Browsing Master Theses & Projects by Author "Pioro, Igor"
Now showing items 1-16 of 16
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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 ... -
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 ... -
Developing 1-D heat transfer correlations for supercritical water and carbon dioxide in vertical tubes
Gupta, Sahil (2014-03-01)Taking into account the expected increase in global energy demands and increasing climate change issues, there is a pressing need to develop new environmentally sustainable energy systems. Nuclear energy will play a major ... -
Development of a heat-transfer correlation for supercritical water in supercritical water-cooled reactor applications
Mokry, Sarah (2009-12-01)A large set of experimental data, obtained in Russia, was analyzed and a new heat-transfer correlation for supercritical water was developed. This experimental dataset was obtained within conditions similar to those for ... -
Development of thermodynamic cycles for sodium-cooled-fast reactors.
Dragunov, Alexey (2013-12-01)Currently, one engineering challenge is designing Generation IV (GEN-IV) Nuclear Power Plants (NPPs) with significantly higher thermal efficiencies compared to current NPPs, and to match, or at least to be close to, the ... -
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 ... -
Sensitivity analysis of fuel centerline temperatures in SuperCritical water-cooled reactors (SCWRs)
Abdalla, Ayman (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 ... -
Specifics of forced-convection heat transfer in a vertical 7-element bundle cooled with upward flow of SuperCritical Water
Clark, Scott E. (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
Sidawi, Khalil (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
Saltanov, Eugene (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 ... -
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 ... -
Study on heat transfer to supercritical water in application to SMRs
Dort-Goltz, Nikita (2021-12-01)The SuperSafe Reactor (SSR), a small modular reactor (SMR) concept with a supercritical water coolant, was subjected to a thermalhydraulic analysis and an economic analysis of its Levelized Unit of Energy Cost (LUEC). ... -
Study on linking a SuperCritical water-cooled nuclear reactor to a hydrogen production facility
Lukomski, Andrew John (2011-07-01)The SuperCritical Water-cooled nuclear Reactor (SCWR) is one of six Generation-IV nuclear-reactor concepts currently being designed. It will operate at pressures of 25 MPa and temperatures up to 625°C. These operating ... -
Study on supercritical fluids in an intermediate heat exchanger for an SCWR hydrogen cogeneration system
Jouvin, Juan Carlos (2015-12-01)SuperCritical Water-cooled Reactors (SCWRs) are one of six Generation-IV nuclear reactor concepts under development worldwide. SCWRs benefit from an increase in thermal efficiency due to the reactor coolant operating above ... -
Thermal aspects of high efficiency channel with conventional and alternative fuels in SuperCritical water-cooled reactor (SCWR) applications
Peiman, Wargha (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
Grande, Lisa Christine (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 ...