18.
Menter F.R.
Two-Equation Eddy-Viscosity Turbulence Models for Engineering
Applications // AIAA Journal. 1994. No. 32 (8). P. 1598–1605.
19.
Ten Years
of Experience with the SST Turbulence Model / F.R. Menter, M. Kuntz,
R. Langtry // Turbulence, Heat and Mass Transfer. 2003. No. 4. P. 625–632.
20.
Calculation
of boundary layer development using the turbulent energy equation /
Bradshaw P., Ferriss D.H., Atwell N.P. // J. Fluid Mech. 1967. No. 28. P. 593–616.
21.
Launder B.E.
,
Spalding D.B.
The Numerical Computation of Turbulent Flows //
Computer Methods in Applied Mechanics and Engineering. 1974. No. 3. P. 269–289.
22.
Bishop A.
,
Todreas N.
Hydraulic characteristics of wire-wrapped rod bundles //
Nuclear Engineering and Design. 1980. No. 62 (1–3). P. 271–293.
23.
Cheng S.K.
,
Todreas N.E.
Hydrodynamic models and correlations for bare and wire-
wrapped hexagonal rod bundles- bundle friction factors, sub-channel friction factors
and mixing parameters // Nuclear engineering and design. 1986. No. 92. P. 227–251.
24.
Sobolev V.
Fuel Rod and Assembly Proposal for XT-ADS Pre-design // Coordination
meeting of WP1&WP2 of DM1 IP EUROTRANS / Bologna, 8–9 February, 2006.
25.
Рекомендации
, правила, методики расчета гидродинамических и тепловых ха-
рактеристик элементов и оборудования энергетических установок. Руководя-
щий технический материал: в 3 т. Обнинск, 1991. Т. 1. 435 с.
26.
Engel F.C.
Laminar, transition and turbulent parallel flow pressure drop across wire-
wrap-spaced rod bundles // Nuclear science and engineering. 1979. No. 69. P. 290–
296.
27.
Rehme K.
Pressure drop correlations for fuel element spacers // Nuclear technology.
1973. No. 17. P. 15–23.
28.
Novendstern E.H.
Turbulent flow pressure drop model for fuel rod assemblies
utilizing a helical wire-wrap spacer system // Nuclear Engineering and Design. 1972.
No. 22. P. 19–27.
REFERENCES
[1] Orlov V.V., Seliverstov M.M., Tishchenko V.A., Zhanova V.U., Smirnov V.S.,
Ganev I.H., Lopatkin A.V., Bryunin S.V., Karhu A.N., Evropin S.V., Shatalov G.E.,
Sitnikov V.E., Dolgosheev P.I. Kozlov V.B., Photinus V.P., ed. Adamov E.O. The
White Book of Nuclear Energy. Moscow, GUPNIKIET Publ., 1998. 356 p.
[2] Dragunov Yu.G.,Lemekhov V.V., Smirnov V.S., Chernetsov N.G. The Technical
Solutions and Development Phases of the Reactor Plant BREST-OD-
300.
AtomicEnergyJ.
, 2012, vol. 113, no. 1, pp. 58–64 (in Russ.).
[3] Sheinina A.V. Hydraulic resistance of rod bundles in an axial fluid flow.
Liquid
Metals
, 1967, pp. 210–223 (in Russ.).
[4] Zhukov A.V., Sorokin A.P., Titov P.A., Ushakov P.A. Analysis of the hydraulic
resistance of the fast reactor fuel bundles.
Atomic Energy J
., 1986, vol. 60, no. 5,
pp. 317–321(in Russ.).
[5] Bubelis E.,Schikorr M. Review and proposal for best-fit of wire-wrapped fuel bundle
friction factor and pressure drop predictions using various existing correlations.
Forschungszentrum Karlsruhe GmbH., Karlsruhe, 2008. 61 p.
[6] Dziubienko B.V., Sakalauskas A., Ashmantas L., Siehal M.D. Turbulent flow and
heat transfer in channels of power plants. Vilnius,PradaiPubl., 1995. 300 p.
[7] Kirillov P.L., Bobkov V.P., Zhukov A.V., Yur’yev Yu.S., ed. Kirillov P.L.
The Reference Thermohydraulic Calculations in Nuclear Power.Thermohydraulic
Processes in the NPP.Moscow, AtPubl., 2010. 776 p.
[8] ANSYS FLUENT, Theory Guide, Rel. 14.5. ANSYS Inc., 2012.
[9] ANSYS Meshing User’s Guide, Rel. 14.5. ANSYS Inc., 2012.
[10] Launder B.E.,Spalding D.B. Lectures in Mathematical Models of Turbulence.London,
England, Academic Press, 1972.
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