Simulation of loss-of-flow transient in a radiant steam boiler with Relap5/Mod3.2

被引:0
|
作者
Deghal Cheridi, A.L. [1 ]
Chaker, A. [2 ]
Loubar, A. [1 ]
机构
[1] Nuclear Research Center, BP 180, Djelfa, Ain Oussera, Algeria
[2] Mentouri University, Constantie, Algeria
关键词
D O I
暂无
中图分类号
学科分类号
摘要
引用
收藏
页码:42 / 46
相关论文
共 50 条
  • [31] IMPLEMENTATION OF LIQUID METAL PROPERTIES IN RELAP5 MOD3.2 FOR SAFETY ANALYSIS OF SODIUM-COOLED FAST REACTORS
    Song, Jian
    Liu, Limin
    Tang, Simiao
    Wu, Yingwei
    Tian, Wenxi
    Qiu, Suizheng
    Su, Guanghui
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 9, 2017,
  • [33] Interactive Graphical Analyzer based on RELAP5/mod 3.2 -: NPA
    Posada, JM
    Martín, M
    Reventós, F
    Llopis, C
    PROCEEDINGS OF THE 2ND CSNI SPECIALIST MEETING ON SIMULATORS AND PLANT ANALYSERS, 1999, 194 : 587 - 600
  • [34] 基于修改后RELAP5/MOD3.2的氟盐高温堆实验回路分析
    许荣栓
    刘利民
    王宁
    张大林
    王成龙
    秋穗正
    苏光辉
    原子能科学技术, 2017, 51 (05) : 828 - 835
  • [35] Condensation experiment in the presence of noncondensables in a vertical tube of a passive containment cooling system and its assessment with RELAP5/MOD3.2
    Park, Hyun Sik
    No, Hee Cheon
    Nuclear Technology, 127 (02): : 160 - 169
  • [36] 三维瞬态物理分析模型与RELAP5/mod3.2程序的耦合研究
    陈玉清
    蔡琦
    于雷
    核动力工程 , 2010, (03) : 9 - 13
  • [37] A condensation experiment in the presence of noncondensables in a vertical tube of a passive containment cooling system and its assessment with RELAP5/MOD3.2
    Park, HS
    No, HC
    NUCLEAR TECHNOLOGY, 1999, 127 (02) : 160 - 169
  • [38] Assessment of RELAP5/MOD3.2 for simulating density wave oscillation with a two-phase natural circulation test facility
    Teng, Chen
    Xie, Heng
    Jia, Haijun
    NUCLEAR ENGINEERING AND DESIGN, 2021, 381
  • [39] Validation of RELAP5/MOD3.2 code for simulating nucleate pool boiling heat transfer outside vertical tube bundle
    20160902019356
    (1) Harbin Engineering University, Harbin, Heilongjiang, China, 1600, et al.; GLSEQ, LLC/SCI Technologies. Inc; Hitachi-GE Nuclear Energy, Ltd.; Mitsubishi Heavy Industries, Ltd. (MHI); Toshiba Corporation; Westinghouse Electric Company (American Society of Mechanical Engineers (ASME), United States):
  • [40] Loss-of-heat-sink transient simulation with RELAP5/Mod3.3 code for the ATHENA facility
    Del Moro, T.
    Giannetti, F.
    Puviani, P. Cioli
    Di Piazza, I.
    Diamanti, D.
    Tarantino, M.
    ANNALS OF NUCLEAR ENERGY, 2025, 211