Browsing Faculty of Energy Systems & Nuclear Science by Title
Now showing items 92-98 of 98
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Theoretical performance analysis of a novel hemispherical tissue equivalent proportional counter for neutron monitoring and dosimetry
(2016-02-01)Neutron dosimetry in reactor fields is currently conducted using thermal neutron flux monitors. It has been demonstrated that Tissue Equivalent Proportional Counters (TEPCs) have the potential to improve the accuracy of ... -
Thermal aspects of high efficiency channel with conventional and alternative fuels in SuperCritical water-cooled reactor (SCWR) applications
(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. ... -
Thermal aspects of using alternative nuclear fuels in supercritical water-cooled reactors
(2010-11-01)A SuperCritical Water-cooled Nuclear Reactor (SCWR) is a Generation IV concept currently being developed worldwide. Unique to this reactor type is the use of light-water coolant above its critical point. The current research ... -
Three dimensional heterogeneous finite element method for static multi-group neutron diffusion
(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; ... -
Towards low dose retrospective dosimetry on shelled species
(2020-08-01)This work investigates calcified tissues of shelled species for retrospective dosimetry using electron paramagnetic resonance (EPR) spectroscopy. To determine applicable samples for low dose studies, shells of crustacean ... -
Transmutation rates in the annulus gas of pressure tube water reactors
(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. ... -
Using MELCOR with enhanced predictive capabilities via Thermochimica to model two severe accident cases of a generic BWR with Zry-2 and FeCrAl
(2022-07-01)The primary goal of this work was to enhance MELCOR’s material modelling capabilities via one-way coupling of Thermochimica. MELCOR is a state-of-the-art code used to simulate the severe accident progression of a nuclear ...