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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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    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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    A Computational Fluid Dynamics based model that predicts wall shear stress in CANDU outlet feeder pipes 

    Wijayaratne, Uditha (2018-01-01)
    Wall thinning of carbon steel in CANDU reactor outlet feeder pipes due to Flow Accelerated Corrosion (FAC) is identified as one of the challenges for CANDU reactors since it would force them to shut down due to safety ...
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    Petri net modeling of fault analysis for probabilistic risk assessment 

    Lee, Andrew (2013-04-01)
    Fault trees and event trees have been widely accepted as the modeling strategy to perform Probabilistic Risk Assessment (PRA). However, there are several limitations associated with fault tree/event tree modeling. These ...
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    Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study. 

    Farkas, Robert (2014-08-01)
    When the coolant is voided in a CANDU lattice, the net reactivity change is positive, due primarily to the fact that the coolant and moderator are separated and the coolant volume is much smaller than the moderator volume. ...
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    Computational fluid dynamic investigations of flow through an aged CANDU pressure tube 

    Lu, Zheng (2021-08-01)
    Single-phase, isothermal computational fluid dynamics simulations of twelve simplified CANDUTM 37M fuel bundles sitting in both as-received and aged pressure tubes were performed with Hydra in this work. The predicted ...
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    Simulation of in-core dose rates for an offline CANDU reactor 

    Gilbert, Jordan (2016-04-01)
    This thesis describes the development of a Monte Carlo simulation to predict the dose rates that will be encountered by a novel robotic inspection system for the pressure tubes of an offline CANDU reactor. Simulations were ...
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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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    AuthorAhmad, Mohammad Mateen (1)Carisse, Katarzyna (1)Farkas, Robert (1)Gilbert, Jordan (1)Haroon, Jawad (1)Lee, Andrew (1)Lu, Zheng (1)Wijayaratne, Uditha (1)Subject
    CANDU (8)
    Fuel channel (3)CFD (2)MCNP (2)Advanced homogenization (1)Annulus gas (1)Applied reactor physics (1)Coherent (1)CVR (1)Dose (1)... View MoreDate Issued2014 (3)2011 (1)2013 (1)2016 (1)2018 (1)2021 (1)Has File(s)Yes (8)

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