Computational simulation of thermal hydraulic processes in the core and fuel assembly in the liquid-metal fast-breader reactor in the porous medium approximation
- Авторы: Bayaskhalanov M.V.1, Vlasov M.N.1, Korsun A.S.1, Merinov I.G.1
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Учреждения:
- National Research Nuclear University “MEPhI”
- Выпуск: Том 44, № 2 (2017)
- Страницы: 50-52
- Раздел: Article
- URL: https://journals.rcsi.science/1068-3356/article/view/228251
- DOI: https://doi.org/10.3103/S1068335617020063
- ID: 228251
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Аннотация
The results of numerical simulation of the sodium coolant flow in the fuel assembly with partial blocking of its cross section are presented. A comparison of the results obtained with experimental data confirmed the operability of the APMod module intended for simulating heat exchange processes in cores and heat exchange equipment of promising nuclear reactors.
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Об авторах
M. Bayaskhalanov
National Research Nuclear University “MEPhI”
Автор, ответственный за переписку.
Email: mr.bayashalanov@mail.ru
Россия, Kashirskoe sh. 31, Moscow, 115409
M. Vlasov
National Research Nuclear University “MEPhI”
Email: mr.bayashalanov@mail.ru
Россия, Kashirskoe sh. 31, Moscow, 115409
A. Korsun
National Research Nuclear University “MEPhI”
Email: mr.bayashalanov@mail.ru
Россия, Kashirskoe sh. 31, Moscow, 115409
I. Merinov
National Research Nuclear University “MEPhI”
Email: mr.bayashalanov@mail.ru
Россия, Kashirskoe sh. 31, Moscow, 115409
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