Coupled neutronic/thermo-hydraulic analysis of water/Al2O3 nanofluids in a VVER-1000 reactor

被引：29
|
作者：
Safarzadeh, O. [1 ]
Shirani, A. S. [1 ]
Minuchehr, A. [1 ]
Saadatian-derakhshandeh, F. [1 ]
机构：
[1] Shahid Beheshti Univ, Tehran, Iran
来源：
ANNALS OF NUCLEAR ENERGY | 2014年 / 65卷
关键词：
Nanofluid; VVER-1000; reactor; Single heated channel; DRAGON; DONJON; HEAT-TRANSFER; SURFACE; FLUIDS; WATER; FLOW;
D O I：
10.1016/j.anucene.2013.10.036
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：
In this paper we investigate the thermal-hydraulic and neutronic attributions of using nanoparticles in the primary cooling system of a VVER-1000 reactor. The coupled analysis of the nanofluid core is performed by using DRAGON, DONJON and a thermal-hydraulic model that solves the governing momentum, energy, and mass equations. The applied approach is validated by comparing the results with the final safety analysis report (FSAR) of the plant. Finally, critical boric acid, relative power distribution, pressure drop, and temperature distributions of fuel, clad and coolant are considered for water/Al2O3 nanofluid. It is observed that low volume fraction of the nanoparticles has a minimum impact in critical boric acid up to about 3% and relative power distribution about 2% at maximum while the heat transfer is enhanced in comparison to pure water. (C) 2013 Elsevier Ltd. All rights reserved.
引用
收藏
页码：72 / 77
页数：6
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