Core thermal hydraulic CFD support for liquid metal reactors

被引:8
作者
Roelofs, F. [1 ]
Dovizio, D. [1 ]
Uitslag-Doolaard, H. [1 ]
De Santis, D. [1 ]
Mathur, A. [1 ]
Mikuz, B. [1 ]
Shams, A. [1 ]
机构
[1] NRG, Westerduinweg 3, NL-1755 LE Petten, Netherlands
关键词
CFD; Fuel assembly; Single-phase; Wire-wraps; HEAT-TRANSFER; NUMERICAL SIMULATIONS; TURBULENT FLOWS; 19-ROD BUNDLE; WIRE SPACERS; FUEL-RODS; BLOCKAGE; VIBRATIONS;
D O I
10.1016/j.nucengdes.2019.110322
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
Knowledge of the heat transport in the core is important for design and safety assessment of all nuclear reactors including liquid metal cooled reactors. In the past, design and safety calculations with respect heat transport in the core for such liquid metal cooled reactors were largely one-dimensional and based on experimental data. Nowadays, with modern state-of-the-art computer power and tools, three-dimensional Computational Fluid Dynamics (CFD) simulations allow designers and safety specialists to obtain much more detailed information on the heat transport in liquid metal cooled fuel assemblies, obviously supported by necessary experimental campaigns. This may lead to new insights possibly decreasing the safety margins. To this respect, an overview will be provided on the necessary activities in the frame of design and safety support using CFD for liquid metal reactors accompanied and illustrated by examples from NRG in the Netherlands. These examples include validation efforts for fuel assemblies as they are designed on the drawing board for 'cold' conditions. However, in reality, even under normal operational condition, a fuel assembly may deform. Therefore, an assessment of the effect of deformations resulting from operational conditions is necessary and will be shown. Another aspect possibly occurring during operational conditions is vibration. State-of-the-art coupled CFD and finite element method fluid structure interaction techniques have been developed and applied to a wire wrapped fuel assembly, providing insights in the vibration behavior of such assemblies. However, design and safety analysts will not only have to cope with operational conditions, but also have to show the heat transport behavior under accident conditions. For this, an assessment of the effect of internal and inlet blockages will be presented.
引用
收藏
页数:10
相关论文
共 61 条
  • [1] [Anonymous], IMPROVEMENT SINGLE P
  • [2] [Anonymous], FR09
  • [3] [Anonymous], SEARCH MAXSIMA INT W
  • [4] [Anonymous], 2015, INT TOP MEET NUCL RE
  • [5] [Anonymous], NURETH16
  • [6] [Anonymous], NURETH 17
  • [7] [Anonymous], 2015, NURETH16
  • [8] [Anonymous], ICONE20
  • [9] The deal.II Library, Version 8.4
    Bangerth, Wolfgang
    Davydov, Denis
    Heister, Timo
    Heltai, Luca
    Kanschat, Guido
    Kronbichler, Martin
    Maier, Matthias
    Turcksin, Bruno
    Wells, David
    [J]. JOURNAL OF NUMERICAL MATHEMATICS, 2016, 24 (03) : 135 - 141
  • [10] Batta A., 2017, NURETH17