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

被引：0

作者：

Usov, Eduard V. ^{[1
]}

Lobanov, Pavel ^{[1
,3
]}

Kashinskiy, Oleg N. ^{[3
]}

Pribaturin, Nikolai A. ^{[1
,3
]}

Mosunova, Nastasya A. ^{[2
]}

Chuhno, Vladimir I. ^{[1
,4
]}

Kutlimetov, Alexander E. ^{[1
,4
]}

Svetonosov, Alexander I. ^{[4
]}

机构：

[1] Russian Acad Sci, Nucl Safety Inst, Novosibirsk Branch, 1 Lavrentiev Ave,1, Novosibirsk 630090, Russia

[2] Russian Acad Sci, Nucl Safety Inst, 52 B Tulskaya Str, Moscow 115191, Russia

[3] Russian Acad Sci, Siberian Branch, Inst Thermophys, 1 Lavrentiev Ave, Novosibirsk 630090, Russia

[4] Novosibirsk State Univ, 2 Pirogova Str, Novosibirsk 630090, Russia

来源：

XXXIII SIBERIAN THERMOPHYSICAL SEMINAR (STS-33) | 2017年 / 115卷

关键词：

D O I：

10.1051/matecconf/201711506007

中图分类号：

O414.1 [热力学];

学科分类号：

摘要：

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.

引用

页数：4

共 17 条

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