Temat: control rod - Katalog OPAC zbiorów

Skocz do pozycji: 1.

Tytuł:: Assessment of the control rods shadow effect in the VENUS-F core
Autorzy:: Cetnar, J.
Domańska, G.
Gajda, P.
Janczyszyn, J.
Powiązania:: https://bibliotekanauki.pl/articles/147908.pdf
Data publikacji:: 2014
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: accelerator driven systems (ADS)
control rod
FREYA
GUINEVERE
reactivity
Opis:: The partitioning and transmutation (P&T) of spent nuclear fuel is an important fi eld of present development of nuclear energy technologies. One of the possible ways to carry out the P&T process is to use the accelerator driven systems (ADS). This technology has been developed within the EURATOM Framework Programmes for several years now. Current research in this fi eld is carried out within the scope of 7th FP project FREYA. Important parts of the project are experiments performed in the GUINEVERE facility devoted to characterising the subcritical core kinetics and development of reactivity monitoring techniques. The present paper considers the effects of control rods use on the core reactivity. In order to carry out the evaluation of the experimental results, it is important to have detailed core characteristics at hand and to take into consideration the differences in the effect of control rods acting separately or together (the so-called shadow effect) on both the reactivity value and the measured neutron fl ux. Also any core asymmetry should be revealed. This goal was achieved by both MCNP simulations and the experimental results. However, in the case of experimental results, the need for calculating respective correction factors was unavoidable.
Źródło:: Nukleonika; 2014, 59, 4; 137-143
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 2.

Tytuł:: Estimation of control rod worth in a VVER-1000 reactor using DRAGON4 and DONJON4
Autorzy:: Saadatian-derakhshandeh, F.
Safarzadeh, O.
Shirani, A. F.
Powiązania:: https://bibliotekanauki.pl/articles/146900.pdf
Data publikacji:: 2014
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: control rod worth
DRAGON4
DONJON4
VVER-1000 reactor
Opis:: One of the main issues in safety and control systems design of power and research reactors is to prevent accidents or reduce the imposed hazard. Control rod worth plays an important role in safety and control of reactors. In this paper, we developed a justifiable approach called D4D4 to estimate the control rod worth of a VVER-1000 reactor that enables to perform the best estimate analysis and reduce the conservatism that utilize DRAGON4 and DONJON4. The results are compared with WIMS-D4/CITATION to show the effectiveness and superiority of the developed package in predicting reactivity worth of the rod and also other reactor physics parameters of the VVER-1000 reactor. The results of this study are in good agreement with the plant’s FSAR.
Źródło:: Nukleonika; 2014, 59, 2; 67-72
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 3.

Tytuł:: Study of temperature distribution of fuel, clad and coolant in the VVER-1000 reactor core during group-10 control rod scram by using diffusion and point kinetic methods
Autorzy:: Rahgoshay, M.
Rahmani, Y.
Powiązania:: https://bibliotekanauki.pl/articles/146827.pdf
Data publikacji:: 2007
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: point kinetic
diffusion
COSTANZA-R,Z
VVER-1000
control rod
RELAP5
Opis:: In this paper, through the application of two different methods (point kinetic and diffusion), the temperature distribution of fuel, clad and coolant has been studied and calculated during group-10 control rod scram, in the Bushehr Nuclear Power Plant (Iran) with a VVER-1000 reactor core. In the reactor core of Bushehr NPP, 10 groups of control rods are used of which, group-10 control rods contain the highest amount of injected negative reactivity in terms of quantity as compared to other groups of control rods. In this paper we explain impacts of negative reactivity, caused by a complete or minor scram of group-10 control rods, on thermoneutronic parameters of the VVER-1000 nuclear reactor core. It should be noted that through these calculations and by using the results, we can develop a sound understanding of impacts of this controlling element in optimum control of the reactor core and, on this basis, with careful attention and by gaining access to a reliable simulation (on the basis of results of calculations made in this survey) we can monitor the VVER-1000 reactor core through a smart control system. In continuation, for a more accurate survey and for comparing results of different calculation systems (point kinetic and diffusion), by using COSTANZA-R,Z calculation code (in which neutronic calculations are based on diffusion model) and using WIMS code at different areas and temperatures (for calculation of constant physical coefficients and temperature coefficients needed in COSTANZAR, Z code) for the VVER-1000 reactor core of Bushehr NPP, calculation of temperature distribution of fuel elements and coolant by using diffusion model is made in the course of group-10 control rods scram and afterwards.
Źródło:: Nukleonika; 2007, 52, 4; 159-165
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 4.

Tytuł:: The effects of fuel type on control rod reactivity of pebble-bed reactor
Autorzy:: Zuhair, Zuhair
Suwoto, Suwoto
Setiadipura, Topan
Kuijper, Jim C.
Powiązania:: https://bibliotekanauki.pl/articles/971546.pdf
Data publikacji:: 2019
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: fuel type
control rod reactivity
pebble-bed reactor
MCNP6
ENDF/B-VII
Opis:: As a crucial core physics parameter, the control rod reactivity has to be predicted for the control and safety of the reactor. This paper studies the control rod reactivity calculation of the pebble-bed reactor with three scenarios of UO2, (Th,U)O2, and PuO2 fuel type without any modifi cations in the confi guration of the reactor core. The reactor geometry of HTR-10 was selected for the reactor model. The entire calculation of control rod reactivity was done using the MCNP6 code with ENDF/B-VII library. The calculation results show that the total reactivity worth of control rods in UO2-, (U,Th)O2-, and PuO2-fueled cores is 15.87, 15.25, and 14.33%k/k, respectively. These results prove that the effectiveness of total control rod in thorium and uranium cores is almost similar to but higher than that in plutonium cores. The highest reactivity worth of individual control rod in uranium, thorium and plutonium cores is 1.64, 1.44, and 1.53%k/k corresponding to CR8, CR1, and CR5, respectively. The other results demonstrate that the reactor can be safely shutdown with the control rods combination of CR3+CR5+CR8+CR10, CR2+CR3+CR7+CR8, and CR1+CR3+CR6+CR8 in UO2-, (U,Th)O2-, and PuO2-fueled cores, respectively. It can be concluded that, even though the calculation results are not so much different, however, the selection of control rods should be considered in the pebble-bed core design with different scenarios of fuel type.
Źródło:: Nukleonika; 2019, 64, 4; 131-138
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 5.

Tytuł:: Diagnostics of control rod drive. Possibilities to extend its lifetime at NPPs
Diagnostyka napędu pręta sterującego. Możliwości zwiększenia czasu eksploatacji napędów w elektrowniach atomowych
Autorzy:: Druzhinin, I.
Sapozhnikova, K.
Taymanov, R.
Powiązania:: https://bibliotekanauki.pl/articles/329298.pdf
Data publikacji:: 2008
Wydawca:: Polska Akademia Nauk. Polskie Towarzystwo Diagnostyki Technicznej PAN
Tematy:: elektromagnetyczny liniowy silnik krokowy
czujnik położenia
pręt sterujący
czas eksploatacji
reaktor jądrowy
linear stepping electromagnetic drive
control rod position sensor
lifetime
nuclear reactor
Opis:: According to specifications, lifetime of a linear stepping electromagnetic drive in WWER-1000 nuclear reactors is limited by the pre-assigned lifetimes of the drive components such as electromagnets, a latch assembly, drive rack, and control rod position sensor. The lifetime of the drive components is from 7 to 20 years. On the basis of diagnostics of these components under real conditions, actual lifetimes of the components at nuclear power plant (NPP) were forecasted. It is shown that in order to extend the lifetime of the drive components up to the reactor lifetime (60 years), it is necessary to replace the sensor of the DPL-type by the new one (of the DPL-KV type) and to decrease the electromagnet temperature. The Measuring and Diagnostic System with the DPL-KV sensor enables diagnosing the sensor, electronic processing unit and drive. Economic effect due to the cumulative technical decisions is estimated to be 7 mln.euro per NPP unit.
Zgodnie z dokumentacją czas eksploatacji elektromagnetycznych silników krokowych prętów sterujących w reaktorach jądrowych WWER-1000 jest ograniczony ustalonymi czasami eksploatacji ich składników (blok przesunięcia, pręt, elektromagnesy, czujnik) - od 7 do 20 lat. Na podstawie wyników diagnostyki tych składników w warunkach realnych została zrobiona prognoza ich rzeczywistej żywotności w elektrowniach atomowych. Wykazano, że w celu wydłużenia czasu eksploatacji składników do czasu życia reaktora (60 lat) trzeba wymienić czujnik DPL na inny, bardziej niezawodny - DPL-KV i znacznie obniżyć temperaturę elektromagnesów. Układ pomiarowo-diagnostyczny wyposażony w czujnik DPL-KV pozwala przeprowadzać diagnostykę czujnika, osprzętu elektronicznego i silnika. Całkowity efekt ekonomiczny wprowadzenia zaproponowanych rozwiązań technicznych jest szacowany na 7 milionów Euro na blok energetyczny.
Źródło:: Diagnostyka; 2008, 3(47); 89-93
1641-6414
2449-5220
Pojawia się w:: Diagnostyka
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 6.

Tytuł:: Source term model for streamwise Rod Vortex Generator modelling
Autorzy:: Kwiatkowski, T.
Flaszyński, P.
Powiązania:: https://bibliotekanauki.pl/articles/244365.pdf
Data publikacji:: 2016
Wydawca:: Instytut Techniczny Wojsk Lotniczych
Tematy:: source term model
rod vortex generator
streamwise vortices
flow control
BAY model
BAY method
Opis:: In the article, the new method of modelling of Rod Vortex Generators (RVGs) was proposed. RVGs are inclined rods, mounted in boundary layer used to flow control. RVGs were intensively investigated in Institute of Fluid-Flow Machinery in Gdansk, Poland. The research results indicate high potential of RVGs to flow control in wide range of Mach numbers (Mach 0.3-1.45) in the main flow. Due to the flow structure details generated by RVG, it is required to create fine grids in the vicinity of RVGs, which increase the computational cost. In order to overcome this difficulty and reduce computational cost the new numerical models of RVGs are proposed, which use the modification of BAY model. Using BAY model it is not needed to resolve the shape of RVG in detail and it is possible to use orthogonal meshes. The BAY model was originally proposed to predict flows behind thin-plate vortex generators. This model works by adding momentum source term to Reynolds-Averaged Navier-Stokes equations in ANSYS Fluent. The BAY model spatial vectors orientation was modified and some simplifications were performed. The model was calibrated and simulations were carried out for the single rod. The results and effectiveness of modified BAY model were compared with wind-tunnel experiment results and grid-resolved model.
Źródło:: Journal of KONES; 2016, 23, 4; 261-268
1231-4005
2354-0133
Pojawia się w:: Journal of KONES
Dostawca treści:: Biblioteka Nauki

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