Numerical Analysis of Hydraulic Characteristic of Fast Reactor Wire-wrapped Rod Bundle Assembly under Low Reynolds Number

被引：0

作者：

Cheng D. ^{[1
]}

Qi X. ^{[1
]}

Du K. ^{[1
]}

Zhai W. ^{[1
]}

机构：

[1] Division of Reactor Engineering Technology Research, China Institute of Atomic Energy, Beijing

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2019年 / 53卷 / 08期

关键词：

China Experimental Fast Reactor; Hydraulic characteristic under low Reynolds number; Wire-wrapped rod bundle;

D O I：

10.7538/yzk.2019.youxian.0073

中图分类号：

学科分类号：

摘要：

Flow under low Reynolds number condition like laminar and transition flows is very important to the safety operation of the fast reactor which can exist in the different kinds of assemblies under normal operating and accident shutdown conditions. The hydraulic characteristics of different kinds of wire-wrapped rod bundle assemblies of China Experimental Fast Reactor (CEFR) under low Reynolds number were analyzed by using CFX program. The results show that the calculation result of hydraulic characteristic under low Reynolds number is in good agreement with the experimental result and the Engel's relational expression by using one helix wire-wrapped rod bundle assemblies as the calculating models. Horizontal flow produced by the wire-wrapper can induce the distinction of pressure distribution on six walls of the assembly, according to the calculation result of four helixes wire-wrapped rod bundle assemblies, but the pressure loss along the axial direction of each face is uniformly distributed by helix when the flow is fully developed. During measuring of the hydraulic characteristic of wire-wrapped rod bundle assemblies, the measuring points need to be placed on the same wall and the distances from inlet are multiples of the helix which can avoid the influence of the measuring caused by the horizontal flow. © 2019, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：1424 / 1432

页数：8

共 16 条

[1]

Engel F.C., Markley R.A., Laminar, transition, and turbulent parallel flow pressure drop across wire-wrap-spaced rod bundles, Nuclear Science and Engineering, 69, pp. 290-296, (1979)

[2]

Cheng S.K., Todreas N.E., Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles-bundle friction factors, sub-channel friction factors and mixing parameters, Nuclear Engineering and Design, 92, pp. 227-251, (1986)

[3]

Liu Y., Yu H., Thermal-hydraulic analysis of fuel subassemblies for sodium-cooled fast reactor, Atomic Energy Science and Technology, 42, 2, pp. 128-134, (2008)

[4]

Chen B., Application of CFD technology in thermal-hydraulics performance and grid development of fuel assemblies in foreign countries, Foreign Nuclear Power, 25, 2, pp. 1-6, (2004)

[5]

Ahmad I., Kim K.Y., Flow and convective heat transfer analysis using rans for a wire-wrapped fuel assembly, Journal of Mechanical Science and Technology, 30, pp. 1514-1524, (2006)

[6]

Raza W., Kim K.Y., Shape optimization of wire-wrapped fuel assembly using Kriging metamodeling technique, Nuclear Engineering and Design, 238, pp. 1332-1341, (2008)

[7]

Gajapathy R., Velusamy K., Selvaraj P., Et al., CFD investigation of helical wire-wrapped 7-pin fuel bundle and the challenges in modeling full scale 217 pin bundle, Nuclear Engineering and Design, 237, pp. 2332-2342, (2007)

[8]

Hamman K.D., Berry R.A., A CFD simulation process for fast reactor fuel assemblies, Nuclear Engineering and Design, 240, pp. 2304-2312, (2010)

[9]

Peniquel C., Rupp I., Rolfo S., Et al., Thermal-hydraulics and conjugate heat transfer calculation in a wire-wrapped SFR assembly, International Congress on Advances in Nuclear Power Plants, (2010)

[10]

Hu R., Fanning T.H., A momentum source model for wire-wrapped rod bundles: Concept, validation and application, Nuclear Engineering and Design, 262, pp. 371-389, (2013)

← 1 2 →