• Login
    Search 
    •   eScholar Home
    • Faculty of Energy Systems & Nuclear Science
    • Search
    •   eScholar Home
    • Faculty of Energy Systems & Nuclear Science
    • 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 1-10 of 71

    • 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 of fuzzy logic in safety and control systems in nuclear power plants 

    Deol, Harsh (2016-03-01)
    Safety and control systems in Nuclear Power Plants are essentially run without intelligent systems. As nuclear industry starts to become more advanced and vendors are starting to manufacture more advance products, old ...
    Thumbnail

    Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors. 

    Haroon, Jawad (2014-08-01)
    In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU ...
    Thumbnail

    Assessment of FLUENT CFD code as an analysis tool for SCW applications 

    Farah, Amjad (2012-08-01)
    Chosen as one of six Generation‒IV nuclear-reactor concepts, SuperCritical Water-cooled Reactors (SCWRs) are expected to have high thermal efficiencies within the range of 45 ‒ 50% owing to the reactor‟s high pressures and ...
    Thumbnail

    Three dimensional heterogeneous finite element method for static multi-group neutron diffusion 

    Aydogdu, Elif Can (2010-08-01)
    Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; ...
    Thumbnail

    The application of experimental microdosimetry to mixed-field neutron-gamma dosimetry 

    Al-Bayati, Saad Najm (2012-12-01)
    Absorbed dose distributions in lineal energy for neutrons and gamma rays were measured by using both a tissue-equivalent walled counter (TEPC) and a graphite-walled low pressure proportional counter (GPC) in the Am-Be ...
    Thumbnail

    Neutron production in a spherical phantom aboard the international space station 

    Tasbaz, Azadeh (2010-12-01)
    Since the beginning of space exploration in last century, several kinds of devices from passive and active dosimeters to radiation environment monitors have been used to measure radiation levels onboard different space ...
    Thumbnail

    Development and characterization of a high resolution portable gamma spectrometer 

    Ali, Muhammad (2012-04-01)
    The recent disaster of Fukushima in Japan combined with the high demand to enhance nuclear safety and to minimize personal exposure to radioactive materials has a significant impact on research and development of radiation ...
    Thumbnail

    Dynamic accident sequence analysis using dynamic flowgraph method and Markov/cell-to-cell mapping technique 

    Zeliang, Chireuding (2018-07-01)
    In the recent years, numerous concerns have been raised regarding the capabilities and adequacy of classical probabilistic safety assessment (PSA) techniques (fault/event tree) to account for dynamic system interactions ...
    Thumbnail

    Polarization, passivation, intercalation, and generation: an examination of In-Situ and Ex-Situ analytical techniques for the study of carbon anode materials for the electrochemical generation of elemental fluorine. 

    Seto, Kelvin (2011-12-01)
    The field of industrial fluorine generation has not made significant progress in the past 60 years due to the difficulty and hazards surrounding the use of hydrofluoric acid (HF) and fluorine gas. This work examines various ...
    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. ...
    • 1
    • 2
    • 3
    • 4
    • . . .
    • 8

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

     

    Browse

    All of eScholarCommunities & CollectionsBy Issue DateAuthorsTitlesSubjectsThis CommunityBy Issue DateAuthorsTitlesSubjects

    My Account

    LoginRegister

    Discover

    AuthorFarah, Amjad (2)Lipchitz, Adam (2)Nasimi, Elnara (2)Peiman, Wargha (2)Saltanov, Eugene (2)Abdalla, Ayman (1)Adenariwo, Adepoju (1)Ahmad, Mohammad Mateen (1)Al-Bayati, Saad Najm (1)Ali, Muhammad (1)... View MoreSubjectCANDU (8)Heat transfer (6)SCWR (6)MCNP (5)Nuclear (4)Supercritical water (4)Tritium (4)CFD (3)Efficiency (3)Heat exchanger (3)... View MoreDate Issued2010 (9)2015 (9)2016 (9)2012 (8)2011 (7)2014 (7)2018 (7)2019 (6)2013 (5)2017 (4)Has File(s)Yes (71)

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