Literature Cited
L. Chang, "Prediction of temperature distribution in a reactor including interassembly heat transfer," Nucl. Eng. Des.,42, No. 2, 223–236 (1977).
B. Chen and N. Todreas, "Prediction of the coolant temperature field in a breeder reactor including interassembly heat transfer," ibid.,35, No. 3, 423–440 (1975).
M. Carelli and C. Bach, "Thermal-hydraulic analysis for CRBRP core-restraint design," Trans. Nucl. Soc.,21, No. 1, 393–395 (1975).
W. Shaw and R. A. Schmitt, "A model to account for bypass-fluid and interfuel assembly heat transfer," ibid.,22, No. 1, 575–576 (1975).
A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, et al., "Channelwise thermal-hydraulic analysis of the fuel assemblies of nuclear reactors," At. Énerg.,51, No. 5, 307–311 (1981).
A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, Interchannel Exchange in the Fuel Assemblies of Fast Reactors: Theoretical Principles and Physics of the Process [in Russian], Énergoatomizdat, Moscow (1989).
A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, Interchannel Exchange in the Fuel Assemblies of Fast Reactors (Computer Programs and Practical Applications) [in Russian], Énergoatomizdat, Moscow (1991).
A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, et al., Effect of Interchannel Exchange on the Leveling (Equalization) of the Velocity- and Temperature Fields in the Fuel Element Cassettes (FA): Preprint FÉI-1062 [in Russian] (1980).
A. V. Zhukov, E. Ya. Sviridenko, N. M. Matyukhin, et al., "Variation of the velocity fields in fuel assemblies of fast reactors as a function of the geometrical changes of the peripheral zones," in: Thermophysical Investigations [in Russian], Izd. VIMI., Moscow (1977), pp. 17–22.
V. I. Subbotin, M. Kh. Ibragimov, P. A. Ushakov, et al., "Hydrodynamics and Heat Exchange in Nuclear Power Installations (Design Principles) [in Russian], Atomizdat, Moscow (1975).
G. P. Bogoslavskaya, A. V. Zhukov, P. L. Kirillov, et al., "Problems of core thermal-hydraulics in LMFBR," in: Proc. Int. Top. Meeting on Nuclear Reactor Thermal-Hydraulics, Karlsruhe (1979), Vol. 1, pp. 1319–1324.
V. M. Gryazev, N. A. Aseev, S. A. Markin, et al., "Theoretical and experimental studies on thermal physics and hydrodynamics of the packets of the core of a BOR-60 reactor," in: Heat Physics and Hydrodynamics of the Cores and the Steam Generators of Fast Reactors, Vol. 1, Izd. ChSKAÉ, Prague (1978), pp. 182–209.
Additional information
FÉI. Translated from Atomnaya Énergiya, Vol. 75, No. 1, pp. 17–21, July, 1993.
Rights and permissions
About this article
Cite this article
Bogatyrev, I.L., Zhukov, A.V., Matyukhin, N.M. et al. Specific features of the development of temperature fields in the system of interacting deformed fuel assemblies of the cores of fast reactors. At Energy 75, 520–525 (1993). https://doi.org/10.1007/BF00738980
Received:
Issue Date:
DOI: https://doi.org/10.1007/BF00738980