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Cong T, Zhang R, Wang B, Xiao Y, Gu H. Single-phase flow in helical cruciform fuel assembly with conjugate heat transfer. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104199] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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Baisov AM, Churkin AN, Deev VI, Kharitonov VS. Testing the Modified Subchannel tempa- sc Code in Comparison With Experiments and Other Computer Codes. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2022. [DOI: 10.1115/1.4053049] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
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.
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Affiliation(s)
- A. M. Baisov
- JSC OKB “GIDROPRESS”, 21 Ordzhonikidze Street, Podolsk 142103, Russia; National Research Nuclear University “MEPhI” (Moscow Engineering Physics Institute), 31 Kashirskoye Shosse, Moscow 115409, Russia
| | - A. N. Churkin
- JSC OKB “GIDROPRESS”, 21 Ordzhonikidze Street, Podolsk 142103, Russia
| | - V. I. Deev
- National Research Nuclear University “MEPhI” (Moscow Engineering Physics Institute), 31 Kashirskoye Shosse, Moscow 115409, Russia
| | - V. S. Kharitonov
- National Research Nuclear University “MEPhI” (Moscow Engineering Physics Institute), 31 Kashirskoye Shosse, Moscow 115409, Russia
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Numerical investigation of the CHF in a vertical round tube and a single rod channel based on the eulerian two-fluid model. PROGRESS IN NUCLEAR ENERGY 2021. [DOI: 10.1016/j.pnucene.2021.103699] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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A circumferentially non-uniform heat transfer model for subchannel analysis of tight rod bundles. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.07.014] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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