MATEC Web Conf.
Volume 115, 2017XXXIII Siberian Thermophysical Seminar (STS-33)
|Number of page(s)||4|
|Section||Chapter 6 Power engineering, energy efficiency and energy saving|
|Published online||10 July 2017|
Some approaches to numerical modelling of a phenomenon observed during steam generator tube rupture in the reactor with liquid metal coolant
1 Nuclear Safety Institute of the Russian Academy of Sciences, Novosibirsk Branch, Novosibirsk, 630090, 1 Lavrentiev Ave., 1, Russia
2 Nuclear Safety Institute of the Russian Academy of Sciences, Moscow, 115191, 52 B. Tulskaya Str., Russia
3 Institute of Thermophysics of the Russian Academy of Sciences, Siberian Branch, Novosibirsk, 630090, 1 Lavrentiev Ave., Russia
4 Novosibirsk State University, Novosibirsk, 630090, 2 Pirogova Str., Russia
* Corresponding author: email@example.com
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.
© The Authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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