A study of large break LOCA in the AP1000 reactor containment

被引:29
|
作者
Rahim, Farzad Choobdar [1 ,2 ]
Rahgoshay, Mohammad [1 ]
Mousavian, Seyed Khalil [3 ]
机构
[1] Islamic Azad Univ Tehran, Fac Engn, Sci & Res Branch, Tehran, Iran
[2] Urmia Univ, Dept Mech Engn, Orumiyeh, Iran
[3] Atom Energy Org Iran AEOI, Reactors & Accelerators Res & Dev Sch, Nucl Sci & Technol Res Inst NSTRI, Tehran 1439951113, Iran
关键词
AP1000; reactor; Containment; LOCA; Two phase; Two volumes; Heat transfer;
D O I
10.1016/j.pnucene.2011.07.004
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
In this paper, one of the most dangerous accidents in reactor containments known as Loss of Coolant Accident (LOCA) in its worst condition called large LOCA has been modelled. The specific type of large LOCA is DECL (Double Ended Cold Leg) break which means a total guillotine type of break in cold leg pipe. When 'LOCA' occurs, the coolant itself is lost, then in this case that happens with pipe break or any kind of losing, the danger of core melting is possible. This modelling is performed in two volumes method in AP1000 reactor which is one of the most sophisticated safe reactors that has ever been built. Its safety systems provide a large variety of safety margins. One of the most important safety features in AP1000 is its passivity. This advantage provides many simplifications to enhance the safety, reliability, construction, operation, maintenance, investment, protection and plant costs. Therefore, it is worthwhile and makes sense to perform the analysis of a most dangerous accident in one of the most secure reactors. The modelling software applied in our analysis is MATLAB, and the results are compared with the AP1000 safety, security and environmental reports. (C) 2011 Elsevier Ltd. All rights reserved.
引用
收藏
页码:132 / 137
页数:6
相关论文
共 50 条
  • [1] THE ACC CONFIGURATION SENSITIVITY STUDY FOR AP1000 LARGE BREAK LOCA
    Yu Jianhui
    [J]. PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 4, 2014,
  • [2] AP1000® Large-Break LOCA BEPU analysis with TRACE code
    Queral, C.
    Montero-Mayorga, J.
    Gonzalez-Cadelo, J.
    Jimenez, G.
    [J]. ANNALS OF NUCLEAR ENERGY, 2015, 85 : 576 - 589
  • [3] THE ANALYSIS OF AP1000 DEPRESSURIZATION DURING SMALL BREAK LOCA
    He, Shuangji
    [J]. PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 3, 2014,
  • [4] RELAP5/SCDAPSIM model development for AP1000 and verification for large break LOCA
    Trivedi, A. K.
    Allison, C.
    Khanna, A.
    Munshi, P.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2016, 305 : 222 - 229
  • [5] Thermal-hydraulic and stress analysis of AP1000 reactor containment during LOCA in dry cooling mode
    Sh. Sheykhi
    S. Talebi
    M. Soroush
    E. Masoumi
    [J]. Nuclear Science and Techniques, 2017, 28
  • [6] Thermal-hydraulic and stress analysis of AP1000 reactor containment during LOCA in dry cooling mode
    Sh.Sheykhi
    S.Talebi
    M.Soroush
    E.Masoumi
    [J]. Nuclear Science and Techniques, 2017, 28 (06) : 89 - 101
  • [7] Thermal-hydraulic and stress analysis of AP1000 reactor containment during LOCA in dry cooling mode
    Sheykhi, Sh.
    Talebi, S.
    Soroush, M.
    Masoumi, E.
    [J]. NUCLEAR SCIENCE AND TECHNIQUES, 2017, 28 (06)
  • [8] Large LOCA accident analysis for AP1000 under earthquake
    Yu, Yu
    Lv, Xuefeng
    Niu, Fenglei
    [J]. ANNALS OF NUCLEAR ENERGY, 2015, 77 : 142 - 147
  • [9] A Fuzzy Probability Algorithm for Evaluating the AP1000 Long Term Cooling System to Mitigate Large Break LOCA
    Purba, J. H.
    [J]. ATOM INDONESIA, 2015, 41 (03) : 113 - 121
  • [10] Simulation and analysis on 10-in. cold leg small break LOCA for AP1000
    Yang, J.
    Wang, W. W.
    Qiu, S. Z.
    Tian, W. X.
    Su, G. H.
    Wu, Y. W.
    [J]. ANNALS OF NUCLEAR ENERGY, 2012, 46 : 81 - 89