Simulation of loss-of-flow transient in a VVER-1000 nuclear power plant with RELAP5/MOD3.2

被引:14
|
作者
Grudev, P [1 ]
Pavlova, M [1 ]
机构
[1] Bulgarian Acad Sci, Inst Nucl Res & Nucl Energy, BU-1784 Sofia, Bulgaria
关键词
VVER-1000; loss of flow transient; RELAP5/MOD; 3.2; code;
D O I
10.1016/j.pnucene.2004.08.001
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
A RELAP5/MOD3.2 model of a VVER-1000 (V-320 model) nuclear power plant was updated, improved and validated against actual plant data. The data included steady-state and operational transient results from unit 6 of the Kozloduy nuclear power plant. The operational transient was initiated by a loss of flow at partial power conditions caused by the trip of a main coolant pump without reactor scram. The assessment of the model has been performed in two stages: an initial validation against steady-state plant data and then a transient validation by comparison to operational transient data. The comparison between the plant data and the results of the calculation proved the adequacy of the model and demonstrated the capability of the code to reproduce the evolution of the main plant parameters. (C) 2004 Published by Elsevier Ltd.
引用
收藏
页码:1 / 10
页数:10
相关论文
共 50 条
  • [1] Simulation of two loss-of-flow transients in a VVER-1000 nuclear power plant with RELAP5/MOD3.2 system code
    Hassan, YA
    Moscalu, DR
    [J]. NUCLEAR TECHNOLOGY, 2000, 129 (01) : 82 - 92
  • [2] RELAP5/MOD3.2 investigation of a VVER-1000 MCP switching on Benchmark problem
    Groudev, PP
    Stefanova, AE
    [J]. ANNALS OF NUCLEAR ENERGY, 2005, 32 (04) : 399 - 416
  • [3] Analysis of the loss of heat sink transients in the secondary circuit of a VVER-1000 using RELAP5/MOD3.2
    Abbasi, Somayeh
    Hadad, Kamal
    [J]. ANNALS OF NUCLEAR ENERGY, 2012, 47 : 28 - 37
  • [4] Simulation of a control rod ejection accident in a VVER-1000/V446 using RELAP5/Mod3.2
    Tabadar, Z.
    Hadad, K.
    Nematollahi, M. R.
    Jabbari, M.
    Khaleghi, M.
    Hashemi-Tilehnoee, M.
    [J]. ANNALS OF NUCLEAR ENERGY, 2012, 45 : 106 - 114
  • [5] Validation of RELAP5/MOD3.2 model of VVER440 on reactor scram transient
    Groudev, P
    Stefanova, A
    [J]. PROGRESS IN NUCLEAR ENERGY, 2006, 48 (02) : 146 - 154
  • [6] RELAP5/MOD3.2 analysis of a VVER-1000 reactor with UO2 fuel and mixed-oxide fuel
    Hassan, YA
    Fu, C
    [J]. NUCLEAR TECHNOLOGY, 2004, 148 (03) : 325 - 334
  • [7] MNSR transient analysis using the RELAP5/Mod3.2 code
    Dawahra, S.
    Khattab, K.
    Alhabit, F.
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (09) : 1990 - 1997
  • [8] Assessment and improvement of condensation models in RELAP5/MOD3.2
    Choi, KY
    Park, HS
    Kim, SJ
    No, HC
    Bang, YS
    [J]. NUCLEAR TECHNOLOGY, 1998, 124 (02) : 103 - 117
  • [9] Simulation of VVER-1000 Guillotine Large Break Loss of Coolant Accident Using RELAP5/SCDAPSIM/MOD3.5
    Thulu, Fabiano Gibson Daud
    Elshahat, Ayah
    Hassan, Mohamed H. M.
    [J]. JOURNAL OF NUCLEAR ENGINEERING, 2021, 2 (04): : 516 - 532
  • [10] Thermal-hydraulic modeling for deterministic safety analysis of portable equipment application in the VVER-1000 nuclear reactor during loss of ultimate heat sink accident using RELAP5/MOD3.2 code
    Tabadar, Z.
    Ansarifar, G. R.
    Pirouzmand, A.
    [J]. ANNALS OF NUCLEAR ENERGY, 2019, 127 : 53 - 67