Abstract
A new method is proposed for performing thermophysical calculations of a core with fuel elements whose cross sections are cross-shaped. The method is based on the concept of equivalent roughness. The equivalent roughness parameters are chosen in accordance with the experimental values of the coefficient of friction of the assemblies consisting of these fuel elements and then the coefficient of heat emission and the critical heat flux are taken into account. The computational formulas used in this method are different from the conventional set and are physically better grounded.
Similar content being viewed by others
REFERENCES
V. I. Ageenkov, V. S. Volkov, M. I. Solonin, et al., “Parameters and fabrication technology for PIK-reactor fuel elements,” At. Énerg., 92, No.6, 438–444 (2002).
V. A. Tsykanov, A. V. Klinov, V. A. Starkov, et al., “Upgrade of the SM reactor core for solving materials-science problems,” At. Énerg., 93, No.3, 167–172 (2002).
G. A. Kirsanov, K. A. Konoplev, A. N. Syasin, and J. A. Shishkina, “Hydraulic characteristics of the reactor PIK fuel elements,” in: Proceedings of LNPI, Research Report 1990–1991, St. Petersburg (1992), pp. 201–202.
S. S. Kutateladze, Handbook of Heat Transfer and Hydrodynamic Resistance, Énergoatomizdat, Moscow (1990).
B. S. Petukhov, L. G. Genin, and S. A. Kovalev, Heat Transfer in Nuclear Power Systems, Énergoatomizdat, Moscow (1986).
B. S. Petukhov, “Heat transfer and friction in turbulent pipe flow with variable physical properties,” Adv. Heat Transfer, 6, 528 (1970).
M. A. Mikheev and I. M. Mikheeva, Principles of Heat Transfer, Énergiya, Moscow (1977).
M. Siman-Tov, W. Gambill, W. Nelson, et al., “Thermal-hydraulic correlations for the advanced neutron source reactor fuel element design and analysis,” Report at ASME Winter Annual Meeting, Atlanta, Georgia, December 1–6, 1991.
M. A. Gotovskii, M. Ya. Belen'kii, B. S. Fokin, and G. A. Kirsanov, “Investigation of critical heat loads at high flow velocities with brief power excursions for the PIK reactor,” in: Basic Results of Scientific Investigations 1992–1993, St. Petersburg Institute of Nuclear Physics, St. Petersburg (1995), pp. 213–215.
A. T. Komov, “Physical model for calculating critical heat loads during boiling in an underheated rotational flow with nonuniform heating,” Teplofiz. Vys. Temp. 38, No.3, 523 (2000).
Yu. A. Zeigarnik, I. V. Kirillova, and A. I. Klimov, “Some results of measurements of the hydraulic resistance during boiling of water not heated to the saturation temperature,” ibid., 21, No.2, 303 (1983).
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Grosheva, N.A., Kirsanov, G.A., Konoplev, K.A. et al. Calculation of a Core with Fuel Elements Whose Cross Sections Are Cross-Shaped. Atomic Energy 95, 449–452 (2003). https://doi.org/10.1023/A:1025840012573
Issue Date:
DOI: https://doi.org/10.1023/A:1025840012573