A Step in the Verification of the Hydra-Ibrae/LM/V1 Thermohydraulic Code for Calculating Sodium Coolant Flow in Fuel-Rod Assemblies
The basic relations used in the HYDRA-IBRAE/LM/V1 code for calculating the flow and heat-exchange of sodium coolant in fuel-rod assemblies in regimes with and without boiling and in the presence of a crisis of heat exchange are presented. The experimental data suitable for verifying the thermohydrau...
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| Published in | Atomic energy (New York, N.Y.) Vol. 118; no. 6; pp. 382 - 388 |
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| Main Authors | , , , , , , , |
| Format | Journal Article |
| Language | English |
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New York
Springer US
01.10.2015
Springer Springer Nature B.V |
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| Abstract | The basic relations used in the HYDRA-IBRAE/LM/V1 code for calculating the flow and heat-exchange of sodium coolant in fuel-rod assemblies in regimes with and without boiling and in the presence of a crisis of heat exchange are presented. The experimental data suitable for verifying the thermohydraulic code for calculating friction in one- and two-phase regimes as well as heat exchange in regimes with and without boiling are picked on the basis of a review of the literature. The computational error of different parameters is obtained on the basis of the verification results. It is shown that the thermohydraulic code HYDRA-IBRAE/LV/V1 can be used to calculate correctly the primary processes in design basis and beyond-design basis accidents in sodium-cooled reactor facilities. |
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| AbstractList | The basic relations used in the HYDRA-IBRAE/LM/V1 code for calculating the flow and heat-exchange of sodium coolant in fuel-rod assemblies in regimes with and without boiling and in the presence of a crisis of heat exchange are presented. The experimental data suitable for verifying the thermohydraulic code for calculating friction in one- and two-phase regimes as well as heat exchange in regimes with and without boiling are picked on the basis of a review of the literature. The computational error of different parameters is obtained on the basis of the verification results. It is shown that the thermohydraulic code HYDRA-IBRAE/LV/V1 can be used to calculate correctly the primary processes in design basis and beyond-design basis accidents in sodium-cooled reactor facilities. The basic relations used in the HYDRA-IBRAE/LM/V1 code for calculating the flow and heat-exchange of sodium coolant in fuel-rod assemblies in regimes with and without boiling and in the presence of a crisis of heat exchange are presented. The experimental data suitable for verifying the thermohydraulic code for calculating friction in one- and two-phase regimes as well as heat exchange in regimes with and without boiling are picked on the basis of a review of the literature. The computational error of different parameters is obtained on the basis of the verification results. It is shown that the thermohydraulic code HYDRAIBRAE/LV/V1 can be used to calculate correctly the primary processes in design basis and beyond-design basis accidents in sodium-cooled reactor facilities. |
| Audience | Academic |
| Author | Butov, A. A. Usov, E. V. Mosunova, N. A. Pribaturin, N. A. Dugarov, G. A. Kudashov, I. G. Ivanov, E. N. Strizhov, V. F. |
| Author_xml | – sequence: 1 givenname: E. V. surname: Usov fullname: Usov, E. V. organization: Novosibirsk Affiliate of the Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) – sequence: 2 givenname: N. A. surname: Pribaturin fullname: Pribaturin, N. A. organization: Novosibirsk Affiliate of the Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) – sequence: 3 givenname: I. G. surname: Kudashov fullname: Kudashov, I. G. organization: Novosibirsk Affiliate of the Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) – sequence: 4 givenname: A. A. surname: Butov fullname: Butov, A. A. organization: Novosibirsk Affiliate of the Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) – sequence: 5 givenname: G. A. surname: Dugarov fullname: Dugarov, G. A. organization: Novosibirsk Affiliate of the Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) – sequence: 6 givenname: N. A. surname: Mosunova fullname: Mosunova, N. A. organization: Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) – sequence: 7 givenname: V. F. surname: Strizhov fullname: Strizhov, V. F. organization: Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) – sequence: 8 givenname: E. N. surname: Ivanov fullname: Ivanov, E. N. organization: Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN) |
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| CitedBy_id | crossref_primary_10_1016_j_applthermaleng_2023_120637 crossref_primary_10_1007_s10512_018_0426_1 crossref_primary_10_1134_S004060151710007X crossref_primary_10_1007_s10512_017_0272_6 crossref_primary_10_1134_S0040601518080086 crossref_primary_10_1134_S0040601523040067 crossref_primary_10_1134_S0040601523120054 crossref_primary_10_1088_1742_6596_754_11_112009 crossref_primary_10_1016_j_nucengdes_2021_111425 crossref_primary_10_1016_j_nucengdes_2022_111877 crossref_primary_10_1088_1742_6596_1128_1_012044 crossref_primary_10_1134_S0040601518050063 |
| Cites_doi | 10.1016/0029-5493(87)90125-7 10.13182/NSE91-A23837 10.1016/0017-9310(94)90355-7 10.1016/0017-9310(67)90047-6 10.1016/0029-5493(84)90216-4 |
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| References_xml | – ident: 12_CR1 – volume: 6 start-page: B8.3.1 year: 1970 ident: 12_CR11 publication-title: Heat Transfer Conf. contributor: fullname: J Chen – volume: 45 start-page: 39 issue: 1 year: 1949 ident: 12_CR4 publication-title: Chem. Eng. Prog. contributor: fullname: R Lockhart – volume: 99 start-page: 247 year: 1987 ident: 12_CR19 publication-title: Nucl. Eng. Des. doi: 10.1016/0029-5493(87)90125-7 contributor: fullname: K Yamaguchi – volume: 108 start-page: 396 year: 1991 ident: 12_CR20 publication-title: Nucl. Eng. Des. doi: 10.13182/NSE91-A23837 contributor: fullname: H Kottowski – ident: 12_CR6 – ident: 12_CR8 – volume-title: Heat and Mass Transfer and Friction in a Turbulent Boundary Layer year: 1985 ident: 12_CR9 contributor: fullname: SS Kutateladze – ident: 12_CR10 – volume: 37 start-page: 3015 issue: 18 year: 1994 ident: 12_CR14 publication-title: Int. J. Heat Mass Transfer doi: 10.1016/0017-9310(94)90355-7 contributor: fullname: V Prisnyakov – volume: 27 start-page: 567 year: 1977 ident: 12_CR21 publication-title: Trans. Am. Nucl. Soc. contributor: fullname: J Wantland – volume: 64 start-page: 12 issue: 82 year: 1968 ident: 12_CR13 publication-title: Chem. Eng. Progr. Symp. Ser. contributor: fullname: C Baroczy – ident: 12_CR16 – volume-title: Thermohydraulic Calculation of the Fuel Assemblies of Fast Reactors with Liquid Metal Coolant year: 1985 ident: 12_CR3 contributor: fullname: AV Zhukov – volume: 10 start-page: 1767 year: 1967 ident: 12_CR5 publication-title: Int. J. Heat and Mass Transfer doi: 10.1016/0017-9310(67)90047-6 contributor: fullname: D Chisholm – ident: 12_CR12 – ident: 12_CR18 – volume: 60 start-page: 317 issue: 5 year: 1986 ident: 12_CR2 publication-title: At. Énerg. contributor: fullname: AV Zhukov – ident: 12_CR17 – volume: 82 start-page: 281 year: 1984 ident: 12_CR7 publication-title: Nucl. Eng. Des. doi: 10.1016/0029-5493(84)90216-4 contributor: fullname: H Kottowski – ident: 12_CR15 |
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| SubjectTerms | Analysis Approximation Assemblies Boiling Control theory Coolants Experiments Friction Hadrons Heat conductivity Heat exchange Heat exchangers Heat transfer Heavy Ions Lattice theory Mathematical analysis Nuclear Chemistry Nuclear Energy Nuclear fuels Nuclear Physics Nuclear reactors Physics Physics and Astronomy Reynolds number Sodium Studies Thermohydraulics |
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| Title | A Step in the Verification of the Hydra-Ibrae/LM/V1 Thermohydraulic Code for Calculating Sodium Coolant Flow in Fuel-Rod Assemblies |
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