Browsing Faculty of Energy Systems & Nuclear Science by Author "Harvel, Glenn"
Now showing items 1-14 of 14
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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 ... -
CFD determination of fluid and geometry related localized heat transfer phenomena for supercritical water flow
Farah, Amjad (2017-04-01)The proposed concept of Supercritical Water-cooled Reactor (SCWR) as part of the Generation IV International Forum aims to improve the thermal efficiency over current power plants by utilizing cooling water at pressures ... -
Characterization of eutectic In-Bi-Sn alloy (Field’s metal) for use in single and two-phase liquid metal flow in natural circulation systems
Lipchitz, Adam (2015-04-01)An In-Bi-Sn eutectic alloy was characterized for the purpose of liquid metal natural circulation experiments. The alloy was chosen to reduce the power requirement and enhance the safety of these types of experiments. The ... -
Characterization of PVA-Borax-fructose gel for the capture of radioactive wastes generated during nuclear decommissioning activities
Sarvendran, Vajran Timothy (2021-05-01)With the long-term objective of using polymer gels for the capture of solid, liquid and gaseous waste generated from decommissioning works, characterization of gel properties as well as the properties of the individual ... -
Conceptual design for a re-entrant type fuel channel for supercritical water-cooled nuclear reactors
Samuel, Jeffrey (2011-04-01)Current CANDU-type nuclear reactors use a once-through fuel-channel with an annulus gas insulating it from the moderator. The current reference design for a CANDU-type SuperCritical Water-Cooled Reactor (SCWR) is to eliminate ... -
Conceptual design of a thermal hydraulic loop for multiple test geometries at supercritical conditions named supercritical phenomena experimental test apparatus (SPETA)
Adenariwo, Adepoju (2012-04-01)The efficiency of nuclear reactors can be improved by increasing the operating pressure of current nuclear reactors. Current CANDU-type nuclear reactors use heavy water as coolant at an outlet pressure of up to 11.5 MPa. ... -
Electrohydrodynamic enhancement of extraterrestrial capilliary pumped loops for nuclear applications
Lipchitz, Adam (2010-12-01)This work examines electrohydrodynamic enhancement of capillary pump loops (CPL) for use in extraterrestrial nuclear applications. A capillary pump uses capillary action through a porous wick to transport heat and mass. ... -
Environmental impact of zebra mussel controls in nuclear power plants
Wong, Jason (Wei Chung) (2020-04-01)Industries that rely on the Great Lakes for cooling have battled the zebra mussel infestation for years. With increasing emphasis on environmental sustainability, decision-makers need to consider more than just monetary ... -
Heat-transfer analysis of double-pipe heat exchangers for indirect-cycle SCW NPP
Thind, Harwinder (2012-04-01)SuperCritical-Water-cooled Reactors (SCWRs) are being developed as one of the Generation-IV nuclear-reactor concepts. SuperCritical Water (SCW) Nuclear Power Plants (NPPs) are expected to have much higher operating parameters ... -
Implementation of power electronics in nuclear power plants: DC electrical system conceptual design and its financial analysis
Li, Enoch Yinuo (2018-05-01)A Power Electronic (PE) device is a semiconductor-based device which enable many advanced conversion of electricity which have been used widely in many industries. Due to the recent development in both circuit design and ... -
One-dimensional single phase natural circulation model of FLiNaK in Molten Salt Loop
Choi, Sungcheol (Eric) (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 ... -
Specifics of forced-convective heat transfer to supercritical CO2 flowing upward in vertical bare tubes
Saltanov, Eugene (2015-04-01)Heat transfer in the forced convection regime of fluids at supercritical conditions has been studied extensively for the past 60 years. The dominant approach to summarize the experimental results was by proposing empirical ... -
Study of contaminants in plasmas during decommissioning processes
Somer, Nicholas (2020-12-01)With the intention of eventual development of on-site radionuclide capture technologies, methods to simulate radionuclide behaviour when contaminated components are subjected to plasma-based decommissioning processes are ... -
Study of heat transfer in a 7-element bundle cooled with the upward flow of supercritical Freon-12
Richards, Graham (2012-04-01)Experimental data on SuperCritical-Water (SCW) cooled bundles are very limited. Major problems with performing such experiments are: 1) small number of operating SCW experimental setups and 2) difficulties in testing and ...