Browse > Article
http://dx.doi.org/10.1016/j.net.2022.01.018

Analytical model of transverse pressure loss in a rod array  

Ricciardi, Guillaume (CEA, DES, IRESNE, Department of Nuclear Technology)
Peybernes, Jean (CEA, DES, IRESNE, Department of Nuclear Technology)
Faucher, Vincent (CEA, DES, IRESNE, Department of Nuclear Technology)
Publication Information
Nuclear Engineering and Technology / v.54, no.7, 2022 , pp. 2714-2719 More about this Journal
Abstract
The present paper proposes some new computational methods and results in the framework of flow computation through congested domains seen as porous media, as it can be found in the core of a Pressurized Water Reactor (PWR). The flow is thus mostly governed by the distribution of pressure losses, both through the porous structures, such as fuel assemblies, and in the thin fluid layers between them. The purpose of the present paper is to consider the question of the interaction of a flow and a rod bundle from an analytical point of view gathering all the contributions through a set of equations as simple and representative as possible. It aims at demonstrating a sound understanding of the relevant phenomena governing the flow establishment in the geometry of interest instead of relying mainly on a posteriori observations obtained both experimentally and numerically. Comparison with two set of experimental results showed good agreement. The model proposed being analytical it appears easily implementable for studies needing an expression of fluid forces in a rod array as for fuel assembly bowing issue. It would be interesting to test the reliability of the model on other geometry with different P/R ratios.
Keywords
Pressure drop; Inclined flow; Fuel assembly;
Citations & Related Records
연도 인용수 순위
  • Reference
1 A. Wanninger, Mechanical Analysis of the Bow Deformation of Fuel Assemblies in a Pressurized Water Reactor Core, Technische Universitat Munchen, 2018.
2 J. Peybernes, Evaluation of the forces generated by cross-flow on PWR fuel assembly, in: Technical Meeting on Structural Behaviour of Fuel Assemblies for Water Cooled Reactors, 2005. Vienna.
3 D.Y. Sheng, M. Seidl, State-of-the-art hydraulic pressure drop and lift force analysis for a PWR fuel assembly by using CFD as compared to the classical one-dimensional approach, in: Conference: Computational Fluid Dynamics for Nuclear Reactor Safety Applications (CFD4NRS-6), 2016.
4 A. Horvath, B. Dressel, On numerical simulation of fuel assembly bow in pressurized water reactors, Nucl. Eng. Des. 265 (2013) 814-825.   DOI
5 A. Wanninger, et al., Mechanical analysis of the creep deformation of a row of fuel assemblies in a PWR core, in: WRFPM 2017, Jeju Island, 2017.
6 G.I. Taylor, Analysis of the swimming of long and narrow animals, Proc. Math. Phys. Eng. Sci. 214 (1952) 158-183.
7 S. Ersdal, O.M. Faltinsen, Normal forces on cylinders in near-axial flow, J. Fluid Struct. 22 (2006) 1057-1077.   DOI
8 L. Divaret, O. Cadot, P. Moussou, O. Doare, Normal forces exerted upon a long cylinder oscillating in an axial flow, J. Fluid Mech. 752 (2014b) 649-669.   DOI
9 A. Joly, Forces fluides stationnaires exercees sur un cylindre deforme en ecoulement axial et confine - application au dimensionnement sismique des assemblages combustibles, Universite Paris-Saclay, 2018.
10 E.F. Relf, C.H. Powell, Tests on Smooth and Stranded Wires Inclined T the Wind Direction, and a Comparison of Results on Stranded Wires in Air and Water, H.M. Stationery Office, 1917.
11 L. Divaret, P. Moussou, J. Berland, H. Berro, O. Cadot, O. Doare, Forces exerted on a cylinder in near-axial flow, J. Pressure Vessel Technol. 136 (2014a) 8, 051306.   DOI
12 M.P. Paidoussis, S. Suss, Stability of a cluster of flexible cylinders in bounded axial flow, J. Appl. Mech. 44 (1977) 401-408, 9.   DOI
13 R.A. Smith, W.T. Moon, T.W. Kao, Experiments on flow about a yawed circular cylinder, J. Basic Eng. 94 (1972) 771-776, 12.   DOI
14 M.M. Zdravkovich, Applications, vol. 612, in: O.U.P. Oxford (Ed.), Flow Around Circular Cylinders, vol. 2, OUP Oxford, 2003.