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    Wyświetlanie 1-3 z 3
    Tytuł:
    Control of the pretension in filament winding process
    Autorzy:
    Akkus, N.
    Genc, G.
    Girgin, C.
    Powiązania:
    https://bibliotekanauki.pl/articles/386520.pdf
    Data publikacji:
    2008
    Wydawca:
    Politechnika Białostocka. Oficyna Wydawnicza Politechniki Białostockiej
    Tematy:
    metoda nawijania
    symulacja
    filament winding
    simulation
    Opis:
    A tension control system which simulates the effect of tension force in the filament winding machines has been designed and implemented in the present study. Filament Winding (FW) machines are widely used in Fiber Reinforced Plastic (FRP) composite production systems in which they have a pretensioning system to optimize the tension of the fiber during winding process. The precise control of the winding path needs highly mechatronic systems. The designed control system consists of magnetic break, servo motor, a PID control unit, a load cell and a data converter. The tension of the carbon fiber was measured by a load cell and compared to the preset value to keep the tension of the carbon fiber in predefined certain range.
    Źródło:
    Acta Mechanica et Automatica; 2008, 2, 3; 5-10
    1898-4088
    2300-5319
    Pojawia się w:
    Acta Mechanica et Automatica
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Neutronic analysis of LBE-uranium spallation target accelerator driven system loaded with uranium dioxide in TRISO particles
    Autorzy:
    Bakir, G.
    Selçuklu, S.
    Genç, G.
    Yapici, H.
    Powiązania:
    https://bibliotekanauki.pl/articles/1068556.pdf
    Data publikacji:
    2016-07
    Wydawca:
    Polska Akademia Nauk. Instytut Fizyki PAN
    Tematy:
    28.20.-v
    28.20.Np
    28.65.+a
    29.20.dg
    29.85.Fj
    Opis:
    This study presents the neutronic performances of fissile breeding and energy production of a gas cooled accelerator-driven system with LBE-uranium dioxide (UO₂) spallation target. The accelerator-driven system is designed and optimized by considering various target materials, in terms of neutronic. Two different materials, LBE + natural UO₂ and LBE + 15% enrichment UO₂ are selected as target materials. The target zone is divided into two parts, one within the other; the outer part is pure LBE target part, and the inner part is UO₂ target part cooled with the helium gas. Tristructural-isotropic (TRISO)-coated fuel particles, containing UO₂ fuel, are embedded in a carbon matrix pebble with the packing fraction of a 29%, and the pebbles are placed in the UO₂ target part and in the fuel core with the packing fraction of a 60%. The fuel core is cooled with helium that is a high-temperature coolant. The target is bombarded with the continuous beams of a 1 GeV protons to produce high-flux neutrons that enter the fuel core. The fuel core is surrounded with a graphite reflector zone serving as both effective moderation and reflection of these neutrons. Furthermore, the whole system is enclosed by boron carbide, B₄C (shielding zone), to prevent the neutrons leakage out of the accelerator-driven system. The high-energy Monte Carlo code MCNPX along with the LA150 library is used for neutronic calculations. The numerical results bring out that the investigated accelerator-driven system has a high neutronic performance, from the energy production and fissile breeding points of view. Namely, it can be obtained over the thermal power of a 350 MW and produced over the fissile breeding of a 300 g/day.
    Źródło:
    Acta Physica Polonica A; 2016, 130, 1; 30-32
    0587-4246
    1898-794X
    Pojawia się w:
    Acta Physica Polonica A
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
    Tytuł:
    Neutron-induced medical radioisotope production in a conceptual accelerator-driven system, fueled with uranium carbide
    Autorzy:
    Arslan, A.
    Bakir, G.
    Selçuklu, S.
    Genç, G.
    Yapici, H.
    Powiązania:
    https://bibliotekanauki.pl/articles/1070433.pdf
    Data publikacji:
    2016-07
    Wydawca:
    Polska Akademia Nauk. Instytut Fizyki PAN
    Tematy:
    28.20.-v
    28.20.Np
    28.65.+a
    29.85.Fj
    29.20.-c
    Opis:
    In this study, the medical radioisotope production performance of a conceptual accelerator-driven system is investigated. Lead-bismuth eutectic is used as target material. The fuel core of the considered accelerator-driven system is divided into ten subzones, loaded with uranium carbide and various isotopes (isotopes of copper, gold, cobalt, holmium, rhenium, scandium, and thulium) and cooled with light water. As is known, light water is an effective moderator of neutrons as well as a good coolant. The fuel and the isotopes are separately placed as cylindrical rods with a cladding of carbon composite. The volume fractions of fuel, isotope, cladding and coolant are selected as 25%, 35%, 10% and 30%, respectively. The copper rods are placed into the first five subzones due to the fact that copper isotopes have low capture cross-section. In the case of the each radioisotope production, one of the other considered isotopes that have higher capture cross-section are placed into the following five subzones for optimization of fission, fissile breeding and radioisotope production. The graphite zone is located around the fuel core to reflect the escaping neutrons. Boron carbide (B₄C) is used as shielding material. In order to produce more neutrons (about 25-30 neutrons per 1 GeV proton), the target is irradiated with a continuous beam of 1 GeV protons. All neutronic computations have been performed with the high-energy Monte Carlo N-Particle Transport Code using the LA150 data library. The neutronic results obtained from these calculations show that the examined accelerator-driven system has a high neutronic capability, in terms of production of thermal power, fissile fuels, and medical radioisotopes.
    Źródło:
    Acta Physica Polonica A; 2016, 130, 1; 68-71
    0587-4246
    1898-794X
    Pojawia się w:
    Acta Physica Polonica A
    Dostawca treści:
    Biblioteka Nauki
    Artykuł
      Wyświetlanie 1-3 z 3

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