Follow
Arsen S. Iskhakov
Title
Cited by
Cited by
Year
Hugoniot analysis of energetic molten lead-water interaction
A Iskhakov, V Melikhov, O Melikhov
Annals of Nuclear Energy 2019 (129), 437-449, 2019
252019
Steam generator tube rupture in lead-cooled fast reactors: estimation of impact on neighboring tubes
A Iskhakov, V Melikhov, O Melikhov, S Yakush
Nuclear Engineering and Design 341, 198-208, 2019
242019
Integration of neural networks with numerical solution of PDEs for closure models development
A Iskhakov, N Dinh, E Chen
Physics Letters A 406, 127456, 2021
19*2021
Pressure waves due to rapid evaporation of water droplet in liquid lead coolant
S Yakush, A Iskhakov, V Melikhov, O Melikhov
Science and Technology of Nuclear Installations 2018, 1-10, 2018
122018
Challenge problem 3: benchmark specifications for mixing in large enclosure and thermal stratification
A Manera, V Petrov, A Iskhakov, I Bolotnov, N Dihn, E Baglietto, E Merzari, ...
Argonne National Laboratory, Tech. Rep. ANL/NSE-22/8, 2022
102022
Challenge problem 1: benchmark specifications for the direct numerical simulation of canonical flows
I Bolotnov, N Dihn, A Iskhakov, CK Tai, E Merzari, T Nguyen, E Baglietto, ...
Argonne National Lab.(ANL), Argonne, IL (United States), 2021
102021
A perspective on data-driven coarse grid modeling for system level thermal hydraulics
A Iskhakov, CK Tai, I Bolotnov, N Dinh
Nuclear Science and Engineering, 2022
9*2022
Data-driven Hi2Lo for coarse-grid system thermal hydraulic modeling
A Iskhakov, N Dinh, V Coppo Leite, E Merzari
Advances in Thermal Hydraulics (ATH 2022), 38048, 2022
72022
Hugoniot analysis of experimental data on steam explosion in stratified melt-coolant configuration
A Iskhakov, V Melikhov, O Melikhov, S Yakush, LT Chung
Nuclear Engineering and Design, 151-157, 2019
72019
Towards data-driven turbulence modeling of mixed convection in advanced reactors using DNS data
CK Tai, A Iskhakov, N Dinh, I Bolotnov
NURETH-19, 36432, 2022
62022
Data-driven high-to-low for coarse grid system thermal hydraulics
A Iskhakov, V Coppo Leite, E Merzari, N Dinh
Nuclear Science and Engineering, 1-13, 2023
52023
Numerical modelling of the hydrodynamic loads applied on the “BREST-300” reactor steam generator tubes during a primary-to-secondary leak accident [Численное моделирование …
A Iskhakov, V Melikhov, O Melikhov
MPEI Vestnik 3, 33-40, 2017
4*2017
NEAMS IRP challenge problem 3: mixing in large enclosures and thermal stratification
A Manera, A Iskhakov, V Coppo Leite
NURETH-20, 40780, 2023
32023
Machine learning from RANS and LES to inform coarse grid simulations
A Iskhakov, N Dinh, V Coppo Leite, E Merzari
Progress in Nuclear Energy 163, 104809, 2023
32023
Direct numerical simulation of low and unitary Prandtl number fluids in reactor downcomer geometry
CK Tai, T Nguyen, A Iskhakov, E Merzari, N Dinh, I Bolotnov
Nuclear Technology, 1-22, 2023
32023
Data-driven RANS turbulence closures for forced convection flow in reactor downcomer geometry
A Iskhakov, CK Tai, I Bolotnov, T Nguyen, E Merzari, D Shaver, N Dinh
Nuclear Technology, 2023
22023
Analysis of the explosive boiling of water droplet in the lead [Анализ взрывного вскипания капли воды в жидком свинце]
A Iskhakov, V Melikhov, O Melikhov, N Rtishchev
Problems of Atomic Science and Technology. Series: Nuclear and Reactor …, 2016
1*2016
Spline-Based Stochastic Collocation Methods for Uncertainty Quantification in Nonlinear Hyperbolic PDEs
A Chertock, AS Iskhakov, S Janajra, A Kurganov
arXiv preprint arXiv:2402.02280, 2024
2024
New High-Order Numerical Methods for Hyperbolic Systems of Nonlinear PDEs with Uncertainties
A Chertock, M Herty, AS Iskhakov, S Janajra, A Kurganov, ...
arXiv preprint arXiv:2312.08280, 2023
2023
NEAMS IRP challenge problem 1: flexible modeling for heat transfer for applications in advanced reactors
I Bolotnov, A Iskhakov, T Nguyen
NURETH-20, 40393, 2023
2023
The system can't perform the operation now. Try again later.
Articles 1–20