Heat removal in fast reactor cores

Journal Article · Tue Oct 01 00:00:00 EDT 1985 · Sov. At. Energy (Engl. Transl.); (United States)

DOI:https://doi.org/10.1007/BF01207211· OSTI ID:5904091

Zhukov, A V; Matyukhin, N M; Sorokin, A P

This paper addresses the problems of a thermal-hydraulic calculation of fast reactor fuel element assemblies (FEA), particularly, that of finding on the basis of the reactor core design parameters the thermal-hydraulic characteristics which determine its operating ability. Research at the FEI is presented here, including studies of the mechanism of interchannel mixing, comples longitudinal-transverse flow in the reactor elements, the characteristics of hydrnDynamics and heat transfer in systems of parallel fuel elements and in atypical channels, and the temperature distributions in symmetrical and distorted fuel element lattices. Methods of mathematical modeling of coolant velocity and temperature distributions in fast reactor FEAs have been developed, and a set of programs has been written for calculating the local thermal-hydraulic characteristics of FEA. They have been tested on a large amount of experimental material and offer an effective method for performing thermal-hydraulic calculations.

• OSTI ID: 5904091
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Vol. 58:4; Other Information: Translated from Atomnaya Energiya, Vol. 58, No. 4, pp. 226-232, April, 1985
• Country of Publication: United States
• Language: English

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