Model for subchannel friction factors and flow redistribution in wire-wrapped rod bundles

Revista Brasileira de Ciencias Mecanicas/Journal of the Brazilian Society of Mechanical Sciences

Volumn 21, Issue 4, 1999, Pages 589-599

  Carajilescov, Pedro ^a   Fernandez Y Fernandez, Elói ^b  

^a FLUMINENSE FEDERAL UNIVERSITY   (Brazil)

^b NONE

Author keywords

[No Author keywords available]

Indexed keywords

CHANNEL FLOW; FRICTION; MATHEMATICAL MODELS; NUCLEAR FUELS; TURBULENT FLOW;

FLOW REDISTRIBUTION; SUBCHANNEL FRICTION FACTORS;

BREEDER REACTORS;

EID: 0033280160     PISSN: 01007386     EISSN: None     Source Type: Journal    
DOI: 10.1590/S0100-73861999000400003     Document Type: Article

References (13)

1. Cheng, S.K. and Todreas, N.E., 1985, "Hydrodynamic Models and Correlations For Wire-Wrapped LMFBR Bundles and Subchannel Friction Factors and Mixing Parameters", Nuclear Eng. Design, Vol. 92, pp. 227.
2. Chiu, C. et al., 1979, "Pressure Drop Measurements in LMFBR Wire-Wrapped Blanket Bundles", Trans. ANS, Vol. 22, pp. 541-543.
3. Chiu, C. et al., 1980, "Turbulent Flow Split Model and Supporting Experiments for Wire-Wrapped Core Assemblies", Nuclear Technology, Vol. 50, pp. 40-52.
4. Engel, F.C. et al., 1979, "Laminar, Transition and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles", Nucl.Sci.Eng.. Vol. 69, pp. 290-296.
5. Ginsberg, T., 1972, "Forced-Flow Interchannel Mixing Model for Fuel Rod Assemblies Utilizing a Helical Wire-Wrap Spacer System", Nucl.Eng.Design, Vol. 22.
6. Hawley, J.T. et al., 1980, "Subchannel and Bundle Friction Factors and Flow Split Parameters for Laminar, Transition and Turbulent Longitudinal Flows in Wire-Wrap Spaced Hexagonal Arrays", ANS/ASME/NRC Intl.Topical Meeting on Nuclear Reactor Thermal-Hydraulics, NUREG/CP-0014, Vol. 3, Saratoga, NY, pp. 1766-1788.
7. Khan, E. and Todreas, N. E., 1973, "A Review of Recent Analytical and Experimental Studies Applicable to LMFBR Fuel and Blanket Assembly Design", Report MIT-COO 2245-4.
8. Novendstern, E.H., 1972, "Turbulent Flow Pressure Drop Model for Fuel Rod Assemblies Utilizing a Helical Wire-Wrap Spacer System", Nucl.Eng.Design, Vol. 22, pp. 19-27.
9. Rehme, K., 1973, "Pressure Drop Correlations for Fuel Element Spacers", Nuclear Technology, Vol. 17, pp. 15-23.
10. Rogers, J.T. and Todreas, N.E., 1968, "Coolant Interchannel Mixing in Reactor Fuel Rod Bundles Single-Phase Coolants", ASME Winter Meeting.
11. th Edition.
12. nd Edition.
13. Tong, L.S., 1968. "Pressure Drop Performance of a Rod Bundle", in Heat Transfer in Rod Bundle, ASME Winter Annual Meeting, NY.