Numerical simulation and analysis on thermal-hydraulic behavior of fuel assembly for sodium-cooled fast reactor

被引：0

作者：

Liu, Yang ^{[1
]}

Yu, Hong ^{[1
]}

Zhou, Zhi-Wei ^{[1
]}

机构：

[1] China Institute of Atomic Energy, P. O. Box 275-34, Beijing

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2014年 / 48卷 / 10期

关键词：

CFD; Fuel assembly; Sodium-cooled fast reactor; Thermal-hydraulic;

D O I：

10.7538/yzk.2014.48.10.1790

中图分类号：

学科分类号：

摘要：

The thermal-hydraulic behavior of triangular arranged fuel bundle with wrapped wire spacer of fuel assembly for sodium-cooled fast reactor was investigated by employing CFD code CFX, and the results were compared with subchannel analysis code SuperEnergy. Fuel bundles composed of 7, 19, 37 and 61 fuel rods were analyzed separately. The axial velocity, cross flow mixing effect, and temperature rise along axial direction for different subchannels of the fuel bundle were discussed, and the effect of wrapped wire spacer was carefully investigated. The results show that the wrapped wire spacer plays an important role on the cross flow effect and axial velocity distribution as well as the temperature rise in different subchannels. Moreover, with the increase of fuel rods, the flow in fuel bundle becomes more complicated, and the non-uniformity of the axial flow also shows a tendency to enhance. ©, 2014, Yuanzineng Kexue Jishu/Atomic Energy Science and Technology. All right reserved.

引用

页码：1790 / 1796

页数：6

共 9 条

[1]

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)

[2]

Liu Y., Yu H., Numerical simulation of flow and temperature field of fuel subassembly for China Experimental Fast Reactor, Atomic Energy Science and Technology, 41, pp. 230-234, (2007)

[3]

Raza W., Kim K.Y., Comparative analysis of flow and convective heat transfer between 7-pin and 19-pin wirewrapped fuel assemblies, Journal of Nuclear Science and Technology, 45, pp. 653-661, (2008)

[4]

Peniguel C., Rupp I., Juhel J., Et al., Three dimensional conjugated heat transfer analysis in sodium fast reactor wire-wrapped fuel assembly, Proceedings of ICAPP 2009, (2009)

[5]

Natesan K., Sundararajan T., Narasim A., Et al., Turbulent flow simulation in a wire-wrap rod bundle of an LMFBR, Nuclear Engineering and Design, 240, pp. 1063-1072, (2010)

[6]

Ikeda K., Hoshi M., Development of Mitsubishi high thermal performance grid: CFD applicability for thermal hydraulic design, JSME International Journal Series B: Fluids and Thermal Engineering, 45, 3, pp. 586-591, (2002)

[7]

McClusky H.L., Holloway M.V., Development of swirling flow in a rod bundle subchannel, Journal of Fluids Engineering-Transactions of the ASME, 124, 3, pp. 747-755, (2002)

[8]

Holloway M.V., Beasley D.E., Single-phase convective heat transfer in rod bundles, Nuclear Engineering and Design, 238, 4, pp. 848-858, (2008)

[9]

Chen B., Xiong W., Wang X., Et al., Application of calculation fluid dynamic in thermal hydraulic analysis of the fuel assembles and design of the spacer grid, Nuclear Power Engineering, 25, 5, pp. 403-407, (2004)

← 1 →