The thermal-hydraulic codes COBRA III-C and terhid and anlaysis and comparison

Simple item page
dc.contributorGraduate Program in Nuclear Engineering.
dc.contributor.advisorBorak, Fahir.
dc.contributor.authorÇağıl, Gülsevin.
dc.date.accessioned2023-03-16T13:52:11Z
dc.date.available2023-03-16T13:52:11Z
dc.date.issued1981.
dc.description.abstractIn this work the thermal-hydraulic programroes TERHID, which makes steady state and transient thermal-hydraulic analysis for plate type nuclear fuel elements , and COBRA 111-C, a computer programme for steady state and transient state therma l-hydraulic analysis of rod bundle fuel elements with subchannel approach analysed and compared. The comparison of the two programmes cover the anslysis of the conduction and the convection models, the assumptions made in the models , and the solution algorithms . The numerical applications consist of two parts. In the first part the sample problem given in TERBID is applied as input to COBRA 111-C. The transient solutions for different time increment are intercompared for this programme. In these condpart another applictaion is carried out for the identical problem using both codes by considering the effect of the inlet temperature change, inlet mass flux change and power change as a function of time during transients.
dc.format.extent30 cm.
dc.format.pagesxii, 109 leaves;
dc.identifier.otherNE 1981 C11
dc.identifier.urihttps://digitalarchive.library.bogazici.edu.tr/handle/123456789/19604
dc.publisherThesis (M.S.)- Bogazici University. Institute for Graduate Studies in Science and Engineering, 1981.
dc.relationIncludes appendices.
dc.relationIncludes appendices.
dc.subject.lcshNuclear reactors.
dc.subject.lcshComputer-aided engineering.
dc.titleThe thermal-hydraulic codes COBRA III-C and terhid and anlaysis and comparison

Files

Original bundle
Now showing 1 - 1 of 1
Thumbnail Image
Name:
b1168491.009992.001.PDF
Size:
2.72 MB
Format:
Adobe Portable Document Format
Download

Collections

M.S. Theses