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Please use this identifier to cite or link to this item: http://hdl.handle.net/11375/12657
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dc.contributor.advisorBuijs, Adriaanen_US
dc.contributor.advisorJonkmans, Guyen_US
dc.contributor.authorRussell, Liam F.en_US
dc.date.accessioned2014-06-18T17:00:18Z-
dc.date.available2014-06-18T17:00:18Z-
dc.date.created2012-09-27en_US
dc.date.issued2012-10en_US
dc.identifier.otheropendissertations/7524en_US
dc.identifier.other8585en_US
dc.identifier.other3353865en_US
dc.identifier.urihttp://hdl.handle.net/11375/12657-
dc.description.abstract<p>When the material or geometry of a reactor varies with time, the neutron flux will respond in the form of a reactor transient. These transients can occur during normal operations when control rods are moved or the reactor is refuelled (CANDU). During a reactor accident, the transient response is especially important because the reactor properties vary quickly with large amplitudes. Therefore, better understanding these conditions allows for improved identification, prevention and mitigation of reactor transients. However, current nuclear simulation codes are generally limited in their ability to model transient behaviour.</p> <p>The NStable code was created to model time-dependent neutron populations in multiplying mediums using the Geant4 Monte Carlo toolkit. The neutron population is allowed to evolve in time, but is periodically renormalized so that the total number of neutrons is constrained within a manageable range. This ensures that the simulation is viable even in highly sub- or supercritical environments. Since Geant4 was not intrinsically designed to track a neutron population over "long" time periods (up to 10 s), the population renormalization mechanisms needed to be created and integrated with Geant4. Additionally, nuclear reactor analysis functionality was added to calculate important quantities such as k<sub>eff</sub>.</p> <p>The NStable code was validated using three established nuclear simulation codes: MCNP 5, DRAGON 3.06J, and TART 2005. The validation cases compared spatial distributions and criticality estimates for either homogeneous spheres (uranium-235 or a uranium-heavy water mixture) or the standard CANDU 6 lattice cell. For all three systems, the criticality estimates in NStable agreed with the appropriate validation code within 10 mk (TART for the spheres and DRAGON for the CANDU 6 lattice). Finally, the NStable code was also used to simulate a temperature transient in a UHW sphere where the temperature linear increased by 700 K over 50 ms. In response to the increasing temperature, k<sub>eff</sub> decreased by 100 mk over the same period. In the future, transient modelling in NStable should be investigated further to reproduce actual experimental results, and to couple NStable with a thermohydraulics code to simulate a full transient response.</p>en_US
dc.subjectMonte Carloen_US
dc.subjectreactor physicsen_US
dc.subjectnuclear engineeringen_US
dc.subjectstochasticen_US
dc.subjecttime-dependenten_US
dc.subjectGeant4en_US
dc.subjectEngineering Physicsen_US
dc.subjectNuclearen_US
dc.subjectNuclear Engineeringen_US
dc.subjectEngineering Physicsen_US
dc.titleSimulation of Time-Dependent Neutron Populations for Reactor Physics Applications Using the Geant4 Monte Carlo Toolkiten_US
dc.typethesisen_US
dc.contributor.departmentEngineering Physics and Nuclear Engineeringen_US
dc.description.degreeMaster of Applied Science (MASc)en_US
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