Отправить статью по E-mail Use of the CFD-Code CONV-3D in Reactor Applications
- Авторы: Chudanov V.V.1, Aksenova A.E.1, Makarevich A.A.1, Pervichko V.A.1, Reyes I.V.1
-
Учреждения:
- Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
- Выпуск: Том 121, № 3 (2017)
- Страницы: 179-184
- Раздел: Article
- URL: https://journals.rcsi.science/1063-4258/article/view/248141
- DOI: https://doi.org/10.1007/s10512-017-0180-9
- ID: 248141
Цитировать
Открытый доступ
Доступ предоставлен
Только для подписчиков
Аннотация
The results of testing the CONV-3D code and methods of direct numerical modeling, using supercomputers, of turbulent flows in the elements of nuclear power plants are presented for problems as close as possible to real processes: natural and forced convection of sodium in the upper plenums of the Monju nuclear power plant in Japan and mixing of the two flows at different temperatures in the secondary loop of the Phénix reactor in France. The particularities of the method for calculating the thermo- and hydrodynamic characteristics of the equipment in nuclear power plants are listed.
Об авторах
V. Chudanov
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Россия, Moscow
A. Aksenova
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Россия, Moscow
A. Makarevich
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Россия, Moscow
V. Pervichko
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Россия, Moscow
I. Reyes
Institute of Problems in the Safe Development of Nuclear Energy, Russian Academy of Sciences (IBRAE RAN)
Email: j-atomicenergy@yandex.ru
Россия, Moscow
Дополнительные файлы
