Global stability analysis of pressurized water reactor core nonlinear system

被引:0
|
作者
机构
[1] Li, Gang
[2] Zhao, Fu-Yu
[3] Liu, Yang
来源
Li, G. | 1600年 / Atomic Energy Press卷 / 47期
关键词
Nonlinear systems - Nuclear power plants - Nuclear fuels - Perturbation techniques - System stability;
D O I
10.7538/yzk.2013.47.02.0271
中图分类号
学科分类号
摘要
引用
收藏
相关论文
共 50 条
  • [41] Global physical and numerical stability of a nuclear reactor core
    Morales-Sandoval, J
    Hernández-Solís, A
    ANNALS OF NUCLEAR ENERGY, 2005, 32 (15) : 1666 - 1678
  • [42] Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor
    Pilehvar, A. F.
    Esteki, M. H.
    Ansarifar, G. R.
    Hedayat, A.
    ANNALS OF NUCLEAR ENERGY, 2020, 139
  • [43] ANALYSIS OF POWER DISTRIBUTION CONTROL-SYSTEM STABILITY IN A REACTOR CORE
    FILIPCHU.EV
    POTAPENK.PT
    KOSILOV, AN
    ATOMNAYA ENERGIYA, 1973, 35 (05): : 317 - 321
  • [44] TRANSIENT ANALYSIS OF INTEGRAL PRESSURIZED WATER REACTOR (IPWR)
    Khan, Salah Ud-Din
    Khan, Shahab Ud-Din
    22ND INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2013), 2013,
  • [45] Development of a Simplified Pressurized Water Reactor Fuel Assembly Nonlinear Model
    Park, Namgyu
    Yoo, Youngik
    Kim, Taesoon
    Jeon, Sangyoun
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2022, 144 (05):
  • [46] A CONSISTENT TECHNIQUE FOR THE GLOBAL HOMOGENIZATION OF A PRESSURIZED WATER-REACTOR ASSEMBLY
    HEBERT, A
    BENOIST, P
    NUCLEAR SCIENCE AND ENGINEERING, 1991, 109 (04) : 360 - 372
  • [47] Analysis of degassing time of pressurized water reactor pressurizer
    Zhong, Xianping
    Yu, Jiyang
    Guo, Xiaoyu
    Saeed, Muhammad
    NUCLEAR ENGINEERING AND DESIGN, 2018, 328 : 301 - 308
  • [48] QUALITY ANALYSIS IN PRESSURIZED WATER REACTOR-FUEL
    DAROLLES, JF
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 20 (APR21): : 572 - 574
  • [49] Cycle-overlapping Analysis of Faults in Pressurized Water Reactors with Assumed Recriticality of the Reactor Core.
    Boehm, R.
    Finnemann, H.
    Roth-Seefrid, H.
    VGB-Kraftwerkstechnik, 1984, 64 (02): : 94 - 100
  • [50] Optimization and Analysis for Passive Residual Heat Removal System of an Integral Pressurized Water Reactor
    Dai Shoubao
    Peng Minjun
    Liu Jiange
    ICONE17, VOL 4, 2009, : 517 - 522