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Literature Cited
A. N. Polyanin, “Heat and mass exchanges in rod bundles with cross currents of turbulent flows in liquids,” At. Énerg.,26, No. 3, 279–280 (1969).
V. S. Osmachkin and V. D. Borisov, The Hydraulic Resistance of Clusters of Heat Generating Rods in a Flow of Boiling Water, Preprint IAÉ 1957, Moscow (1970).
Yu. V. Mironov, E. V. Sakovich, and S. V. Shpanskii, “Analyzing the hydrodynamics and heat exchange crises in clusters of smooth rods, taking nonuniformities in the distributions of thermohydraulic parameters throughout the cross section of the channel into account,” in: Seminar TF-74: Investigating Critical Heat Flows in Clusters of Rods Under Steady-State and Monsteady-State Conditions of Heat Exchange [in Russian], Moscow (1974), pp. 189–200.
Yu. V. Mironov and S. V. Shpanskii, “Distribution of two-phase flow parameters throughout the cross section of a channel with clusters of fuel elements,” At. Énerg.,39, No. 6, 403–408 (1975).
G. S. Mingaleeva and Yu. V. Mironov, “Thermohydraulic calculation of multirod heat-dissipating clusters cooled by a single-phase coolant,” At. Énerg.,48, No. 5, 303–308 (1980).
G. S. Mingaleeva, Yu. V. Mironov, N. S. Razina, and T. I. Fomicheva, “Heat exchange in gas-cooled clusters with artificial roughening,” At. Énerg.,51, No. 6, 389–390 (1981).
M. Dalle Donne and L. Mayer, “Turbulent convection heat transfer from rough surfaces with two-dimensional rectangular ribs,” Int. J. Heat Mass Transfer,20, No. 6, 583–620 (1977).
M. Huggenburger, “Verification of thermal-hydraulic computer code SCRIMP by AVATHE HEX 31-rod bundle, 2: experimental data, TM-23-82-2,” Eidg. Inst. für Reaktorforschung, April, 1982.
V. Walker, L. White, and P. Burnett, “Forced convection heat transfer for parallel flow through a roughened rod cluster,” Int. J. Heat Mass Transfer,15, No. 2, 403–424 (1972).
D. Rowe, “A mechanism for turbulent mixing between rod bundle subchannels,” Trans. ANS,12, No. 2, 805–806 (1969).
A. P. Nikonov, S. P. Nikonov, and E. A. Katkovskii, H2O — a Packet of Applied Programs in FORTRAN for the Calculation of Thermal and Physical Properties and Their Derivatives for Water and Steam, Preprint IAÉ-3344/16, Moscow (1980).
Yu. S. Molochkikov and G. N. Batasheva, “Real steam content for boiling water superheated in tubes,” in: Achievements in Investigating the Heat Exchange and Hydraulics of Two-Phase Flows in the Elements of Electrical Plant [in Russian], Nauka, Moscow (1973), pp. 79–96.
V. S. Osmachkin and N. N. Lystsova, Comparing Test Data on Heat Exchange Crisis Conditions in Models of Fuel Clusters for Reactors Type VVÉR with the Results of Calculations by the IAÉ Method, Preprint IAÉ-2558, Moscow (1975).
V. N. Smolin and V. K. Polyakov, “Method of calculating heat-exchange crises with boiling coolant in rod clusters,” in: Seminar TF-78: Thermophysical Investigations for Ensuring Reliability and Safety in Water-cooled-Water-moderated Nuclear Reactors, Budapest (1978), pp. 475–486.
L. Tong, Boiling Crisis and Critical Heat Flows [in Russian], Atomizdat, Moscow (1976).
S. Eide and R. Gottula, Evaluation and Results of Loft Steady-State Departure from Nucleate Boiling Test, TREE-NUREG-1043, Idaho National Engineering Laboratory (1977).
H. Herkenrath and W. Hufschmidt, “Experimental subchannel investigation in a 16-rod test React. Safety Appl., Proc. Multiphase Flow and Heat Transfer Symp. Workshop, Vol. 3, Miami Beach 16–18 Apr., 1979, pp. 1713–1736.
V. S. Osmachkin, Heat Exchange Crisis for Movement of Boiling Water Along Clusters of Heat Generating Rods, Preprint IAÉ-2014, Moscow (1972).
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Translated from Atomnaya Énergiya, Vol. 58, No. 6, pp. 425–429, June, 1985.
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Mironov, Y.V. Program complexes for calculating cells of local thermohydpaulic parameters in rod clusters by the cell method. At Energy 58, 483–488 (1985). https://doi.org/10.1007/BF01130857
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DOI: https://doi.org/10.1007/BF01130857