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    Characterization of neutron fields around an intense neutron generator 

    Kicka, Leslie (2016-12-01)
    Neutron fields in the vicinity of the University of Ontario Institute of Technology neutron facility have been investigated in a series of simulations and experiments. The neutron fluence at several locations around the ...
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    Low energy photon mimic of the tritium beta decay energy spectrum 

    Malabre-O'Sullivan, Neville (2013-04-01)
    Tritium is a radioactive hydrogen isotope that is typically produced via neutron interaction with heavy water (D2O), producing tritiated water (DTO). As a result of this, tritium accounts for roughly a third of all ...
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    Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR. 

    Carisse, Katarzyna (2014-08-01)
    The neutron flux throughout a reactor core should be calculated, ideally, by solving the neutron transport equation for a highly detailed geometric model of the core. Since this is computationally impractical, approximate ...
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    Thermal aspects of high efficiency channel with conventional and alternative fuels in SuperCritical water-cooled reactor (SCWR) applications 

    Peiman, Wargha (2011-03-01)
    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 reactor‘s high outlet temperatures. ...
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    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 ...
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    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 ...
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    Steam-reheat option for supercritical-water-cooled reactors 

    Saltanov, Eugene (2010-12-01)
    SuperCritical-Water-cooled Reactors (SCWRs) are being developed as one of the Generation-IV nuclear-reactor concepts. Main objectives of the development are to increase thermal efficiency of a Nuclear Power Plant (NPP) and ...
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    Development of thermodynamic cycles for sodium-cooled-fast reactors. 

    Dragunov, Alexey (2013-12-01)
    Currently, one engineering challenge is designing Generation IV (GEN-IV) Nuclear Power Plants (NPPs) with significantly higher thermal efficiencies compared to current NPPs, and to match, or at least to be close to, the ...
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    Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP 

    Thind, Harwinder (2012-04-01)
    SuperCritical-Water-cooled Reactors (SCWRs) are being developed as one of the Generation-IV nuclear-reactor concepts. SuperCritical Water (SCW) Nuclear Power Plants (NPPs) are expected to have much higher operating parameters ...
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    Study of heat transfer in a 7-element bundle cooled with the upward flow of supercritical Freon-12 

    Richards, Graham (2012-04-01)
    Experimental data on SuperCritical-Water (SCW) cooled bundles are very limited. Major problems with performing such experiments are: 1) small number of operating SCW experimental setups and 2) difficulties in testing and ...
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    AuthorAbdalla, Ayman (1)Adenariwo, Adepoju (1)Ahmad, Mohammad Mateen (1)Al-Bayati, Saad Najm (1)Ali, Muhammad (1)Aydogdu, Elif Can (1)Broughton, David (1)Carisse, Katarzyna (1)Chaput, Joseph (1)Choi, Sungcheol (Eric) (1)... View MoreSubjectCANDU (7)Heat transfer (5)MCNP (5)SCWR (5)Supercritical water (4)Tritium (4)Efficiency (3)Heat exchanger (3)Nuclear (3)Simulation (3)... View MoreDate Issued2010 (9)2012 (8)2011 (7)2016 (7)2019 (6)2013 (5)2014 (5)2015 (5)2018 (3)2017 (1)Has File(s)
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