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    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 ...
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    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 ...
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    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 ...
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    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; ...
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    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 ...
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    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 ...
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    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 ...
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    Transmutation rates in the annulus gas of pressure tube water reactors 

    Ahmad, Mohammad Mateen (2011-07-01)
    CANDU (CANada Deuterium Uranium) reactor utilizes Pressure Tube (PT) fuel channel design and heavy water as a coolant. Fuel channel annulus gas acts as an insulator to minimize heat losses from the coolant to the moderator. ...
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    Optimization of a GEM-based detector to measure tritium and discriminate against other radiation types 

    Dhinakar, Arvind (2019-11-01)
    Tritium poses a radioprotection issue, in the Canadian Nuclear industry due to the operation of its fleet of Canadian Deuterium Uranium (CANDU) heavy water reactors. Although it is a less penetrative radionuclide, tritium ...
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    Dosimetric characterization of a miniature x-ray source for biophysics studies 

    Virdi, Karanvir Singh (2015-07-01)
    Tritium is a low energy beta emitter that is found in abundance at CANDU nuclear power plants and is a cause of concern since it accounts for roughly thirty three percent of the total occupational exposure of nuclear ...
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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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