Modeling by RELAP5 in nuclear power plant engineering simulator

被引：0
|
作者：
机构：
[1] Lin, Meng
[2] Su, Yun
[3] Hu, Rui
[4] Yang, Yan-Hua
来源：
Lin, M. | 2005年 / Atomic Energy Publishing House卷 / 39期
关键词：
Computer simulation - Computer software - Models - Numerical methods;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
Thermal hydraulic calculation module RELAP5 is one part of digital reactor system (DRS). The modeling method by RELAP5 is described. There are mainly following 3 steps: the first is modification of RELAP5 source code; the second is constructing normal model; the third is establishing special model. Thus besides plant-running parameters can be dynamically extracted from RELAP5, it can be dynamically changed in RELAP5. This model is strong enough to meet the needs of nuclear power plant engineering simulator.
引用
收藏
相关论文
共 50 条
  • [1] Animation model of Krsko nuclear power plant for RELAP5 calculations
    Prosek, Andrei
    Mavko, Borut
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (04) : 1034 - 1046
  • [2] VERIFICATION OF THE AP1000 NUCLEAR POWER PLANT SIMULATOR NPPSIM AGAINST RELAP5 FOR TRANSIENT ANALYSIS
    Wu, Shifa
    Wang, Pengfei
    Fang, Huawei
    Wei, Xinyu
    Zhao, Fuyu
    PROCEEDINGS OF THE 24TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2016, VOL 5, 2016,
  • [3] RELAP5 NUCLEAR-PLANT ANALYZER CAPABILITIES
    WAGNER, RJ
    RANSOM, VH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 43 : 381 - 382
  • [4] A web-based nuclear simulator using RELAP5 and LabVIEW
    Kim, K. D.
    Rizwan-uddin
    NUCLEAR ENGINEERING AND DESIGN, 2007, 237 (11) : 1185 - 1194
  • [5] Sensitivity Analysis of Relap5 Simulation on AP1000 Nuclear Power Plant
    谢明亮
    谢飞
    单福昌
    谢政权
    JournalofDonghuaUniversity(EnglishEdition), 2018, 35 (01) : 94 - 100
  • [6] RELAP5 Analysis of Krsko Nuclear Power Plant Abnormal Event from 2011
    Prosek, Andrej
    Matkovic, Marko
    23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014), 2014,
  • [7] ABWR power tests simulation by using a dual RELAP5 nuclear power plant simulation platform
    Yang, Chung-Yu
    Dai, L. C.
    Liang, Thomas K. S.
    Pei, B. S.
    Shih, C. K.
    Wang, L. C.
    Chiang, S. C.
    NUCLEAR ENGINEERING AND DESIGN, 2012, 249 : 41 - 48
  • [8] MODELING AND LOSS-OF-COOLANT ACCIDENT ANALYSIS OF A NUCLEAR-POWER-PLANT USING RELAP5/MOD2
    SALIM, P
    HASSAN, YA
    NUCLEAR TECHNOLOGY, 1990, 90 (03) : 275 - 285
  • [9] RELAP5 CONSTITUTIVE RELATIONS MODELING
    RANSOM, VH
    KISER, DM
    CHOW, H
    LIN, JC
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 41 : 671 - 672
  • [10] APPLICATION OF RELAP5 MOD2 TO LOVIISA NUCLEAR-POWER-PLANT OVERCOOLING TRANSIENTS
    KANTEE, H
    TUOMISTO, H
    YRJOLA, V
    NUCLEAR TECHNOLOGY, 1990, 90 (03) : 308 - 315
12345