To study the characteristics of the mass transfer of noncondensable gases in the primary loop of the nuclear icebreaker reactors, models of the core and the up-core space were developed using the Relap5 (USA) and Fluent (USA) codes and modeling of interphase mass transfer and transport of the gas phase by the water coolant was performed on these sections. Spatial non-uniformity of the content of undissolved gases, which arises as a result of vapor-gas bubbles concentrating in the vortex structures of the flow and resulting in a significant reduction of their dissolution rate, was revealed. This must be taken into account in the analysis of the operation of the primary loop equipment of nuclear icebreakers (hydrogen absorption in the titanium alloys of steam-generator piping, nodular corrosion of the zirconium cladding of the fuel rods).
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
A. I. Kasperovich, I. V. Bychkov, and V. K. Shiryaev, “Gas transfer and gas evolution in the primary circuit of a pressurized water reactor,” At. Energ., 36, No. 5, 387–389 (1974).
S. A. Kabakchi, A. V. Luzakov, D. S. Urtenov, et al., “Assessment of the corrosion state of equipment elements 1 of the loop of transport power plants using water-chemistry indicators,” Teploenergetika, No. 3, 42–48 (2019).
Yu. A. Kalaida, Yu. D. Katkov, V. A. Kuznetsov, et al., “On the solubility of nitrogen in water,” At. Energ., 48, No. 2, 91–94 (1980).
V. I. Baranenko, V. S. Sysoev, L. N. Fal’kovskii, et al., “Solubility of nitrogen in water,” At. Energ., 65, No. 2, 133–135 (1990).
J. Hinze, “Fundamentals of the hydrodynamic mechanism of splitting in dispersion processes,” AIChE J., 1, No. 3, 289–295 (1955).
R. Higbie, “The rate of absorption of a pure gas into a still liquid during short periods of exposure,” AIChE J., 31, 365–389 (1935).
J. Lamont and D. Scott, “An eddy cell model of mass transfer into surface of a turbulent liquid,” AIChE J., 16, No. 4, 513–519 (1970).
Th. Frank, P. Zwart, and E. Krepper, “Validation of CFD models for mono- and polydisperse air-water two-phase flows in pipes,” Nucl. Eng. Design, 238, No. 3, 647–659 (2008).
V. Ustinenko, M. Samigulin, A. Ioilev, et al., “Validation of CFD-BWR, a new two-phase computational fluid dynamics model for boiling water reactor analysis,” ibid., 660–670.
S. Lezhnin, D. Eskin, Y. Leonenko, et al., “Dissolution of air bubbles in a turbulent water pipeline flow,” Heat Mass Transf.39, No. 5, 483–487 (2003).
Author information
Authors and Affiliations
Corresponding author
Additional information
Translated from Atomnaya Énergiya, Vol. 127, No. 2, pp. 69–73, August, 2019.
Rights and permissions
About this article
Cite this article
Karnaukhov, V.E., Ustinov, V.S., Urtenov, D.S. et al. Features of Mass Transfer of Noncondensable Gases by Primary Coolant of Nuclear Icebreaker Reactors. At Energy 127, 77–82 (2019). https://doi.org/10.1007/s10512-019-00588-0
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-019-00588-0