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KTH, School of Engineering Sciences (SCI), Physics, Reactor Technology.
2009 (English)Independent thesis Advanced level (degree of Master (Two Years)), 20 credits / 30 HE creditsStudent thesis
Abstract [en]

The master thesis is concerned with the investigation of void fraction distributionsacross BWR fuel assemblies without spacers in minor scale design and with theinvestigation of the influence of different axial heat flux distribution and variations ofmass flux on the void fraction using Computational Fluid Dynamic (CFD) commercialcode CFX.11. The code is validated against experimental data obtained by R.T Lahey etal. [1]. A reasonable agreement between predictions and experimental data is obtainedfor the quality. However, some discrepancies are observed for the relative mass fluxdistributions. Further investigation and appropriate modelling in CFD code would beneeded to understand these inconsistencies.

The CFD code is also tested for BWR and PWR operational conditions. In case ofBWR, CFX suggests constant average void fraction distribution at the cross-section ofrod bundle near the exit at low mass flux and this distribution disrupted at higher massflux for different axial heat flux profiles. While, in case of PWR, CFX suggests that theaverage temperature distribution at the cross-section of the rod bundle near the exit isconstant for specific mass flux, average heat flux and no influence of different axial heatflux profile is detected.

Place, publisher, year, edition, pages
2009. , 47 p.
Trita-FYS, ISSN 0280-316X ; 2009:64
Keyword [en]
CFD, CFX, Rod bundle, Reactor, Reactor Technology, Nuclear, heat transfer
National Category
Engineering and Technology
URN: urn:nbn:se:kth:diva-129175OAI: diva2:650418
Subject / course
Nuclear Reactor Engineering
Educational program
Master of Science - Nuclear Energy Engineering
Available from: 2013-10-18 Created: 2013-09-21 Last updated: 2013-10-18Bibliographically approved

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