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dc.contributorKozlowski, Tomasz
dc.contributor.authorJara Heredia, Daniel
dc.date.accessioned2012-03-13T10:02:55Z
dc.date.available2012-03-13T10:02:55Z
dc.date.issued2010
dc.identifier.urihttp://hdl.handle.net/2099.1/14686
dc.description.abstractThe aim of the thesis is the assessment and validation of numerical models for the prediction of detailed subchannel distribution and departure from nucleate boiling (DNB) to a full scale data on a prototypical PWR rod bundle. To carry out this goal the participant will used TRACE, a software designed by the United State Nuclear Regulatoey Commision. The student should study implications on reactor design and safety analyses, propose changes/additions to reactor design and propose new experiments. The thesis is composed ny the following sections: - Introduction - Description of the Facility - Description of the Method - Description of the Model - Results - Conclusions
dc.language.isoeng
dc.publisherUniversitat Politècnica de Catalunya
dc.publisherKungliga Tecniska Högskolan
dc.subjectÀrees temàtiques de la UPC::Energies::Energia nuclear
dc.subject.lcshNuclear reactors
dc.titleDNB and Void Fraction TRACE Model Validation with PSBT Experiments
dc.typeMaster thesis (pre-Bologna period)
dc.subject.lemacReactors nuclears
dc.rights.accessOpen Access
dc.audience.educationlevelEstudis de primer/segon cicle
dc.audience.mediatorEscola Tècnica Superior d'Enginyeria Industrial de Barcelona
dc.description.mobilityOutgoing


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