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    Analysis of Dense-Mesh Distribution Network Operation Using Long-Term Monitoring Data
    (MDPI, 2019-11-14) Ptáček, Michal; Vyčítal, Václav; Toman, Petr; Vaculík, Jan
    The technical and economic aspects and the possibility of the mesh network topology offering many radial configurations lead to the fact that large municipal networks are generally under radial operation. However, it is very important to analyze the operation and control of the mesh networks, especially in terms of their safety and durability and in the frame of the smart grid concept, respectively. The article deals with the analysis of the operation of the dense-mesh municipal distribution network of E.ON Distribuce a.s. based on the long-term data from power quality monitors. It also shows a brief view of the current lack of data usability from monitors installed in distribution networks in the context of smart grid.
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    Generated heat by different targets irradiated by 660 MeV protons
    (Council of Scientific & Industrial Research - National Institute of Science Communication and Information Resources, 2020-04-30) Svoboda, Josef; Adam, Jindřich; Foral, Štěpán; Gustov, S.A.; Katovský, Karel; Kushvatov, J.; Král, Dušan; Solnyshkin, Alexander A.; Tichý, Pavel; Tyutyunnikov, S.; Zeman, Miroslav
    Calorimetric experiments have been performed to analyze different thick targets of natU, C, Pb material, irradiated by 660 MeV protons at the Phasotron accelerator facility, Joint Institute for Nuclear Research (JINR) in Dubna, Russia. The method of online temperature measurement has been compared with MCNPX 2.7.0 simulation and selected with Ansys Transient Thermal Simulation to compare measured temperature with the simulated one. Thermocouples type T and E have been used as a temperature probe. Many different positions have been measured for each target. Temperature results are following very well the processes inside of the cylinders. Changes of heat deposition caused by drops of the proton beam intensity are displayed very well as a jagged line shown in almost every chart. Accurate temperature changing measurement is a very modest variation of how to observe inner macroscopic behavior online.
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    Measurement of (n,) reaction cross section of W-186-isotope at neutron energy of 20.02±0.58 MeV
    (Council of Scientific & Industrial Research - National Institute of Science Communication and Information Resources, 2020-05-30) Mehta, M.; Singh, N.L.; Makwana, R.; Subhash, P.V.; Suryanarayana, S.V.; Parashari, S.; Chauhan, Rakesh; Singh, R.K.; Naik, H.; Mukherjee, S.; Soni, B.; Khirwadkar, S.; Varmuža, Jan; Katovský, Karel
    The cross-section of 186W(n,)187W reaction has been measured at an average neutron energy of 20.02±0.58 MeV by using activation technique. The 27Al(n,)24Na and 115In(n,n´)115mIn reactions have been used for absolute neutron flux measurement. Theoretically the reaction cross-sections have been calculated by using the TALYS-1.9 code. The results from the present work and the EXFOR based literature data have been compared with the evaluated data and calculated data from TALYS-1.9 code.
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    The definition of input parameters for modelling of energetic subsystems
    (EDP Sciences, 2013-06-26) Ptáček, Michal
    This paper is a short review and a basic description of mathematical models of renewable energy sources which present individual investigated subsystems of a system created in Matlab/Simulink. It solves the physical and mathematical relationships of photovoltaic and wind energy sources that are often connected to the distribution networks. The fuel cell technology is much less connected to the distribution networks but it could be promising in the near future. Therefore, the paper informs about a new dynamic model of the low-temperature fuel cell subsystem, and the main input parameters are defined as well. Finally, the main evaluated and achieved graphic results for the suggested parameters and for all the individual subsystems mentioned above are shown.
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    New experimental research stand SVICKA neutron field analysis using neutron activation detector technique
    (EDP Sciences - France, 2018-04-18) Varmuža, Jan; Katovský, Karel; Zeman, Miroslav; Šťastný, Ondřej; Haysak, Ivan; Holomb, Robert
    Knowledge of neutron energy spectra is very important because neutrons with various energies have a different material impact or a biological tissue impact. This paper presents basic results of the neutron flux distribution inside the new experimental research stand SVICKA which is located at Brno University of Technology in Brno, Czech Republic. The experiment also focused on the investigation of the sandwich biological shielding quality that protects staff against radiation effects. The set of indium activation detectors was used to the investigation of neutron flux distribution. The results of the measurement provide basic information about the neutron flux distribution inside all irradiation channels and no damage or cracks are present in the experimental research stand biological shielding.