Works by Mosunova, N. A.

Results: 23

Numerical Study of Thermal Destruction of Nitride Fuel Rods Using the Severe Accident Module of the Integral Euclid/V2 Code.

Published in:

2023

By:

Usov, E. V.;
Chukhno, V. I.;
Klimonov, I. A.;
Veprev, D. P.;
Mosunova, N. A.;
Strizhov, V. F.

Publication type:

Case Study

Experimental Investigation of the High-Temperature Interaction of Steel with a Lead Coolant.

Published in:

High Temperature, 2022, v. 60, p. S255, doi. 10.1134/S0018151X21050011

By:

Almjashev, V. I.;
Khabensky, V. B.;
Krushinov, E. V.;
Vitol, S. A.;
Kotova, S. Yu.;
Shevchenko, E. V.;
Kalyago, E. K.;
Sulatsky, A. A.;
Strizhov, V. F.;
Mosunova, N. A.

Publication type:

Article

Model of vapor slug growth in the channels of power engineering equipment with sodium coolant.

Published in:

High Temperature, 2017, v. 55, n. 4, p. 555, doi. 10.1134/S0018151X17030051

By:

Butov, A.;
Usov, E.;
Lezhnin, S.;
Mosunova, N.

Publication type:

Article

Validation of the severe accident module of the EVKLID/V2 integral code on the base of experiments with fission products release and dissociation of nitride fuel.

Published in:

Atomic Energy, 2024, v. 135, n. 5/6, p. 297, doi. 10.1007/s10512-024-01115-6

By:

Zhdanov, V. S.;
Klimonov, I. A.;
Kudashov, I. G.;
Mosunova, N. A.;
Strizhov, V. F.;
Sycheva, T. V.;
Usov, E. V.;
Chukhno, V. I.;
Kireev, G. A.;
Krivov, M. P.;
Skupov, M. V.

Publication type:

Article

Validation of the EUCLID/V1 integrated computer code against the BOR-60 experimental data.

Published in:

Atomic Energy, 2023, v. 134, n. 3/4, p. 223, doi. 10.1007/s10512-024-01047-1

By:

Veprev, D. P.;
Kuzmichev, S. A.;
Shershov, A. V.;
Mosunova, N. A.;
Strizhov, V. F.;
Boev, A. V.;
Zhemkov, I. Yu.;
Naboyshchikov, Yu. V.

Publication type:

Article

Virtual-Digital Model of NFC Closure for a Fast Reactor.

Published in:

Atomic Energy, 2022, v. 133, n. 1, p. 1, doi. 10.1007/s10512-023-00964-x

By:

Egorov, A. V.;
Rodina, E. A.;
Chudinova, V. A.;
Khomyakov, Yu. S.;
Makeeva, I. R.;
Popov, I. S.;
Fairushin, A. G.;
Veprev, D. P.;
Dolganov, A. E.;
Mosunova, N. A.;
Sumarokov, S. V.

Publication type:

Article

Three-Liquid, Two-Phase, Per-Channel Thermohydraulics Code Subchannel-Na/V1.0 for Single-Phase Sodium-Coolant Flows and Heat-Transfer: Key Models.

Published in:

Atomic Energy, 2022, v. 132, n. 6, p. 347, doi. 10.1007/s10512-023-00958-9

By:

Alipchenkov, V. M.;
Grudtsyn, Ya. V.;
Mosunova, N. A.;
Enzel, M. I.

Publication type:

Article

Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage.

Published in:

Atomic Energy, 2022, v. 132, n. 4, p. 212, doi. 10.1007/s10512-023-00930-7

By:

Koltashev, D. A.;
Mosunova, N. A.;
Strizhov, V. F;
Butov, A. A.;
Klimonov, I. A.;
Chukhno, V. I.;
Usov, E. V.

Publication type:

Article

Implementation of Parallel-Computing Algorithms for Systems with Distributed Memory in the EUKLID/V1 Integrated Computer Code.

Published in:

Atomic Energy, 2021, v. 130, n. 5, p. 273, doi. 10.1007/s10512-021-00808-6

By:

Veprev, D. P.;
Koltashev, D. A.;
Khachatryan, K. S.;
Bereznev, V. P.;
Mosunova, N. A.;
Strizhov, V. F.

Publication type:

Article

Modeling of Gas-Phase Transport in Heavy Liquid-Metal Coolant Flow in the HYDRA-IBRAE/LM Thermohydraulic Code.

Published in:

Atomic Energy, 2021, v. 129, n. 3, p. 127, doi. 10.1007/s10512-021-00723-w

By:

Alipchenkov, V. M.;
Grudtsyn, Ya. V.;
Mosunova, N. A.

Publication type:

Article

Verification of the Aerosol/Lm Module in Experiments on Sodium Burning in Moist Air.

Published in:

Atomic Energy, 2020, v. 127, n. 6, p. 352, doi. 10.1007/s10512-020-00635-1

By:

Kolobaeva, P. V.;
Mosunova, N. A.;
Sorokin, A. A.

Publication type:

Article

3D EVKLID/V2 Code Aided Simulation of Severe Accidents.

Published in:

Atomic Energy, 2019, v. 127, n. 1, p. 1, doi. 10.1007/s10512-019-00575-5

By:

Usov, E. V.;
Butov, A. A.;
Chukhno, V. I.;
Klimonov, I. A.;
Kudashov, I. G.;
Zhdanov, V. S.;
Pribaturin, N. A.;
Mosunova, N. A.;
Strizhov, V. F.

Publication type:

Article

Verification of Analytical Test Based Thermohydraulic Systems Codes for One- and Two-Phase Liquid-Metal Flows.

Published in:

Atomic Energy, 2018, v. 124, n. 6, p. 379, doi. 10.1007/s10512-018-0426-1

By:

Usov, E. V.;
Butov, A. A.;
Klimonov, I. A.;
Chukhno, V. I.;
Mosunova, N. A.;
Chalyi, R. V.;
Ryzhov, N. I.

Publication type:

Article

Experiment-Based Verification of the SAFR/V1 Module of the EVKLID/V2 Integral Code for Thermal Breakdown of Fuel Pins in a Fast Reactor.

Published in:

Atomic Energy, 2018, v. 124, n. 5, p. 287, doi. 10.1007/s10512-018-0412-7

By:

Usov, E. V.;
Butov, A. A.;
Chukhno, V. I.;
Klimonov, I. A.;
Kudashov, I. G.;
Zhdanov, V. S.;
Pribaturin, N. A.;
Mosunova, N. A.;
Strizhov, V. F.

Publication type:

Article

AEROSOL-LM/Na Aided Simulation of Fission Product Production and Transport in the First Loop of a Fast Reactor.

Published in:

Atomic Energy, 2018, v. 124, n. 4, p. 266, doi. 10.1007/s10512-018-0409-2

By:

Filippov, M. F.;
Kolobaeva, P. V.;
Mosunova, N. A.;
Sorokin, A. A.

Publication type:

Article

SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident.

Published in:

Atomic Energy, 2018, v. 124, n. 4, p. 232, doi. 10.1007/s10512-018-0403-8

By:

Usov, E. V.;
Butov, A. A.;
Chukhno, V. I.;
Klimonov, I. A.;
Kudashov, I. G.;
Zhdanov, V. S.;
Pribaturin, N. A.;
Mosunova, N. A.;
Strizhov, V. F.

Publication type:

Article

Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code.

Published in:

Atomic Energy, 2018, v. 124, n. 3, p. 147, doi. 10.1007/s10512-018-0389-2

By:

Usov, E. V.;
Butov, A. A.;
Chukhno, V. I.;
Klimonov, I. A.;
Kudashov, I. G.;
Zhdanov, V. S.;
Pribaturin, N. A.;
Mosunova, N. A.;
Strizhov, V. F.

Publication type:

Article

HYDRA-IBRAE/LM/V1 Thermohydraulic Code Verification Based on BN-600 Experiments.

Published in:

Atomic Energy, 2017, v. 122, n. 5, p. 311, doi. 10.1007/s10512-017-0272-6

By:

Klimonov, I.;
Usov, E.;
Dugarov, G.;
Butov, A.;
Kudashov, I.;
Ivanov, E.;
Mosunova, N.;
Strizhov, V.;
Anfimov, A.;
Gorbunov, V.;
Kuznetsov, D.;
Osipov, S.;
Bel'tyukov, A.

Publication type:

Article

Modeling of Oxide Layer Formation and Corrosion Products Coagulation and Transport in Lead Coolant Using the OXID Module of the HYDRA-IBRAE/LM Code.

Published in:

Atomic Energy, 2017, v. 122, n. 3, p. 172, doi. 10.1007/s10512-017-0252-x

By:

Usov, E.;
Sorokin, A.;
Chukhno, V.;
Mosunova, N.

Publication type:

Article

Next Generation Design Codes for a New Technological Platform for Nuclear Power.

Published in:

Atomic Energy, 2016, v. 120, n. 6, p. 369, doi. 10.1007/s10512-016-0145-4

By:

Bol'shov, L.;
Mosunova, N.;
Strizhov, V.;
Shmidt, O.

Publication type:

Article

A Step in the Verification of the Hydra-Ibrae/LM/V1 Thermohydraulic Code for Calculating Sodium Coolant Flow in Fuel-Rod Assemblies.

Published in:

Atomic Energy, 2015, v. 118, n. 6, p. 382, doi. 10.1007/s10512-015-0012-8

By:

Usov, E.;
Pribaturin, N.;
Kudashov, I.;
Butov, A.;
Dugarov, G.;
Mosunova, N.;
Strizhov, V.;
Ivanov, E.

Publication type:

Article

Molecular Ion Mechanism of HI Formation in the First Loop.

Published in:

Atomic Energy, 2013, v. 114, n. 3, p. 183, doi. 10.1007/s10512-013-9693-z

By:

Sorokin, A.;
Mosunova, N.;
Strizhov, V.

Publication type:

Article

Requirements for the EUCLID-F Integral Code for the Deterministic Analysis of Accidents in Fusion Reactors.

Published in:

Physics of Atomic Nuclei, 2023, v. 86, p. S99, doi. 10.1134/S106377882314003X

By:

Bahdanovich, R. B.;
Aksenova, A. E.;
Bereznev, V. P.;
Blokhin, A. I.;
Blokhin, P. A.;
Veprev, D. P.;
Vorivonchik, M. V.;
Efremova, O. V.;
Koltashev, D. A.;
Mosunova, N. A.;
Petrova, M. N.;
Sorokin, A. A.;
Usov, E. V.;
Chudanov, V. V.

Publication type:

Article