Numerical boron mixing studies for Loviisa nuclear power plant

被引:15
作者
Gango, P [1 ]
机构
[1] IVO Power Engn Ltd, Vantaa, Finland
关键词
D O I
10.1016/S0029-5493(97)00197-0
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 program is in the process of studying numerically boron mixing in the downcomer of Loviisa NPP (VVER-440). Mixing during the transport of a diluted slug from the loop to the core might serve as an inherent protection mechanism against severe reactivity accidents in inhomogenous boron dilution scenarios for PWRs. The commercial general purpose Computational Fluid Dynamics (CFD) code PHOENICS is used for solving the governing fluid flow equations in the downcomer geometry of VVER-440. So far numerical analyses have been performed for steady state operation conditions and two different pump driven transients. The steady state analyses focused on model development and validation against existing experimental data. The two pump driven transient scenarios reported are based on slug transport during the start of the sixth and first loop, respectively. The results from the two transients show that mixing is case and plant specific; the high and open downcomer geometry of VVER-440 seems to be advantageous from mixing point of view. In addition the analyzing work for the 'first pump start' scenario brought up some considerations about flow distribution in the existing experimental facilities. (C) 1997 Elsevier Science S.A.
引用
收藏
页码:239 / 254
页数:16
相关论文
共 50 条
  • [41] Remote disassembly of a nuclear power plant - The case of the Niederaichbach nuclear power plant
    Orwantschke, D
    ATW-INTERNATIONALE ZEITSCHRIFT FUR KERNENERGIE, 1995, 40 (10): : 615 - 618
  • [42] PHYTOPLANKTON IN THE SEA AREA AROUND THE LOVIISA NUCLEAR-POWER STATION, SOUTH COAST OF FINLAND
    ILUS, E
    KESKITALO, J
    ANNALES BOTANICI FENNICI, 1987, 24 (01) : 35 - 61
  • [43] nuclear power station与nuclear power plant
    嘉梁
    国外核新闻, 1992, (01) : 23 - 23
  • [44] Experience at Loviisa Nuclear Power Station with the Decontamination of Steam Generators and Primary Cycle Components.
    Helske, J.
    Jaernstroem, R.
    VGB-Kraftwerkstechnik, 1982, 62 (03): : 223 - 227
  • [45] Numerical model for estimation of corrosion location in nuclear power plant steam generators
    Tashakor, S.
    Jahanfarnia, G.
    Kebriaee, A.
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (01) : 95 - 100
  • [46] Numerical Simulation of Leakage Characteristics of Pressurized Water Reactor Nuclear Power Plant
    Yin S.
    Wang N.
    Wang H.
    Zhu M.
    Hedongli Gongcheng/Nuclear Power Engineering, 2021, 42 (03): : 32 - 36
  • [47] BELENE nuclear power plant numerical and experimental bedrock, layers and surface signals
    Philipoff, Philip
    Michaylov, Philip
    APPLIED MATHEMATICAL MODELLING, 2007, 31 (09) : 1889 - 1898
  • [48] Numerical investigation on cavitation within letdown orifice of PWR nuclear power plant
    Bai, Wenjie
    Duan, Quan
    Zhang, Zaoxiao
    NUCLEAR ENGINEERING AND DESIGN, 2016, 305 : 230 - 245
  • [49] Studies on helium-3 separation at Cernavoda nuclear power plant
    Bulubasa, Gheorghe
    Cristescu, Ion
    Bornea, Anisia
    Zamfirache, Marius
    Stefan, Liviu
    Ana, George
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 398 - 401
  • [50] ENVIRONMENTAL-STUDIES AND NUCLEAR-POWER PLANT SITE EVALUATIONS
    ODOR, DL
    HEALTH PHYSICS, 1975, 29 (06): : 909 - 910