Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer CodesSource: Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003::page 31401-1DOI: 10.1115/1.4053049Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The 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.
|
Show full item record
contributor author | Baisov, A. M. | |
contributor author | Churkin, A. N. | |
contributor author | Deev, V. I. | |
contributor author | Kharitonov, V. S. | |
date accessioned | 2022-05-08T08:32:02Z | |
date available | 2022-05-08T08:32:02Z | |
date copyright | 3/22/2022 12:00:00 AM | |
date issued | 2022 | |
identifier issn | 2332-8983 | |
identifier other | ners_008_03_031401.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4284046 | |
description abstract | The 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. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes | |
type | Journal Paper | |
journal volume | 8 | |
journal issue | 3 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4053049 | |
journal fristpage | 31401-1 | |
journal lastpage | 31401-9 | |
page | 9 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003 | |
contenttype | Fulltext |