Evaluation of advanced accumulator in a VVER-1000 reactor in loss of coolant accident

被引:3
|
作者
Pouresgandar, M. [1 ]
Safarzadeh, O. [2 ]
Talebi, S. [1 ]
机构
[1] Amirkabir Univ Technol, Dept Energy Engn & Phys, 424 Hafez Ave,POB 15875-4413, Tehran, Iran
[2] Shahed Univ, Fac Engn, POB 33191-18651, Tehran, Iran
关键词
Advanced accumulator; Fluidic device; Safety injection tank; LOCA; VVER-1000; RELAP5;
D O I
10.1016/j.anucene.2022.108988
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
The advanced accumulator is a passive system which gradually decreases the high flow into a low flow. The role of the fluidic device is to obtain an additional safety margin by increasing golden time to cope in the LOCA. In this paper, the effect of using the safety injection tank and the fluidic device, called advanced accumulator, in a wide spectrum of LOCA break sizes without emergency core cooling systems (ECCS) of a VVER-1000 is evaluated. Firstly, the main component of primary and secondary loops of Bushehr nuclear power plant (BNPP) is modeled by RELAP5. Secondly, the performance of the model is assessed in steady-state and LOCA conditions by comparing the obtained results with the plant's FSAR. Thirdly, a model is developed in RELAP5 to simulate the behavior of advanced accumulator and validated by blowdown test in a test facility and MARS-KS code. Finally, the performance of advanced accumulator in the spectrum of 200-300 mm break sizes of LOCA without ECCS. In this range of breaks, the core damage times (CDT) developed from peak cladding temperature (PCT) of 1204 degrees C have been calculated. In accordance with the results, the advanced accumulators can increase the CDT in the whole range of breaks.
引用
收藏
页数:12
相关论文
共 50 条
  • [1] Analysis of the small break loss of coolant accident in the VVER-1000/V446 reactor
    Altaha, S. M.
    Mansouri, M.
    Jahanfarnia, G.
    KERNTECHNIK, 2015, 80 (06) : 545 - 556
  • [2] LARGE BREAK LOSS-OF-COOLANT ACCIDENT ANALYSIS OF VVER-1000 REACTOR USING CATHARE CODE
    Sabotinov, Luben
    Srivastava, Abhishek
    NUCLEAR TECHNOLOGY, 2010, 170 (01) : 123 - 132
  • [3] Analytical assessment of VVER-1000 fuel assembly deformation in loss of coolant accident
    Taheranpour, N.
    Talebi, S.
    Pesaraklu, A.
    ANNALS OF NUCLEAR ENERGY, 2022, 165
  • [4] Neutronic analysis of nanofluids as a coolant in the Bushehr VVER-1000 reactor
    Zarifi, Ehsan
    Jahanfarnia, Gholamreza
    Veisy, Farzad
    NUKLEONIKA, 2012, 57 (03) : 375 - 381
  • [5] Accident management in VVER-1000
    D'Auria, F.
    Suslov, A.
    Muellner, N.
    Petrangeli, G.
    Cherubini, M.
    Science and Technology of Nuclear Installations, 2008, 2008
  • [6] PCTRAN enhancement for large break loss of coolant accident concurrent with loss of offsite power in VVER-1000 simulation
    Hadad, K.
    Esmaeili-Sanjavanmareh, M.
    KERNTECHNIK, 2017, 82 (02) : 176 - 183
  • [7] Uncertainty analysis of rod ejection accident in VVER-1000 reactor
    Miglierini, Bruno
    Kozlowski, Tomasz
    Kopecek, Vit
    ANNALS OF NUCLEAR ENERGY, 2019, 132 : 628 - 635
  • [8] Investigation of thermal performance of aluminum nanoparticle coolant in vver-1000 reactor
    Uzun, Sinem
    Genc, Yasin
    Acir, Adem
    JOURNAL OF POLYTECHNIC-POLITEKNIK DERGISI, 2021, 24 (03): : 1009 - 1015
  • [9] The Power Operating Conditions of the Reactor Installation for a VVER-1000 Reactor with Natural Circulation of the Coolant
    Blagoveshchenskii, A.Ya.
    Bor, S.M.
    Konovich, M.N.
    Mityukov, V.N.
    Sokolov, V.G.
    Shumskii, B.E.
    Vygovskii, S.B.
    Pinegin, A.A.
    Bogachek, L.N.
    Bai, V.F.
    Ignat'ev, N.A.
    Thermal Engineering, 2004, 51 (02) : 124 - 130
  • [10] Diagnostics of VVER-1000 Coolant Temperature Pulsations
    S. V. Priymak
    Atomic Energy, 2019, 125 : 297 - 300