Browsing Faculty of Energy Systems & Nuclear Science by Author "Pioro, Igor"
Now showing items 1-19 of 19
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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 ... -
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 ... -
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 ... -
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 specifics of thermalhydraulics and neutronics of pressure-channel supercritical water-cooled reactors (SCWRs)
Peiman, Wargha (2017-08-01)A group of countries has initiated an international collaboration to develop a next generation (i.e., Generation IV) of nuclear reactors. Chosen as one of the six Generation‒IV nuclear-reactor concepts, the SCWRs are ... -
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 ...