Zobrazeno 1 - 10
of 85
pro vyhledávání: '"Paulech Juraj"'
Publikováno v:
Journal of Mechanical Engineering, Vol 69, Iss 3, Pp 89-94 (2019)
This paper presents the preparation phase for model of transmission tower lattice construction using ANSYS APDL environment. Beam elements are used for the model which introduce complications in the preparation phase because of the need to define the
Externí odkaz:
https://doaj.org/article/5ec2ab7fd9484c30a465fe4abcf6488c
Publikováno v:
Journal of Mechanical Engineering, Vol 69, Iss 3, Pp 95-100 (2019)
The contribution deals with mechanical simulation of clamps for overhead powerline AlFe conductors. The process of pressed joint creation for two AlFe conductors and tensile test of such system are simulated using ANSYS software. The obtained results
Externí odkaz:
https://doaj.org/article/a54e57521ddf4ccfa8ea01590377f21f
Autor:
Murín Justín, Aminbaghai Mehdi, Goga Vladimír, Kutiš Vladimír, Paulech Juraj, Hrabovský Juraj
Publikováno v:
Journal of Mechanical Engineering, Vol 68, Iss 2, Pp 35-52 (2018)
In this paper, results of numerical simulations and measurements are presented concerning the non-uniform torsion and bending of an angled members of hollow cross-section. In numerical simulation, our linear-elastic 3D Timoshenko warping beam finite
Externí odkaz:
https://doaj.org/article/0fc62280609b477c8c6bf614d0de6d0f
Publikováno v:
Journal of Mechanical Engineering, Vol 67, Iss 1, Pp 69-76 (2017)
The paper deals with CFD modelling and simulation of coolant flow within the nuclear reactor VVER 440 fuel assembly. The influence of coolant flow in bypass on the temperature distribution at the outlet of the fuel assembly and pressure drop was inve
Externí odkaz:
https://doaj.org/article/123f7751919d49b790a26987caf4c2b6
Publikováno v:
Journal of Mechanical Engineering, Vol 67, Iss 1, Pp 87-92 (2017)
The paper presents the numerical simulation of thermo-hydraulic behaviour of coolant in the VVER- 440 nuclear reactor under standard outage conditions. Heating-up and flow of coolant between the reactor pressure vessel and spent fuel storage pool are
Externí odkaz:
https://doaj.org/article/1ae197a261904317a92677f75cad1167
Publikováno v:
Journal of Mechanical Engineering, Vol 67, Iss 1, Pp 37-44 (2017)
The article deals with modelling of coolant flow within the spent fuel storage pool of a VVER 440 reactor. The spent fuel storage pool is modelled in a state of standard reactor operation. The coolant heating from the remaining thermal power of store
Externí odkaz:
https://doaj.org/article/af88de5bd34d4863bf5a31d2c55eaef0
Publikováno v:
Journal of Mechanical Engineering, Vol 66, Iss 2, Pp 55-62 (2016)
The paper is focused on CFD analyses of the coolant flow in the nuclear reactor VVER 440. The goal of the analyses is to investigate the influence of the orifice diameter on the mass flow through individual fuel assemblies in the reactor core. The di
Externí odkaz:
https://doaj.org/article/d422abd9ba684137826fd318598a2f90
Autor:
Murín, Justín, Goga, Vladimir, Paulech, Juraj, Hrabovský, Juraj, Kutiš, Vladimír, Kugler, Stephan, Aminbaghai, Mehdi
Publikováno v:
In Sensors and Actuators: A. Physical 1 October 2024 376
Autor:
Murín, Justín, Kugler, Stephan, Hrabovsky, Juraj, Kutiš, Vladimir, Paulech, Juraj, Aminbaghai, Mehdi
Publikováno v:
In Composite Structures 1 July 2022 291
Autor:
Hanzalík, Matej, Paulech, Juraj
Publikováno v:
AIP Conference Proceedings; 2024, Vol. 3251 Issue 1, p1-9, 9p