Temat: MCB - Prolib Integro

Skocz do pozycji: 1.

Tytuł:: Let-through energy of miniature circuit breaker in function of phase angle of short-circuit current
Autorzy:: Książkiewicz, A.
Tematy:: MCB
let-through energy
Joule's heat; Pokaż więcej
Wydawca:: Politechnika Poznańska. Wydawnictwo Politechniki Poznańskiej
Powiązania:: https://bibliotekanauki.pl/articles/377379.pdf Link otwiera się w nowym oknie
Opis:: Let-through energy (Joule heat) is an important factor in proper protection of electrical installations and devices. Studies were preformed during which the relationship between amount of energy and phase angle of short-circuit current was examined. Typically used miniature circuit breaker was utilized as a protective device. Scilab software for numerical computation was used to calculate the let-through energy based on recorded oscillograms of short-circuit current. Results of this calculations are presented.
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 2.

Tytuł:: Design and implementation of programmable ultrafast circuit breaker with solid state relay
Autorzy:: Omotayo, Mayowa Emmanuel
Olawuni, Adeolu
Tematy:: Ultra Fast
MCB
8051 Microcontroller
Overload
Mosfet; Pokaż więcej
Wydawca:: Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Powiązania:: https://bibliotekanauki.pl/articles/1192022.pdf Link otwiera się w nowym oknie
Opis:: The concept of electronic circuit breaker came into focus realizing that conventional circuit breakers such as MCBs take longer time to trip. Therefore, for sensitive loads it is very important to activate the tripping mechanism at the shortest possible time, preferably instantaneously. This project is demonstrates fast tripping mechanism as against the slow one like MCB. Electronic circuit breaker is based on the voltage drop across a series element proportional to the load current, typically a low value resistor. This voltage is sensed and rectified to DC which is and then compared with a preset voltage by a level comparator to generate an output that drives a relay through a MOSFET to trip the load. The unit is extremely fast and overcomes the drawback of the thermal type. It uses a microcontroller from 8051 family. The project was designed to shut down the power supply when it is overloaded. Conventional circuit breaker like MCB based is on thermal bimetal lever trip mechanism. It is very slow and the trip time is dependent upon the percentage of overload. This project senses the current passing through a series element and the corresponding voltage drop is compared against the preset voltage proportional to the current by a level comparator to generate an output for the load to trip.
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 3.

Tytuł:: Monte Carlo modelling of Th-Pb fuel assembly with californium neutron source
Autorzy:: Oettingen, M.
Stanisz, S.
Tematy:: californium
lead
Monte Carlo
MCB
thorium; Pokaż więcej
Wydawca:: Instytut Chemii i Techniki Jądrowej
Powiązania:: https://bibliotekanauki.pl/articles/147828.pdf Link otwiera się w nowym oknie
Opis:: This paper describes the methodology developed for the numerical reconstruction and modelling of the thorium-lead (Th-Pb) assembly available at the Department of Nuclear Energy, Faculty of Energy and Fuels, AGH University, Krakow, Poland. This numerical study is the first step towards integral irradiation experiments in the Th-Pb environment. The continuous-energy Monte Carlo burnup (MCB) code available on supercomputer Prometheus of ACK Cyfronet AGH was applied for numerical modelling. The assembly consists of a hexagonal array of ThO2 fuel rods and metallic Pb rods. The design allows for different arrangements of the rods for various types of irradiations and experimental measurements. The intensity of the fresh neutron source intended for integral experiments is about 108 n/s, which corresponds to the mass of about 43 μg 252Cf. The source was modelled in the form of Cf2O3-Pd cermet wire embedded in two stainless steel capsules.
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 4.

Tytuł:: Radionuclide neutron source trajectories in the closed nuclear fuel cycle
Autorzy:: Stanisz, Przemysław
Cetnar, Jerzy
Oettingen, Mikołaj
Tematy:: MCB
transmutation
equilibrium fuel cycle
LFR
trajectory period folding; Pokaż więcej
Wydawca:: Instytut Chemii i Techniki Jądrowej
Powiązania:: https://bibliotekanauki.pl/articles/147021.pdf Link otwiera się w nowym oknie
Opis:: The highest efficiency in the usage of nuclear energy resources can be implemented in fast breeder reactors of generation IV. It is achieved thanks to the ability of consuming minor actinides (MAs) in energy production. One of the options to use this benefit is full recycling of MAs to close the nuclear fuel cycle. Monte Carlo burn up (MCB), an integrated burn-up calculation code, deals with the complexity of the burn-up process which is applied to the European Lead-cooled Fast Reactor (ELFR). MCB uses continuous energy representation of cross section and spatial effects of full core reactor model; however, it automatically calculates nuclide production in all possible reactions or decay channels. Multi-recycling of MAs can cause an intensified build-up of curium, berkelium and californium. Some of their isotopes are strong neutron emitters from spontaneous fission, which hinders fuel recycling. The implementation of a novel methodology for trajectory period folding allows us to trace the life cycle of crucial MAs from the beginning of the reactor life towards the state of adiabatic equilibrium. The result of the analysis performed is presented, showing the sources of strong contribution to the neutron production rate. The parametric sensitivity analysis method for selected nuclide reactions is applied, revealing sensitivity of transmutation chains for the production of neutron emitter isotopes.
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 5.

Tytuł:: The MCB code for numerical modeling of Fourth Generation nuclear reactors
Autorzy:: Oettingen, M.
Cetnar, J.
Mirowski, T.
Tematy:: Monte Carlo
nuclear reactors
radiation transport
MCB
VHTR
LFR; Pokaż więcej
Wydawca:: Akademia Górniczo-Hutnicza im. Stanisława Staszica w Krakowie. Wydawnictwo AGH
Powiązania:: https://bibliotekanauki.pl/articles/305705.pdf Link otwiera się w nowym oknie
Opis:: R&D in the nuclear reactor physics demands state-of-the-art numerical tools that are able to characterize investigated nuclear systems with high accuracy. In this paper, we present the Monte Carlo Continuous Energy Burnup Code (MCB) developed at AGH University’s Department of Nuclear Energy. The code is a versatile numerical tool dedicated to simulations of radiation transport and radiation-induced changes in matter in advanced nuclear systems like Fourth Generation nuclear reactors.We present the general characteristics of the code and its application for modeling of Very-High-Temperature Reactors and Lead-Cooled Fast Rectors. Currently, the code is being implemented on the supercomputers of the Academic Computer Center (CYFRONET) of AGH University and will soon be available to the international scientific community.
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 6.

Tytuł:: Postępy obrazwania termicznego w medycynie – praca poświęcona osobie profesora Antoniego Nowakoweskiego
Advances of infrared thermal imaging in medicine – devoted to profesor Antoni Nowakowski
Autorzy:: Bauer, J.
Tematy:: termografia medyczna
132. Seminarium MCB
medical thermography
132. ICB Seminar; Pokaż więcej
Wydawca:: Politechnika Wrocławska. Wydział Podstawowych Problemów Techniki. Katedra Inżynierii Biomedycznej
Powiązania:: https://bibliotekanauki.pl/articles/262119.pdf Link otwiera się w nowym oknie
Opis:: Praca stanowi skrótowy przegląd wiedzy na temat historii oraz najnowszych osiągnięć termografii medycznej. Przesłanką do napisania niniejszej pracy stało się 132. Seminarium Międzynarodowego Centrum Biocybernetyki, które odbyło się na przełomie czerwca i lipca 2013 i było okazją do integracji oraz do wymiany poglądów międzynarodowych i krajowych środowisk naukowych, zajmujących się medycznymi zastosowaniami termografii. Inicjatorem i przewodniczącym Seminarium Advances of Infrared Thermal Imaging in Medicine był Profesor Antoni Nowakowski z Politechniki Gdańskiej.
This review presents briefly the history and current advances of thermal imaging in medicine. The reason to write it, it was the 132. Seminar of the International Center of Biocybernetics held in Warsaw from 30 June to 3 July 2013. The Seminar devoted to Advances of Infrared Thermal Imaging in Medicine was initiated and chaired by Professor Antoni Nowakowski from Gdańsk University of Technology.
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 7.

Tytuł:: Depletion analysis of the HELIOS experiment using the MCB code
Autorzy:: Oettingen, M.
D'Agata, E.
Döderlein, C.
Tuček, K.
Cetnar, J.
Tematy:: depletion
HELIOS
Monte Carlo continuous energy burn-up code (MCB)
minor actinides; Pokaż więcej
Wydawca:: Instytut Chemii i Techniki Jądrowej
Powiązania:: https://bibliotekanauki.pl/articles/146842.pdf Link otwiera się w nowym oknie
Opis:: The focus of our studies is to present an advanced depletion analysis of the HELIOS experiment by means of the Monte Carlo continuous energy burn-up code (MCB). The MCB was used mainly to calculate nuclide density evolution in nuclear reactor cores. We present the capability of the MCB to investigate the depletion of nuclear fuel samples irradiated in the HELIOS experiment. In our studies we traced the behaviour of the main fissile isotopes, 242mAm and 239Pu, respectively. We also perform a sensitivity analysis to the choice of JEF2.2 and JEFF3.1 cross section libraries in terms of the released fission power and the evolution of actinide inventories. The amount of He produced at the end of irradiation, as well as Am and Pu depletion, were also considered.
Dostawca treści:: Biblioteka Nauki

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na półce

Skocz do pozycji: 8.

Tytuł:: Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR
Autorzy:: Oettingen, M.
Cetnar, J.
Tematy:: comparative analysis
major actinides
MCB
Monte Carlo
ressurized water reactor (PWR); Pokaż więcej
Wydawca:: Instytut Chemii i Techniki Jądrowej
Powiązania:: https://bibliotekanauki.pl/articles/148636.pdf Link otwiera się w nowym oknie
Opis:: In the paper, we assess the accuracy of the Monte Carlo continuous energy burnup code (MCB) in predicting final concentrations of major actinides in the spent nuclear fuel from commercial PWR. The Ohi-2 PWR irradiation experiment was chosen for the numerical reconstruction due to the availability of the final concentrations for eleven major actinides including five uranium isotopes (U-232, U-234, U-235, U-236, U-238) and six plutonium isotopes (Pu-236, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242). The main results were presented as a calculated-to-experimental ratio (C/E) for measured and calculated final actinide concentrations. The good agreement in the range of ±5% was obtained for 78% C/E factors (43 out of 55). The MCB modeling shows significant improvement compared with the results of previous studies conducted on the Ohi-2 experiment, which proves the reliability and accuracy of the developed methodology.
Dostawca treści:: Biblioteka Nauki

Artykuł

na półce

Skocz do pozycji: 9.

Tytuł:: On the neutronics of European lead-cooled fast reactor
Autorzy:: Cetnar, J.
Oettingen, M.
Domańska, G.
Tematy:: fuel burn-up
plutonium
minor actinides
oxide fuel
nitride fuel
LFR
ELSY
MCB; Pokaż więcej
Wydawca:: Instytut Chemii i Techniki Jądrowej
Powiązania:: https://bibliotekanauki.pl/articles/148566.pdf Link otwiera się w nowym oknie
Opis:: The perspective of nuclear energy development in the near future imposes a new challenge on a number of sciences over the world. For years, the European Commission (EC) has sponsored scientific activities through the framework programmes (FP). The lead-cooled fast reactor (LFR) development in the European Union (EU) has been carried out within European lead-cooled system (ELSY) project of the 6th FP of EURATOM. This paper concerns the reactor core neutronic and burn-up design studies. We discuss two different core configurations of ELSY reactor; one loaded with the reference – mixed oxide fuel (MOX), whereas the second one with an advanced fuel – uranium- -plutonium nitride. Both fuels consist of reactor grade plutonium, depleted uranium and additionally, a fraction of minor actinides (MA). The fuel burn-up and the time evolution of the reactor characteristics has been assessed using a Monte Carlo burn-up code (MCB). One of the important findings concerns the importance of power profile evolution with burn-up as a limiting factor of the refuelling interval.
Dostawca treści:: Biblioteka Nauki

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