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contributor authorBaisov, A. M.
contributor authorChurkin, A. N.
contributor authorDeev, V. I.
contributor authorKharitonov, V. S.
date accessioned2022-05-08T08:32:02Z
date available2022-05-08T08:32:02Z
date copyright3/22/2022 12:00:00 AM
date issued2022
identifier issn2332-8983
identifier otherners_008_03_031401.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4284046
description abstractThe paper describes a modified version of the tempa-sc computer program designed to calculate temperature fields in bundles of rods cooled by a supercritical pressure (SCP) fluid. This version of the program is based on the subchannel method that was used in the tempa-1f program, developed earlier in the OKB “GIDROPRESS” for calculating heat and mass transfer in the core of VVER-type reactors cooled by single-phase water at subcritical pressure. As the relations that close the system of equations of mass, momentum, and energy conservation, the new version of the program includes correlations for calculating heat transfer and friction resistance, taking into account the strong dependence of the properties of the coolant on temperature and pressure. In particular, the use of the universal calculation model of heat transfer, developed by the authors of this paper, allows us to perform calculations in a wide range of flow parameters of various fluids, including the modes of normal, improved and deteriorated heat transfer. The results of tests of the tempa-sc program are presented in comparison with the available experimental data for water and modeling fluids (carbon dioxide, freons R-12 and R-134a) at SCPs, as well as with the published data of calculations by using similar subchannel programs (cobra-sc, assert-pv) and CFD codes. A qualitative agreement between the calculated and experimental data is shown.
publisherThe American Society of Mechanical Engineers (ASME)
titleTesting the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
typeJournal Paper
journal volume8
journal issue3
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4053049
journal fristpage31401-1
journal lastpage31401-9
page9
treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003
contenttypeFulltext


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