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Title:Simulacija tokovnih razmer v vstopnem plenumu uparjalnika jedrske elektrarne s programom za računsko dinamiko tekočin
Authors:Kamenik, Blaž (Author)
Marn, Jure (Mentor) More about this mentor... New window
Kljenak, Ivo (Co-mentor)
Files:.pdf UN_Kamenik_Blaz_2017.pdf (1,91 MB)
 
Language:Slovenian
Work type:Bachelor thesis/paper (mb11)
Typology:2.11 - Undergraduate Thesis
Organization:FS - Faculty of Mechanical Engineering
Abstract:V diplomski nalogi so bile simulirane tokovne razmere v vstopnem plenumu in v začetnem delu cevnega snopa uparjalnika tlačnovodne jedrske elektrarne. Naloga je bila izvedena s pomočjo programa za računsko dinamiko tekočin ANSYS CFX. Za potrebe simulacije je bilo potrebno nekatere parametre določiti z empiričnimi korelacijami. Originalen doprinos naloge je, da je bil cevni snop modeliran kot porozen medij. Rezultati so pokazali, da so masni pretoki skozi različne sekcije cevnega snopa različni. Posledično je termična obremenitev cevi cevnega snopa neenakomerna.
Keywords:vstopni plenum jedrske elektrarne, uparjalnik, računska dinamika tekočin
Year of publishing:2017
Publisher:[B. Kamenik]
Source:Maribor
UDC:532.542:621.039.577(043.2)
COBISS_ID:21273622 Link is opened in a new window
NUK URN:URN:SI:UM:DK:E3ZGK9IZ
License:CC BY-NC-ND 4.0
This work is available under this license: Creative Commons Attribution Non-Commercial No Derivatives 4.0 International
Views:346
Downloads:76
Metadata:XML RDF-CHPDL DC-XML DC-RDF
Categories:KTFMB - FS
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Secondary language

Language:English
Title:Simulation of flow conditions in the inlet plenum of a nuclear power plant steam generator with a computational fluid dynamics code
Abstract:In the diploma, the flow conditions in the inlet plenum and the initial part of the tube bundle in a pressurized water reactor steam generator were simulated. The task was carried out with ANSYS CFX computational fluid dynamics software. For the needs of the simulations, some parameters had to be determined from empirical correlations. The original contribution of the assignment is that the tube bundle was modeled as a porous medium. The results showed that mass flows through different sections of the tube bundle are different. Consequently, the thermal load of the tubing (tube bundle) is uneven.
Keywords:inlet plenum of a nuclear power plant, steam generator, computational fluid dynamics


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