Abstract
An experimental study has been made of heat exchange in bubble and transient regimes of boiling in spherical-element fills as applied to the cores of nuclear reactors with spherical fuel microelements based on uranium dioxide with multilayer ceramic coatings. Critical dependences describing experimental data and making it possible to calculate the heat-transfer coefficient in such regimes of boiling have been obtained.
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V. V. Lozovetskii and V. N. Krymasov, Hydromechanical and Thermal Processes in Nuclear Reactors with Fuel Microelements [in Russian], VINITI RAN, Moscow (2003).
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Translated from Inzhenerno-Fizicheskii Zhurnal, Vol. 80, No. 4, pp. 35–39, July–August, 2007.
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Lozovetskii, V.V. Heat transfer in boiling of water in a fill of spherical elements. J Eng Phys Thermophy 80, 671–675 (2007). https://doi.org/10.1007/s10891-007-0090-0
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DOI: https://doi.org/10.1007/s10891-007-0090-0