Safety analysis of a supercritical-pressure water-cooled fast reactor under supercritical pressure

被引:22
|
作者
Ikejiri, Satoshi [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 & Managemnt, Tokai, Ibaraki 3191188, Japan
关键词
COOLANT VOID REACTIVITY; FAST BREEDER REACTOR; SUPER LWR;
D O I
10.1016/j.nucengdes.2009.12.034
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
The supercritical-pressure water-cooled fast reactor (SWFR) is a fast spectrum supercritical water-cooled reactor (SCWR) studied by the University of Tokyo The SWFR is designed as a two-pass core with an outlet temperature 500 degrees C The SWFR has fuel channels cooled by downward flow, higher power density, and smaller coolant density reactivity feedback compared with Super LWR. This paper describes the safety analyses of abnormal events for the SWFR. SPRAT-F code is used for the safety analysis at supercritical pressure considering the downward flow cooled seed fuel channel This code is based On a 1-D node junction model with point kinetics and decay heat calculations Flow redistribution among parallel paths is calculated by pressure-loss balance and momentum conservation The initiating events are selected from those of LWRs. For the safety analysis, nine abnormal transients and four accidents are selected with considering types of abnormality By the numerical analyses, It was found that the loss of flow events can be mitigated by the "water source" effect of the downward flow blanket channels in the abnormal transients and accidents All the abnormal events satisfy the criteria with margin (C) 2010 Elsevier B.V All rights reserved
引用
收藏
页码:1218 / 1228
页数:11
相关论文
共 50 条
  • [41] Improved core design of the high temperature supercritical-pressure light water reactor
    Yamaji, A
    Kamei, K
    Oka, Y
    Koshizuka, S
    [J]. ANNALS OF NUCLEAR ENERGY, 2005, 32 (07) : 651 - 670
  • [42] Subchannel analysis of a fast reactor cooled by supercritical light water
    Mukohara, T
    Koshizuka, S
    Oka, Y
    [J]. PROGRESS IN NUCLEAR ENERGY, 2000, 37 (1-4) : 197 - 204
  • [43] Supercritical Water-Cooled Reactors
    Cai, Jiejin
    Renault, Claude
    Gou, Junli
    [J]. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2014, 2014
  • [44] Reactors Cooled by Water at Supercritical Pressure
    Silin V.A.
    Zorin V.M.
    Khlopov R.A.
    [J]. Silin, V.A. (alarik1181@mail.ru), 1600, Springer Science and Business Media, LLC (48): : 222 - 231
  • [45] Hydrodynamic Characteristics Analysis of Supercritical Water in Water-cooled Wall of Supercritical Boiler
    Hao, Xiao-Hong
    Xu, Pei-Xing
    Ma, Da-Fu
    [J]. Kung Cheng Je Wu Li Hsueh Pao/Journal of Engineering Thermophysics, 2019, 40 (10): : 2334 - 2339
  • [46] Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water
    Sukarman
    Yamaji, Akifumi
    Someya, Takayuki
    [J]. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2018, 4 (01):
  • [47] Conceptual design of compact supercritical water-cooled fast reactor with thermal hydraulic coupling
    Yoo, Jaewoon
    Ishiwatari, Yuki
    Oka, Yoshiaki
    Liu, Jie
    [J]. ANNALS OF NUCLEAR ENERGY, 2006, 33 (11-12) : 945 - 956
  • [48] Supercritical-pressure water cooled thermal reactor with uranium–plutonium–thorium fuel cycle and bidirectional coolant flow articles
    A. P. Glebov
    A. V. Klushin
    [J]. Atomic Energy, 2009, 106 : 305 - 315
  • [49] DESIGN OF WATER ROD CORES OF A DIRECT CYCLE SUPERCRITICAL-PRESSURE LIGHT-WATER REACTOR
    OKANO, Y
    KOSHIZUKA, S
    OKA, Y
    [J]. ANNALS OF NUCLEAR ENERGY, 1994, 21 (10) : 601 - 611
  • [50] Fuel Assembly Concept of the Canadian Supercritical Water-Cooled Reactor
    Yetisir, Metin
    Hamilton, Holly
    Xu, Rui
    Gaudet, Michel
    Rhodes, David
    King, Mitch
    Andrew, Kittmer
    Benson, Ben
    [J]. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2018, 4 (01):