• Login
    Search 
    •   eScholar Home
    • Faculty of Energy Systems & Nuclear Science
    • Master Theses & Projects
    • Search
    •   eScholar Home
    • Faculty of Energy Systems & Nuclear Science
    • Master Theses & Projects
    • Search
    JavaScript is disabled for your browser. Some features of this site may not work without it.

    Search

    Show Advanced FiltersHide Advanced Filters

    Filters

    Use filters to refine the search results.

    Now showing items 1-5 of 5

    • Sort Options:
    • Relevance
    • Title Asc
    • Title Desc
    • Issue Date Asc
    • Issue Date Desc
    • Results Per Page:
    • 5
    • 10
    • 20
    • 40
    • 60
    • 80
    • 100
    Thumbnail

    Study on supercritical fluids in an intermediate heat exchanger for an SCWR hydrogen cogeneration system 

    Jouvin, Juan Carlos (2015-12-01)
    SuperCritical Water-cooled Reactors (SCWRs) are one of six Generation-IV nuclear reactor concepts under development worldwide. SCWRs benefit from an increase in thermal efficiency due to the reactor coolant operating above ...
    Thumbnail

    Specifics of forced-convection heat transfer to supercritical water flowing upward in annular and bundle flow geometries 

    Sidawi, Khalil (2016-08-01)
    Since annulus- and bundle-flow geometries impede coolant flow, heat transfer to the coolant would occur differently than in bare tubes. The main objective of this work is to propose and verity a universal method to accurately ...
    Thumbnail

    Developing 1-D heat transfer correlations for supercritical water and carbon dioxide in vertical tubes 

    Gupta, Sahil (2014-03-01)
    Taking into account the expected increase in global energy demands and increasing climate change issues, there is a pressing need to develop new environmentally sustainable energy systems. Nuclear energy will play a major ...
    Thumbnail

    Conceptual design of a thermal hydraulic loop for multiple test geometries at supercritical conditions named supercritical phenomena experimental test apparatus (SPETA) 

    Adenariwo, Adepoju (2012-04-01)
    The efficiency of nuclear reactors can be improved by increasing the operating pressure of current nuclear reactors. Current CANDU-type nuclear reactors use heavy water as coolant at an outlet pressure of up to 11.5 MPa. ...
    Thumbnail

    Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications 

    Mokry, Sarah (2009-12-01)
    A large set of experimental data, obtained in Russia, was analyzed and a new heat-transfer correlation for supercritical water was developed. This experimental dataset was obtained within conditions similar to those for ...

    DSpace software copyright © 2002-2016  DuraSpace
    Contact Us | Send Feedback
    Theme by 
    Atmire NV
     

     

    Browse

    All of eScholarCommunities & CollectionsBy Issue DateAuthorsTitlesSubjectsThis CollectionBy Issue DateAuthorsTitlesSubjects

    My Account

    LoginRegister

    Discover

    AuthorAdenariwo, Adepoju (1)Gupta, Sahil (1)Jouvin, Juan Carlos (1)Mokry, Sarah (1)Sidawi, Khalil (1)Subject
    Supercritical water (5)
    Heat transfer (2)Computational fluid dynamics (1)Correlations (1)Experimental loop design (1)Forced-convection (1)Generation IV (1)Generation IV nuclear reactors (1)Heat exchanger (1)Heat transfer correlations (1)... View MoreDate Issued2009 (1)2012 (1)2014 (1)2015 (1)2016 (1)Has File(s)Yes (5)

    DSpace software copyright © 2002-2016  DuraSpace
    Contact Us | Send Feedback
    Theme by 
    Atmire NV