LOCA Analysis of Super Fast Reactor

被引:2
|
作者
Ikejiri, Satoshi [1 ]
Han, Chi Young [1 ]
Ishiwatari, Yuki [2 ]
Oka, Yoshiaki [1 ,2 ]
机构
[1] Univ Tokyo, Nucl Profess Sch, Tokai, Ibaraki 3191188, Japan
[2] Univ Tokyo, Dept Nucl Engn & Management, Bunkyo Ku, Tokyo 1138656, Japan
关键词
Super Fast Reactor; loss of coolant accident; once-through coolant cycle; downward flow cooled fuel assembly; blowdown; reflooding; depressurization; automatic depressurization system; low-pressure core spray;
D O I
10.3327/jnst.48.1289
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This paper describes loss of coolant accident (LOCA) analyses of the Supercritical-pressure Water-Cooled Fast Reactor (Super Fast Reactor). The features of the Super Fast Reactor are high power density and downward flow cooled fuel channels for the improvement of the economic potential of the Super Fast Reactor with high outlet steam temperature. The LOCA induces large pressure and coolant density change in the core. This change influences the flow distribution among the downward flow parallel channels. It will affect the safety of the Super Fast Reactor. LOCA analysis of Super Fast Reactor is important to understand the safety features of the Super Fast Reactor. Keeping the flow rate in the core is important for the safety of the Super Fast Reactor. In LOCA, it is difficult to maintain an adequate flow rate clue to the once-through coolant cycle and the downward flow cooled fuel assemblies. Therefore, the early actuation of the Automatic Depressurization System (ADS) and reduction of the maximum linear heat generation rates of the downward flow seed fuel assemblies and Low-Pressure Core Spray (LPCS) system are necessary for the Super Fast Reactor to cool the core under LOCA. Analysis results show that the Super Fast Reactor can satisfy the safety criteria with these systems.
引用
收藏
页码:1289 / 1299
页数:11
相关论文
共 50 条
  • [21] Analysis of anticipated transient without scram of a Super Fast Reactor with single flow pass core
    Sutanto
    Oka, Yoshiaki
    ANNALS OF NUCLEAR ENERGY, 2015, 75 : 54 - 63
  • [22] Development of a LOCA safety analysis evaluation model for the Westinghouse Small Modular Reactor
    Liao, Jun
    Kucukboyaci, Vefa N.
    Wright, Richard F.
    ANNALS OF NUCLEAR ENERGY, 2016, 98 : 61 - 73
  • [23] PRELIMINARY LARGE BREAK LOCA AND SGTR ACCIDENT ANALYSIS OF THE COMPACT SMALL REACTOR
    Xing, Mian
    Li, Linsen
    Shen, Feng
    Hu, Xiao
    Liu, Zhan
    Qi, Zhanfei
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 4, 2017,
  • [24] The effect of noncondensables on condensation in reactor LOCA transients
    Young, MY
    Bajorek, SM
    HEAT TRANSFER - BALTIMORE 1997, 1997, (214): : 6 - 13
  • [25] Experimental simulation on LOCA of a nuclear heating reactor
    Bo, Jinhai
    Zhang, Youjie
    Wu, Shaorong
    Zhang, Xuesong
    He, Xuedong
    Qinghua Daxue Xuebao/Journal of Tsinghua University, 1995, 35 (12): : 74 - 77
  • [26] PARAMETRIC CALCULATIONS OF LOCA FOR VVER 440 REACTOR
    MISAK, J
    JADERNA ENERGIE, 1978, 24 (01): : 15 - 22
  • [27] Improvements of two-pass core design for super fast reactor
    Liu, Qingjie
    Oka, Yoshiaki
    ANNALS OF NUCLEAR ENERGY, 2014, 69 : 108 - 115
  • [28] In-box LOCA accident analysis for the European DEMO water-cooled reactor
    D'Onorio, Matteo
    Giannetti, Fabio
    Caruso, Gianfranco
    Porfiri, Maria Teresa
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 732 - 735
  • [29] FAST BREEDER REACTOR VESSEL ANALYSIS
    FOX, GL
    COMBUSTION, 1971, 43 (01): : 21 - &
  • [30] FAST-REACTOR SAFETY ANALYSIS
    LEIGH, KM
    NUCLEAR ENERGY-JOURNAL OF THE BRITISH NUCLEAR ENERGY SOCIETY, 1978, 17 (03): : 225 - 228