Hydraulic characteristics of a fast reactor fuel subassembly: An experimental investigation. (April 2017)

• Record Type: Journal Article
• Authors: Padmakumar, G.; Velusamy, K.; Prasad, B.V.S.S.; Rajan, K.K.
• Is Part Of: Annals of nuclear energy. Volume 102(2017:Apr.)
• Page Start: 255
• Page End: 267
• Publication Date: 2017-04
• Subjects: Fast breeder reactor -- Fuel subassembly -- Rod bundle -- Top blockage -- Pressure drop -- Laminar and turbulent flows -- Water model; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2016.12.025
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: Fuel subassembly bundle geometry is studied for its hydraulic behaviour. The results are also compared with data available in literature. All flow regimes viz. laminar, transition and turbulent is covered for the study. Pressure drop across different regions of subassembly was also determined. The effect of external blockage is also studied and reported. Abstract: Fuel subassemblies of a fast reactor consist of fuel pin bundle with helically wound spacer wires, arranged in a triangular pitch within a hexagonal wrapper. The fuel pins are located within the subassembly. Further the subassembly comprises of a diffuser where the cross section changes from cylindrical to hexagonal, mixing plenum before the exit of pin bundle and a specially designed blockage adapter. Accurate assessment of the pressure drop in the fuel subassembly is essential to ensure adequate core cooling and design of sodium pump. Experimental determination of pressure drop characteristics in the subassembly by simulating the hydraulic condition in the subassemblies of the reactor core is considered essential as a better choice as correlations reported in the literature cannot be directly used for all the complex regions present in the subassembly. This is due to the fact that flows in the interconnecting sections are highly under developed. Further, the flow regime in a fuel subassembly varies from laminar (during shutdown heat removal under natural convection) to completely turbulent under full power condition. To understand the hydraulic characteristics of the 500 MWe Proto type Fast Breeder Reactor (PFBR) fuel subassembly, an experimental facility has been commissioned. Experiments on full scale subassembly with dummy fuel pins have been performed using water as simulant. Experiments have been conducted covering a wide range of Reynolds number encompassing laminar, transition and turbulent regimes. In the rod bundle, no abrupt changes in friction factor were observed when the flow changes from laminar to turbulent. The experimental results have been transposed using Euler number similarity, to determine the pressure drop for sodium flow in the reactor. Possible uncertainties in the experimental data have been quantified. Useful pressure drop correlations have been proposed for various section of the subassembly of a fast breeder reactor. Finally the results for fuel pin bundle region are compared with the data reported in the literature and a satisfactory agreement has been observed.