|

Influence of spacer type on fluid dynamics of 7-rod fuel assembly

Authors: Markov P.V., Solonin V.I. Published: 11.06.2013
Published in issue: #1(90)/2013  

DOI:

 
Category: Power-generating and Transport Machine Building  
Keywords: fast fission reactors, spacing of fuel rods, fuel rods, computational fluid dynamics, subchannel transfer

The numerical simulation of fluid flow in 7-rod fuel assemblies is performed. The fuel rods are spaced by twisted wire wrap or four-rib wrap. Data on the coolant flow structure that determines the subchannel transfer intensity and hydraulic characteristics of the assemblies are obtained. The agreement of results of physical and numerical simulations is shown.

References

[1] Solonin V.I. Yadernye reaktory i ustanovki [Nuclear reactors and plants]. Moscow, Bauman MSTU Publ., 2010, 87 p.

[2] Townsend A.A. The structure of turbulent shear flow. Cambridge University Press, 1956, 315 p. (Russ. ed.: Taunsend A. Struktura turbulentnogo potoka s poperechnym sdvigom. Moscow, Inostrannaya literatura Publ., 1959, 399 p.)

[3] Zhukov A.V., Sorokin A.P., Matyukhin N.M. Mezhkanal’nyy obmen v TVS bystrykh reaktorov [Cross-channel exchange in fast reactor fuel assemblies]. Moscow, Energoatomizdat Publ., 1989, 184 p.

[4] Belov I.A. Modelirovanie turbulentnykh techeniy [Modeling of turbulent flows]. St. Petersburg, Baltic STU Publ., 2001, 104 p.

[5] Patankar S. Numerical heat transfer and fluid flow. New York, Hemisphere Publishing Corporation, 1980, 112 p. (Russ. ed.: Patankar S. Chislennye metody resheniya zadach teploobmena i dinamiki zhidkosti. Moscow, Energoatomizdat Publ., 1984, 152 p.)

[6] STAR-CCM+, version 7.02. UserGuide, CD-adapco Group, 2012.

[7] Kirillov P. L., ed. Spravochnik po teplogidravlicheskim raschetam (Yadernye reaktory, teploobmenniki, parogeneratory) [Handbook on thermohydraulic design: nuclear reactors, heat exchangers, steam generators]. Moscow, Energoatomizdat Publ., 1984, 296 p.