENERGY, 2014, 77 : 247 - 265
  • [42] SODIUM-COOLED FAST REACTOR (SFR) SAFETY
    Sofu, Tanju
    INTERNATIONAL SEMINAR ON NUCLEAR WAR AND PLANETARY EMERGENCIES, 43RD SESSION, 2011, : 123 - 129
  • [43] A feasibility study of a steam methane reforming hydrogen production plant with a sodium-cooled fast reactor
    Chikazawa, Y
    Konomura, M
    Uchida, S
    Sato, H
    NUCLEAR TECHNOLOGY, 2005, 152 (03) : 266 - 272
  • [44] Analysis of Background Noise Power Spectrum for Steam Generator of Sodium Cooled Fast Reactor
    Cao Y.
    Liu G.
    Liu Z.
    Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (01): : 140 - 143
  • [45] Study on Thermal-hydraulic Steady-state Comprehensive Performance of Fast Reactor Sodium-water Steam Generator
    Xiao C.
    Yang H.
    Zhang D.
    Shen G.
    Qiu S.
    Lu Y.
    Zhang K.
    Huang Y.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2024, 58 (02): : 328 - 336
  • [46] Development of Sodium-cooled Fast Reactor Sodium Combined Fire Code
    Li S.
    Yu H.
    Ren L.
    Zhao L.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2020, 54 (10): : 1840 - 1848
  • [47] DESIGN CRITERIA FOR SODIUM-COOLED FAST REACTOR COMPONENTS
    SLEMBER, R
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (01): : 116 - &
  • [48] Experimental study on flow optimization in upper plenum of reactor vessel for a compact sodium-cooled fast reactor
    Kimura, N
    Hayashi, K
    Kamide, H
    Itoh, M
    Sekine, T
    NUCLEAR TECHNOLOGY, 2005, 152 (02) : 210 - 222
  • [49] SAFETY INSTRUMENTATION FOR SODIUM-COOLED FAST-REACTOR
    HALL, RS
    JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1974, 13 (02): : 173 - 181
  • [50] TRIBOLOGY IN CORE OF A SODIUM-COOLED FAST BREEDER REACTOR
    WILD, E
    MACK, KJ
    WEAR, 1975, 34 (03) : 331 - 340
12345