Transverse Transport and Heat Transfer in Smooth VVER Fuel-Rod Bundle with Cellular Spacer Grid

被引：0
|
作者：
P. V. Markov
V. I. Solonin
机构：
[1] Bauman Moscow State Technical University (BMSTU),
来源：
Atomic Energy | 2019年 / 125卷
关键词：
D O I：
暂无
中图分类号：
学科分类号：
摘要：
The results of the numerical modeling of flow and heat transfer in a bundle of smooth fuel rods spaced by a cellular grid in application to VVER are presented. The results are analyzed and compared with computational-experimental studies in the homegrown and foreign nuclear power industries. The computational region simulating a VVER FA fragment, a mathematical model, and the boundary conditions are described. The results of a calculation of the coolant flow velocity field and the temperature field for the fuel-rod cladding under conditions of stabilized heat transfer in the bundle and on a section of stabilization beyond the cellular spacer grid are presented. Flow in the bundle and the mechanisms of interchannel transfer are described. Recommendations are given for taking account of the grid effect on intensification of heat transfer in the bundle, and a comparison is made with data obtained for plate-shaped spacer grids in PWR.
引用
收藏
页码：172 / 177
页数：5
相关论文
共 50 条
  • [21] Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 x 4 Rod Bundle With a Twist-Vane Spacer Grid
    Kumawat, Ganesh Lal
    Kansal, Anuj Kumar
    Maheshwari, Naresh Kumar
    Sharma, Avaneesh
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2019, 5 (04):
  • [22] Heat transfer to liquid metals in a hexagonal rod bundle with grid spacers: Experimental and simulation results
    Pacio, J.
    Litfin, K.
    Batta, A.
    Viellieber, M.
    Class, A.
    Doolaard, H.
    Roelofs, F.
    Manservisi, S.
    Menghini, F.
    Boettcher, M.
    NUCLEAR ENGINEERING AND DESIGN, 2015, 290 : 27 - 39
  • [23] HEAT-TRANSFER AND FLUID-DYNAMICS OF HIGH HEAT-FLUX FUEL-ROD FOR VHTR HEAT-TRANSFER AUGMENTATION BY SQUARE RIBBED SURFACE
    TAKASE, K
    HINO, R
    MIYAMOTO, Y
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 1991, 33 (10): : 975 - 982
  • [24] Analysis of the IAEA benchmark on heat transfer in a 4 x 4 rod bundle with mixing grid
    Bieder, Ulrich
    Costa, Delphine
    ANNALS OF NUCLEAR ENERGY, 2018, 115 : 352 - 366
  • [25] Experimental study of spacer effects on post-dryout heat transfer in a tight-lattice rod bundle
    Chen, Shuo
    Zeng, Chen
    Xiao, Yao
    Gu, Hanyang
    PROGRESS IN NUCLEAR ENERGY, 2025, 184
  • [26] DISPERSED-FLOW FILM BOILING HEAT-TRANSFER DATA NEAR SPACER GRIDS IN A ROD BUNDLE
    YODER, GL
    MORRIS, DG
    MULLINS, CB
    OTT, LJ
    NUCLEAR TECHNOLOGY, 1983, 60 (02) : 304 - 313
  • [27] Numerical Investigation of Single-Phase Heat Transfer in a 2 x 2 Rod Bundle with Spacer Grids for a High Pressure Heat Transfer Facility
    Dong, Xiaomeng
    Duarte, Juliana P.
    Zhang, Zhijian
    Corradini, Michael L.
    Tian, Zhaofei
    Chen, Guangliang
    NUCLEAR TECHNOLOGY, 2017, 199 (02) : 174 - 186
  • [28] Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers
    Gradecka, Malwina
    Thiele, Roman
    Anglart, Henryk
    JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2016, 2 (03):
  • [29] Heavy-liquid metal heat transfer experiment in a 19-rod bundle with grid spacers
    Pacio, J.
    Daubner, M.
    Fellmoser, F.
    Litfin, K.
    Marocco, L.
    Stieglitz, R.
    Taufall, S.
    Wetzel, Th.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 273 : 33 - 46
  • [30] Methods of simulating large-scale rod bundle and application to a 17 x 17 fuel assembly with mixing vane spacer grid
    Li, Xiaochang
    Gao, Ye
    NUCLEAR ENGINEERING AND DESIGN, 2014, 267 : 10 - 22
12345