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Title:Primerjava reaktorske tlačne posode II. in III. generacije
Authors:Gračner, Gregor (Author)
Marn, Jure (Mentor) More about this mentor... New window
Files:.pdf UNI_Gracner_Gregor_2012.pdf (4,10 MB)
 
Language:Slovenian
Work type:Bachelor thesis/paper (mb11)
Typology:2.11 - Undergraduate Thesis
Organization:FS - Faculty of Mechanical Engineering
Abstract:Diplomsko delo zajema splošno primerjavo reaktorske tlačne posode II. generacije z reaktorsko tlačno posodo III. in III.+ generacije, s konkretnimi predstavniki. Glavni del diplomske naloge je pregled scenarijev majhne izlivne nezgode za dva reaktorja III.(III.+) generacije in sicer EPR in AP1000. Za analize so uporabljeni rezultati, ki so pridobljeni s pomočjo testnega objekta APEX-1000, ki simulira reaktor AP1000 in testnega objekta PKL, ki simulira reaktor EPR. Rezultati prikazujejo termohidravlične razmere v primarnem sistemu reaktorja v primeru različnih scenarijev nezgod in potrjujejo začetno tezo, da so varnostni sistemi, v primeru majhne izlivne nezgode, zmožni popolnoma varno odvajati zaostalo toploto iz sistema.
Keywords:reaktor NEK, reaktor AP1000, reaktor EPR, reaktorska tlačna posoda, majhna izlivna nezgoda, termohidravlični kriteriji, pasivni varnostni sistem, testni objekt APEX-1000, testni objekt PKL
Year of publishing:2012
Publisher:[G. Gračner]
Source:Maribor
UDC:621.039.536.2(043.2)
URN:URN:SI:UM:DK:MPFVRZ4O
COBISS_ID:16385814 Link is opened in a new window
Views:1066
Downloads:186
Metadata:XML RDF-CHPDL DC-XML DC-RDF
Categories:KTFMB - FS
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Secondary language

Language:English
Title:Comparison of reactor pressure vessel
Abstract:The diploma thesis contains basic comparison of reactor pressure vessel of II. generation and of the reactor pressure vessel of III. and III. + generation with concrete representatives. The main part of diploma thesis is the review of scenarios of small-break loss of coolant accident (SB-LOCA) for two reactors of III.(III.+) generation which are EPR and AP1000. For the analyses, results, gained with the help of test facility APEX-1000 which simulates the reactor AP1000 and test facility PKL that simulates the reactor EPR, are used. The results show thermohydraulic conditions in reactors’ primary system in case of different accident scenarios and confirm the earlier thesis that security systems are, in a case of small-break loss of coolant accident, absolutely capable to safely divert the residual heat from the system.
Keywords:reactor NEK, reactor AP1000, reactor EPR, reactor pressure vessel, small-break loss of coolant accident, thermohydraulic criteria, passive safety system, test facility APEX-1000, test facility PKL


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