Study on Turbine System of Nuclear Power Plant Based on RELAP5/MOD3.4 Code

被引:0
|
作者
Wang S.-W. [1 ]
Peng M.-J. [1 ]
Liu J.-G. [1 ]
机构
[1] College of Nuclear Science and Technology, Harbin Engineering University, Harbin
来源
关键词
Relap5/Mod3.4; Secondary-loop; Turbine system;
D O I
10.1007/978-4-431-99779-5_45
中图分类号
学科分类号
摘要
In this paper, the secondary-loop steam turbine system has been modeled using RELAP5/MOD3.4 code. The operating conditions for the turbine load have been changed from 100% FP (full power) to 80% FP that have been simulated and which will explain transient analysis. These result shows that the transient performance of the steam turbine system components and theoretical analysis are identical, which demonstrated the reliability of the requisite program model. © Springer 2010.
引用
收藏
页码:286 / 291
页数:5
相关论文
共 50 条
  • [21] The Behavior of ANGRA 2 Nuclear Power Plant Core for a Small Break LOCA Simulated with RELAP5 Code
    Sabundjian, Gaiane
    Andrade, Delvonei A.
    Belchior, Antonio, Jr.
    Rocha, Marcelo da Silva
    Conti, Thadeu N.
    Torres, Walmir M.
    Macedo, Luiz A.
    Umbehaun, Pedro E.
    Mesquita, Roberto N.
    Masotti, Paulo H. F.
    de Souza Lima, Ana Cecilia
    XXXV BRAZILIAN WORKSHOP ON NUCLEAR PHYSICS, 2013, 1529 : 151 - 154
  • [22] MNSR transient analysis using the RELAP5/Mod3.2 code
    Dawahra, S.
    Khattab, K.
    Alhabit, F.
    NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (09) : 1990 - 1997
  • [23] RELAP5 NUCLEAR-PLANT ANALYZER CAPABILITIES
    WAGNER, RJ
    RANSOM, VH
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1982, 43 : 381 - 382
  • [24] 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
  • [25] Simulation of loss-of-flow transient in a VVER-1000 nuclear power plant with RELAP5/MOD3.2
    Grudev, P
    Pavlova, M
    PROGRESS IN NUCLEAR ENERGY, 2004, 45 (01) : 1 - 10
  • [26] THEORETICAL ANALYSIS OF A NATURAL CIRCULATION SYSTEM UNDER ROLLING CONDITION BASED ON RELAP5/MOD3.3 CODE
    Lian, Haibo
    Zhu, Hongye
    Yang, Xingtuan
    Jiang, Shengyao
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 2, 2014,
  • [27] THE RELAP5-FORCE MOD2 CODE, A HYDRODYNAMIC FORCING FUNCTION CALCULATION VERSION OF RELAP5
    CAJIGAS, JM
    NUCLEAR TECHNOLOGY, 1990, 90 (03) : 316 - 325
  • [28] Development and Verification of Thermal-hydraulic System Analysis Code Based on RELAP5 MOD3.2 for SFRs
    Song J.
    Tan C.
    Tang S.-M.
    Liu L.-M.
    Tian W.-X.
    Wu Y.-W.
    Qiu S.-Z.
    Su G.-H.
    1600, Atomic Energy Press (51): : 994 - 1001
  • [29] Development of a thermal-hydraulic system code for simulators based on RELAP5 code
    Lin, M
    Su, Y
    Hu, R
    Zhang, RH
    Yang, YH
    NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (06) : 675 - 686