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Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant. / Usov, Eduard V.; Lobanov, Pavel; Kashinskiy, Oleg N. et al.

In: MATEC Web of Conferences, Vol. 115, 06007, 10.07.2017.

Research output: Contribution to journal › Conference article › peer-review

Harvard

Usov, EV, Lobanov, P, Kashinskiy, ON, Pribaturin, NA, Mosunova, NA, Chuhno, VI, Kutlimetov, AE & Svetonosov, AI 2017, 'Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant', MATEC Web of Conferences, vol. 115, 06007. https://doi.org/10.1051/matecconf/201711506007

APA

Usov, E. V., Lobanov, P., Kashinskiy, O. N., Pribaturin, N. A., Mosunova, N. A., Chuhno, V. I., Kutlimetov, A. E., & Svetonosov, A. I. (2017). Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant. MATEC Web of Conferences, 115, [06007]. https://doi.org/10.1051/matecconf/201711506007

Vancouver

Usov EV, Lobanov P, Kashinskiy ON, Pribaturin NA, Mosunova NA, Chuhno VI et al. Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant. MATEC Web of Conferences. 2017 Jul 10;115:06007. doi: 10.1051/matecconf/201711506007

Author

Usov, Eduard V. ; Lobanov, Pavel ; Kashinskiy, Oleg N. et al. / Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant. In: MATEC Web of Conferences. 2017 ; Vol. 115.

BibTeX

@article{e6b3b2d96ae24082b21f3280e2f5104b,
title = "Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant",
abstract = "The presented paper contains a description of approaches to simulate processes, observed during leakage in the steam generator of the reactor with liquid metal coolant. These approaches have been implemented in thermal hydraulic code HYDRA-IBRAE/LM. To calculate motion of gas bubbles in liquid metal flow and heat transfer of gas bubbles with metal, different relations are used in HYDRA-IBRAE/LM code. The code contains models of chemical interaction between water and sodium for modelling of tube rupture in sodium cooled fast reactors, Modelling of the experiments has been made using HYDRA-IBRAE/LM code. The results of the modelling with determined main factors are presented in the article.",
author = "Usov, {Eduard V.} and Pavel Lobanov and Kashinskiy, {Oleg N.} and Pribaturin, {Nikolai A.} and Mosunova, {Nastasya A.} and Chuhno, {Vladimir I.} and Kutlimetov, {Alexander E.} and Svetonosov, {Alexander I.}",
year = "2017",
month = jul,
day = "10",
doi = "10.1051/matecconf/201711506007",
language = "English",
volume = "115",
journal = "MATEC Web of Conferences",
issn = "2261-236X",
publisher = "EDP Sciences",

}

RIS

TY - JOUR

T1 - Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant

AU - Usov, Eduard V.

AU - Lobanov, Pavel

AU - Kashinskiy, Oleg N.

AU - Pribaturin, Nikolai A.

AU - Mosunova, Nastasya A.

AU - Chuhno, Vladimir I.

AU - Kutlimetov, Alexander E.

AU - Svetonosov, Alexander I.

PY - 2017/7/10

Y1 - 2017/7/10

N2 - The presented paper contains a description of approaches to simulate processes, observed during leakage in the steam generator of the reactor with liquid metal coolant. These approaches have been implemented in thermal hydraulic code HYDRA-IBRAE/LM. To calculate motion of gas bubbles in liquid metal flow and heat transfer of gas bubbles with metal, different relations are used in HYDRA-IBRAE/LM code. The code contains models of chemical interaction between water and sodium for modelling of tube rupture in sodium cooled fast reactors, Modelling of the experiments has been made using HYDRA-IBRAE/LM code. The results of the modelling with determined main factors are presented in the article.

AB - The presented paper contains a description of approaches to simulate processes, observed during leakage in the steam generator of the reactor with liquid metal coolant. These approaches have been implemented in thermal hydraulic code HYDRA-IBRAE/LM. To calculate motion of gas bubbles in liquid metal flow and heat transfer of gas bubbles with metal, different relations are used in HYDRA-IBRAE/LM code. The code contains models of chemical interaction between water and sodium for modelling of tube rupture in sodium cooled fast reactors, Modelling of the experiments has been made using HYDRA-IBRAE/LM code. The results of the modelling with determined main factors are presented in the article.

UR - http://www.scopus.com/inward/record.url?scp=85025444794&partnerID=8YFLogxK

U2 - 10.1051/matecconf/201711506007

DO - 10.1051/matecconf/201711506007

M3 - Conference article

AN - SCOPUS:85025444794

VL - 115

JO - MATEC Web of Conferences

JF - MATEC Web of Conferences

SN - 2261-236X

M1 - 06007

ER -

ID: 9978016