Development of 3-D CFD methodology to investigate the transient thermal-hydraulic characteristics of coolant in a spent fuel pool

被引：8

作者：

Chen, S. R. ^{[1
,2
]}

Lin, W. C. ^{[3
]}

Ferng, Y. M. ^{[2
,3
]}

Chieng, C. C. ^{[2
,4
]}

Pei, B. S. ^{[2
,3
]}

机构：

[1] Taiwan Power Co, Taipei, Taiwan

[2] Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsingchu 30013, Taiwan

[3] Natl Tsing Hua Univ, Dept Engn & Syst Sci, Hsingchu 30013, Taiwan

[4] City Univ Hong Kong, Dept Mech & Biomed Engn, Kowloon, Hong Kong, Peoples R China

来源：

NUCLEAR ENGINEERING AND DESIGN | 2014年 / 275卷

关键词：

SIMULATION; FLOW;

D O I：

10.1016/j.nucengdes.2014.05.020

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：

Based on the need for decommissioning and as a consequence of the Fukushima accident, research into spent fuel pools (SFPs) has become an important topic for nuclear safety analysis. In this paper, a three-dimensional (3-D) computational fluid dynamics (CFD) methodology is proposed to investigate the transient behaviors of flow and heat transfer for the coolant within a rod bundle in a SFP. A cell with a 17 x 17 rod bundle in a SFP of the Maanshan nuclear power plant (NPP) is practically simulated, instead of using the porous media assumption employed in previous simulations. Normal operation conditions are adopted in the present transient simulations. The thermal-hydraulic characteristics of coolant in a rod bundle can be reasonably captured by the present CFD model. These characteristics include the flow acceleration and heat transfer enhancement in the support grids, the secondary flow between the rods, and the non-uniform distributions of velocity and temperature on the cross-section of the rod bundle. In future, this 3-D transient CFD model can be extended to investigate accidents that might occur in the SFP. Such investigations can be useful in providing the transient characteristics of localized flow and heat transfer for the coolant to assist the tradition system codes in simulating the accident scenarios. (C) 2014 Elsevier B.V. All rights reserved.

引用

页码：272 / 280

页数：9

共 18 条

[1]

[Anonymous], 2009, 20 ASME V V

[2]

[Anonymous], 2002, EVOLECORAD01

[3]

BENJAMIN AS, 1979, NUREGCR0649

[4]

Blake F., 1922, T AM I CHEM ENGRS, V14, P415

[5]

Boyd C., 2000, PREDICTIONS SPENT FU

[6]

CD-adapco, 2011, STARCCM 6 04 016

[7]

CHURCHILL SW, 1975, INT J HEAT MASS TRAN, V18, P1323, DOI [10.1016/0017-9310(75)90243-4, 10.1016/0017-9310(75)90222-7]

[8]

Collins T, 2001, NUREG1738

[9]

ERGUN S, 1952, CHEM ENG PROG, V48, P89

[10] The development of a three-dimensional transient CFD model for predicting cooling ability of spent fuel pools [J].

Hung, Tzu-Chen ;

Dhir, Vijay K. ;

Pei, Bau-Shei ;

Chen, Yen-Shu ;

Tsai, Fengjee P. .

APPLIED THERMAL ENGINEERING, 2013, 50 (01) :496-504

← 1 2 →