Temat: reactor hydraulics - Katalog OPAC zbiorów

Skocz do pozycji: 1.

Tytuł:: The CFD modeling in bioreactor tracer studies
Autorzy:: Zima, P.
Powiązania:: https://bibliotekanauki.pl/articles/1933153.pdf
Data publikacji:: 2007
Wydawca:: Politechnika Gdańska
Tematy:: mathematical modeling
pollutant migration
reactor hydraulics
advection-dispersion equation
tracer studies
Opis:: This paper presents the effects of dispersion on predicting longitudinal tracer concentration profiles in an activated sludge bioreactor located at the Wschód Waste-Water Treatment Plant in Gdansk. The aim of this study has been to use the one-dimensional advection-dispersion equation to simulate a non-active substance flow (based on the measured tracer concentration). The simulation results were compared with those obtained in the traditional tanks-in-series approach, commonly used in designing biological reactors. The dispersion coefficient was calculated from a statistical formula based on differences in the tracer concentration distributions at two sampling points. The study has shown that the numerical simulation using the one-dimensional tracer migration equation yields better results than the tanks-in-series model in predicting longitudinal tracer concentration profiles. This paper is an in-troduction to the study of reactive substances in activated sludge bioreactors.
Źródło:: TASK Quarterly. Scientific Bulletin of Academic Computer Centre in Gdansk; 2007, 11, 4; 439-447
1428-6394
Pojawia się w:: TASK Quarterly. Scientific Bulletin of Academic Computer Centre in Gdansk
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 2.

Tytuł:: Neutronic and thermal-hydraulic coupling for 3D reactor core modeling combining MCB and fluent
Autorzy:: Królikowski, I. P.
Cetnar, J.
Powiązania:: https://bibliotekanauki.pl/articles/147457.pdf
Data publikacji:: 2015
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: code coupling
modeling
Monte Carlo
neutronics
nuclear reactor
thermal hydraulics
Opis:: Three-dimensional simulations of neutronics and thermal hydraulics of nuclear reactors are a tool used to design nuclear reactors. The coupling of MCB and FLUENT is presented, MCB allows to simulate neutronics, whereas FLUENT is computational fluid dynamics (CFD) code. The main purpose of the coupling is to exchange data such as temperature and power profi le between both codes. Temperature required as an input parameter for neutronics is significant since cross sections of nuclear reactions depend on temperature. Temperature may be calculated in thermal hydraulics, but this analysis needs as an input the power profile, which is a result from neutronic simulations. Exchange of data between both analyses is required to solve this problem. The coupling is a better solution compared to the assumption of estimated values of the temperatures or the power profiles; therefore the coupled analysis was created. This analysis includes single transient neutronic simulation and several steady-state thermal simulations. The power profi le is generated in defined points in time during the neutronic simulation for the thermal analysis to calculate temperature. The coupled simulation gives information about thermal behavior of the reactor, nuclear reactions in the core, and the fuel evolution in time. Results show that there is strong influence of neutronics on thermal hydraulics. This impact is stronger than the impact of thermal hydraulics on neutronics. Influence of the coupling on temperature and neutron multiplication factor is presented. The analysis has been performed for the ELECTRA reactor, which is lead-cooled fast reactor concept, where the coolant flow is generated only by natural convection.
Źródło:: Nukleonika; 2015, 60, No. 3, part 2; 531-536
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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Skocz do pozycji: 3.

Tytuł:: Modelling of thermal hydraulics in a KAROLINA calorimeter for its calibration methodology validation
Autorzy:: Luks, A.
Pytel, K.
Tarchalski, M.
Uzunow, N.
Krok, T.
Powiązania:: https://bibliotekanauki.pl/articles/147579.pdf
Data publikacji:: 2016
Wydawca:: Instytut Chemii i Techniki Jądrowej
Tematy:: computional fluid dynamics
CFD
differential calorimeter
gamma heating
gamma rays
Jules Horowitz Reactor
JHR
modelling of thermal hydraulics
nuclear heating
nuclear reactor
research
reactor MARIA
Opis:: Results of numerical calculations of heat exchange in a nuclear heating detector for nuclear reactors are presented in this paper. The gamma radiation is generated in nuclear reactor during fission and radiative capture reactions as well as radioactive decay of its products. A single-cell calorimeter has been designed for application in the MARIA research reactor in the National Centre for Nuclear Research (NCBJ) in Świerk near Warsaw, Poland, and can also be used in the Jules Horowitz Reactor (JHR), which is under construction in the research centre in Cadarache, France. It consists of a cylindrical sample, which is surrounded by a gas layer, contained in a cylindrical housing. Additional calculations had to be performed before its insertion into the reactor. Within this analysis, modern computational fuid dynamics (CFD) methods have been used for assessing important parameters, for example, mean surface temperature, mean volume temperature, and maximum sample (calorimeter core) temperature. Results of an experiment performed at a dedicated out-of-pile calibration bench and results of numerical modelling validation are also included in this paper.
Źródło:: Nukleonika; 2016, 61, 4; 453-460
0029-5922
1508-5791
Pojawia się w:: Nukleonika
Dostawca treści:: Biblioteka Nauki

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