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Critical heat flux for water boiling in channels. Modern state, typical regularities, unsolved problems, and ways for solving them (a review)

  • Heat and Mass Transfer and Properties of Working Fluids and Materials
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Abstract

Some general matters concerned with description of burnout in channels are outlined. Data obtained from experimental investigations on critical heat fluxes (CHF) in different channels, CHF data banks, the main determining parameters, CHF basic dependences, and a system of correction functions are discussed. Two methods for estimating the CHF description errors are analyzed. The influence of operating parameters, transverse sizes of channels, and conditions at their inlet are analyzed. The effects of heat-transfer surface shape and heat supply arrangement are considered for concentric annular channels. The notions of a thermal boundary layer and an elementary thermal cell during burnout in channels with an intricate cross section are defined. New notions for describing CHF in rod assemblies are introduced: bundle effect, thermal misalignment, assembly-section-averaged and local parameters (for an elementary cell), cell-wise CHF analysis in bundles, and standard and nonstandard cells. Possible influence of wall thermophysical properties on CHF in dense assemblies and other effects are considered. Thermal interaction of nonequivalent cells and the effect of heat supply arrangement over the cell perimeter are analyzed. Special attention is paid to description of the effect the heat release nonuniformity along the channels has on CHF. Objectives to be pursued by studies of CHF in channels of different cross-section shapes are formulated.

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References

  1. V. N. Smolin, S. V. Shpanskii, V. I. Esikov, and T. K. Sedova, “A procedure for calculating burnout in tubular fuel rods cooled by water and steam-water mixture,” Therm. Eng. 24(12) (1977).

    Google Scholar 

  2. “Recommendations on calculating burnout for water boiling in round tubes,” Preprint No. 1-57, IVT AN SSSR (Institute of High Temperatures, Soviet Union’s Academy of Sciences, Moscow, 1980).

  3. V. P. Bobkov, P. L. Kirillov, and V. N. Vinogradov, “Recommendations on calculating burnout in tubes using a data bank,” At. Energ. 59(1), 223–228 (1985).

    Google Scholar 

  4. D. C. Groeneveld, L. K. H. Leung, P. L. Kirillov, V. P. Bobkov, V. N. Vinogradov, I. P. Smogalev, and X. C. E. Royer, “The 1996 look-up table for critical heat flux in tubes,” Nucl. Eng. Des., No. 163, 223–226 (1996).

    Google Scholar 

  5. V. P. Bobkov, V. N. Vinogradov, O. A. Zyatnina, and N. V. Kozina, “A method for evaluating the critical heat flux in channels and cells of arbitrary geometry,” Therm. Eng. 42(3), 221 (1995).

    Google Scholar 

  6. V. P. Bobkov, O. A. Sudnitsyn, and M. O. Sudnitsyna, “Numerical and analytic description of critical heat fluxes in channels,” At. Energ. 84(2), 114–123 (1998).

    Article  Google Scholar 

  7. V. P. Bobkov, “A method for describing and calculating critical heat fluxes in annular channels in a wide range of parameters,” Therm. Eng. 59(7), 536 (2012).

    Article  MathSciNet  Google Scholar 

  8. V. P. Bobkov, V. N. Vinogradov, P. L. Kirillov, and I. P. Smogalev, “Critical heat fluxes in triangular rod bundles (the 1997 version of the lookup table),” Therm. Eng. 46(11), 959 (1999).

    Google Scholar 

  9. V. P. Bobkov, V. N. Vinogradov, A. D. Efanov, V. V. Sergeev, and I. P. Smogalev, “Substantiation and verification of the model for burnout in rod bundles of the KORSAR thermohydraulic code,” Therm. Eng. 50(3), 189 (2003).

    Google Scholar 

  10. V. P. Bobkov, A. D. Efanov, R. S. Pomet’ko, and I. P. Smogalev, “A modified table for calculating critical heat fluxes in assemblies of triangularly packed fuel rods,” Therm. Eng. 58(4), 317 (2011).

    Article  Google Scholar 

  11. V. P. Bobkov and I. P. Smogalev, “A tabular method for describing critical heat fluxes in square-packed fuel assemblies,” At. Energ. 94(5), 407–410 (2013).

    Google Scholar 

  12. V. P. Bobkov, A. D. Efanov, I. P. Smogalev, and R. S. Pomet’ko, “A table for critical heat fluxes in square-packed fuel assemblies,” At. Energ. 99(1), 33–42 (2005).

    Article  Google Scholar 

  13. L. S. Tong, Burnout and Critical Heat Flux (Atomizdat, Moscow, 1976).

    Google Scholar 

  14. L. S. Tong, “Prediction of departure from nucleate boiling from an axially nonuniform heat flux distribution,” J. Nucl. Energy 21(3), 241–248 (1967).

    Article  Google Scholar 

  15. I. S. Wilson and I. S. Stanek, “Critical heat flux in nonuniformly heated rod bundles,” in Proceedings of ASME Winter Annual Meeting, Gellerstedt, 1969, pp. 56–62.

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  1. State Scientific Center of the Russian Federation-Leipunskii Institute for Physics and Power Engineering, pl. Bondarenko 1, Obninsk, Kaluga oblast, 249020, Russia

    V. P. Bobkov

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  1. V. P. Bobkov
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Correspondence to V. P. Bobkov.

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Original Russian Text © V.P. Bobkov, 2015, published in Teploenergetika.

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Bobkov, V.P. Critical heat flux for water boiling in channels. Modern state, typical regularities, unsolved problems, and ways for solving them (a review). Therm. Eng. 62, 88–96 (2015). https://doi.org/10.1134/S0040601515020020

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  • DOI: https://doi.org/10.1134/S0040601515020020

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