A momentum source model for wire-wrapped rod bundles-Concept, validation, and application

被引:25
作者
Hu, Rui [1 ]
Fanning, Thomas H. [1 ]
机构
[1] Argonne Natl Lab, Nucl Engn Div, Argonne, IL 60439 USA
关键词
D O I
10.1016/j.nucengdes.2013.04.026
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
Large uncertainties still exist in the treatment of wire-spacers and drag models for momentum transfer in current lumped parameter models. To improve the hydraulic modeling of wire-wrap spacers in a rod bundle, a three-dimensional momentum source model (MSM) has been developed to model the anisotropic flow without the need to resolve the geometric details of the wire-wraps. The MSM is examined for 7-pin and 37-pin bundles steady-state simulations using the commercial CFD code STAR-CCM+. The calculated steady-state inter-subchannel cross flow velocities match very well in comparisons between bare bundles with the MSM applied and the wire-wrapped bundles with explicit geometry. The validity of the model is further verified by mesh and parameter sensitivity studies. Furthermore, the MSM is applied to a 61-pin EBR-II experimental subassembly for both steady state and PLOF transient simulations. Reasonably accurate predictions of temperature, pressure, and fluid flow velocities have been achieved using the MSM for both steady-state and transient conditions. Significant computing resources are saved with the MSM since it can be used on a much coarser computational mesh. (C) 2013 Elsevier B.V. All rights reserved.
引用
收藏
页码:371 / 389
页数:19
相关论文
共 19 条
  • [1] [Anonymous], 2006, ANL-ABR-1 (ANL-AFCI-173)
  • [2] BASEHORE K.L., 1980, SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis
  • [3] CD-adapco Group, 2010, STAR CCM US MAN V5 0
  • [4] DUNN F. E., 2004, P 14 PAC BAS NUCL C
  • [5] Fanning T. H., 2012, SAS4A SASSYS 1 SAFET
  • [6] A comparative CFD investigation of helical wire-wrapped 7, 19 and 37 fuel pin bundles and its extendibility to 217 pin bundle
    Gajapathy, R.
    Velusamy, K.
    Selvaraj, P.
    Chellapandi, P.
    Chetal, S. C.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (11) : 2279 - 2292
  • [7] A CFD simulation process for fast reactor fuel assemblies
    Hamman, Kurt D.
    Berry, Ray A.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2010, 240 (09) : 2304 - 2312
  • [8] Hu R., 2011, T AM NUCL SOC, V104, P1043
  • [9] Hu R., 2011, P NURETH 14 TOR CAN
  • [10] Hu R., 2011, ANLNE1135