РАСЧЕТНЫЙ КОД HYDRA-IBRAE/LM

ПУБЛИКАЦИИ

1. Alipchenkov V.M., Anfimov А.М., Afremov D.А., Gorbunov V.S., Zeigarnik Yu.А., Kudryavtsev А.V., Osipov S.L., Mosunova N.A., Strizhov V.F., Usov E.V., 2016. Fundamentals, Current State of the Development of, and Prospects for Further Improvement of the New-Generation Thermal-Hydraulic Computational HYDRA-IBRAE/LM Code for Simulation of Fast Reactor Systems. Thermal Engineering. 2, 130-139. https://doi.org/10.1134/S0040601516020014.
2. Mosunova N.A., Alipchenkov V.M., Pribaturin N.A., Strizhov V.F., Usov E.V., Lobanov P.D., Afremov D.A., Semchenkov A.A., Larin I.A., 2020. Lead coolant modeling in system thermal-hydraulic code HYDRA-IBRAE/LM and some validation results. Nuclear Engineering and Design. 359. № 1104631. 11 p. https://doi.org/10.1016/j.nucengdes.2019.110463.
3. Alipchenkov V.M., Grudtsyn Ya.V., Ilyasova O.H., Mosunova N.A. Simulation of the processes occurring during steam generator tube rupture in the lead cooled reactor unit using HYDRA-IBRAE/LM code// Progress in Nuclear Energy, V. 149,2 022, 104278, https://doi.org/10.1016/j.pnucene.2022.104278.
4. Alipchenkov V. M., Grudtsyn Ya. V., Mosunova N. A., 2021. Modeling of gas-phase transport in heavy liquid-metal coolant flow in the HYDRA-IBRAE/LM thermohydraulic code. Atomic energy. 129. 127–134. https://doi.org/10.1007/s10512-021-00723-w.
5. Ilyasova O.H., Alipchenkov V.M., Mosunova N.A.,  Grudtsyn Ya.V  Simulation of natural circulation experiments for heavy liquid metal coolant using HYDRA-IBRAE/LM code // Progress in Nuclear Energy, V. 173,2 024, 105233,  https://doi.org/10.1016/j.pnucene.2024.105233.
6. Grudtsyn, Y. V., Alipchenkov, V. M., Mosunova, N. A., Ilyasova, O. H.,  Morkin, M. S. Simulation of the gas-lift effect for lead and lead-bismuth coolants in HYDRA-IBRAE/LM thermohydraulic code// Progress in Nuclear Energy, V. 173, 105275, https://doi.org/10.1016/j.pnucene.2024.105275.