APPLICATION OF A HYBRID COMPUTER TO ANALYSIS OF TRANSIENT PHENOMENA IN A FAST REACTOR CORE

被引:0
|
作者
SANATHAN.CK
CARTER, JC
BRYANT, LT
AMIOT, LW
机构
来源
关键词
D O I
暂无
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
引用
收藏
页码:272 / &
相关论文
共 50 条
  • [21] Experimental and numerical analysis of fast transient phenomena in distribution transformers
    Van Craenenbroeck, T
    De Ceuster, J
    Marly, JP
    De Herdt, H
    Brouwers, B
    Van Dommelen, MD
    2000 IEEE POWER ENGINEERING SOCIETY WINTER MEETING - VOLS 1-4, CONFERENCE PROCEEDINGS, 2000, : 2193 - 2198
  • [22] Transient analysis of the CiADS reactor core loaded with nitride fuel
    Liu, Bo
    Li, Song
    Zhang, You-Peng
    Wallenius, Janne
    Xi, Bin
    Gu, Long
    Li, Jin-Yang
    Wang, Di-Si
    Jiang, Wei
    Zhang, Lu
    ANNALS OF NUCLEAR ENERGY, 2023, 182
  • [23] CORA - TRANSIENT ANALYSIS CODE FOR A CLUSTER OF REACTOR CORE ASSEMBLIES
    JOHNSON, HG
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1979, 32 (JUN): : 533 - 534
  • [24] Hybrid parallel strategy for the simulation of fast transient accidental situations at reactor scale
    Faucher, V.
    Galon, P.
    Beccantini, A.
    Crouzet, F.
    Debaud, F.
    Gautier, T.
    ANNALS OF NUCLEAR ENERGY, 2015, 82 : 188 - 194
  • [25] Hybrid parallel strategy for the simulation of fast transient accidental situations at reactor scale
    Faucher, V.
    Galon, P.
    Beccantini, A.
    Crouzet, F.
    Debaud, F.
    Gautier, T.
    SNA + MC 2013 - JOINT INTERNATIONAL CONFERENCE ON SUPERCOMPUTING IN NUCLEAR APPLICATIONS + MONTE CARLO, 2014,
  • [26] THEORETICAL AND COMPUTER ANALYSIS ON BEHAVIOR OF FAST REACTOR FUEL PINS AND RELATED PARTS OF CORE UNDER OPERATIONAL CONDITIONS
    KARSTEN, G
    KAMPF, H
    GERKEN, A
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1968, 11 (02): : 513 - &
  • [28] Application of a 3D model in the transient system analysis of sodium-cooled fast reactor
    Ge Li
    Lu Tianyu
    Shan Jianqiang
    Liu Dong
    ANNALS OF NUCLEAR ENERGY, 2020, 135
  • [29] Safety Analysis of Demonstration Fast Reactor Core Melt Collector
    Liu Z.
    Hu J.
    Gong J.
    Cao J.
    Gao F.
    Xuan F.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (08): : 1445 - 1450
  • [30] The results of analysis of sodium fast reactor core melting accident
    Usynin, G.B.
    Vlasichev, G.N.
    Anoshkin, Yu.I.
    Semenychev, M.A.
    Boldin, S.V.
    Atomnaya Energiya, 1992, 73 (06): : 433 - 438