Browsing Master Theses & Projects by Title
Now showing items 45-64 of 80
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Leakage-corrected discontinuity factors for a second-generation Th-Pu pressure-tube SCWR.
(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 ... -
Local dose coefficients for radionuclide contamination in wounds
(2020-05-01)The objective of this research is to create local dose coefficients for radionuclide contaminated wounds to accompany dose coefficients obtained by Oak Ridge Institute for Science and Education looking at whole body effects ... -
Low energy photon mimic of the tritium beta decay energy spectrum
(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 ... -
Moderator displacers for reducing coolant void reactivity in CANDU reactors: a neutronics scoping study.
(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. ... -
Monte Carlo simulations for the purpose of efficiency curve calibration for the Fastscan whole body counter
(2015-08-01)In order to be able to qualify and quantify radiation exposure in terms of dose, a Fastscan whole body counter must be calibrated correctly. Current calibration methods do not take the full range of body types into ... -
Neutron production in a spherical phantom aboard the international space station
(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 ... -
One-dimensional single phase natural circulation model of FLiNaK in Molten Salt Loop
(2019-04-01)This work studied a coolant for a molten salt type reactor in terms of a natural circulation behavior. A natural circulation model using MATLAB was developed. This model is for the Molten Salt Loop currently under development ... -
Optimization of a GEM-based detector to measure tritium and discriminate against other radiation types
(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 ... -
Optimization of plastic scintillator thicknesses for online beta detection in mixed fields
(2010-12-01)For efficient beta detection in a mixed beta gamma field, Monte Carlo simulation models have been built to optimize the thickness of a plastic scintillator, used in whole body monitor. The simulation has been performed ... -
Petri net modeling of fault analysis for probabilistic risk assessment
(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 ... -
Planning and optimization of nuclear-renewable micro hybrid energy systems for off-grid applications
(2020-11-01)Resilient operation of medium/large scale off-grid energy systems is a key challenge for energy crisis solutions, which requires continuous and sustainable energy resources. In this context, microreactors are incorporated ... -
Polarization, passivation, intercalation, and generation: an examination of In-Situ and Ex-Situ analytical techniques for the study of carbon anode materials for the electrochemical generation of elemental fluorine.
(2011-12-01)The field of industrial fluorine generation has not made significant progress in the past 60 years due to the difficulty and hazards surrounding the use of hydrofluoric acid (HF) and fluorine gas. This work examines various ... -
Sensitivity analysis of fuel centerline temperatures in SuperCritical water-cooled reactors (SCWRs)
(2012-12-01)SuperCritical Water-cooled Reactors (SCWRs) are one of the six nuclear-reactor concepts currently being developed under the Generation-IV International Forum (GIF). A main advantage of SCW Nuclear Power Plants (NPPs) is ... -
Simulation of dynamic response of Self-Powered-Inconel-Neutron-Detector lead cables using a semi-empirical model
(2013-11-01)The work presented here was devoted to the modelling and simulation of the dynamic response of lead cables of Inconel self-powered neutron detectors in a CANDUpower reactor. The main goal was to develop a semi-empirical ... -
Simulation of in-core dose rates for an offline CANDU reactor
(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 ... -
Simulation, design and construction of a gas electron multiplier for particle tracking
(2012-12-01)The biological effects of charged particles is of interest in particle therapy, radiation protection and space radiation science and known to be dependent on both absorbed dose and radiation quality or LET. Microdosimetry ... -
Special isotopes of the FUGEN nuclear reactor
(2022-04-01)The Canadian and Japanese nuclear regulatory bodies have shown dissimilarities between the isotopes considered to be of interest in decommissioning similarly styled heavy water reactors. This research examines the quantity ... -
Specifics of forced-convection heat transfer in a vertical 7-element bundle cooled with upward flow of SuperCritical Water
(2020-08-17)Current Generation II/III/III+ Nuclear Power Plants (NPPs) are no longer economically competitive partially due to low thermal efficiencies. Six Generation IV NPP concepts were proposed having increased thermal efficiency, ... -
Specifics of forced-convection heat transfer to supercritical water flowing upward in annular and bundle flow geometries
(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 ... -
Steam-reheat option for supercritical-water-cooled reactors
(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 ...