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 outlet temperatures. The behaviour of supercritical water however, is not well understood and most of the methods available to predict the effects of the heat transfer phenomena within the pseudocritical region are based on empirical one-directional correlations which do not capture the multi-dimensional effects and do not provide accurate results in regions such as the deteriorated heat transfer regime. Computational Fluid Dynamics (CFD) is a numerical approach to model fluids in multidimensional space using the Na...
Paper presented at 2018 Canadian Society of Mechanical Engineers International Congress, 27-30 May 2...
The paper further explores the application of computational fluid dynamics (CFD) codes for the stu...
A SuperCritical Water-cooled Nuclear Reactor (SCWR) is a Generation IV concept currently being devel...
The proposed concept of Supercritical Water-cooled Reactor (SCWR) as part of the Generation IV Inter...
Experimental data on SuperCritical-Water (SCW) cooled bundles are very limited. Major problems with ...
In this study, the methodology to construct a control system based on computational fluid dynamics (...
Canada participated in the Generation IV nuclear reactors with the Supercritical Water-Cooled Reacto...
Supercritical water reactors are considered in the Generation IV as one of the promising nuclear rea...
The present work, partly made during a three month stage at the University of Aberdeen (UK), is aime...
Taking into account the expected increase in global energy demands and increasing climate change iss...
This work is part of a benchmarking excise organized by IAEA CRP in SCWR thermal-hydraulics aimed at...
Thermal-hydraulics is recognized as a key scientific issue in the development of innovative nuclear ...
A large set of experimental data, obtained in Russia, was analyzed and a new heat-transfer correlati...
Heat transfer in supercritical water reactors (SCWR) shows a complex behavior, especially when the ...
Nationwide, the demand for electricity due to population and industrial growth is on the rise. Howev...
Paper presented at 2018 Canadian Society of Mechanical Engineers International Congress, 27-30 May 2...
The paper further explores the application of computational fluid dynamics (CFD) codes for the stu...
A SuperCritical Water-cooled Nuclear Reactor (SCWR) is a Generation IV concept currently being devel...
The proposed concept of Supercritical Water-cooled Reactor (SCWR) as part of the Generation IV Inter...
Experimental data on SuperCritical-Water (SCW) cooled bundles are very limited. Major problems with ...
In this study, the methodology to construct a control system based on computational fluid dynamics (...
Canada participated in the Generation IV nuclear reactors with the Supercritical Water-Cooled Reacto...
Supercritical water reactors are considered in the Generation IV as one of the promising nuclear rea...
The present work, partly made during a three month stage at the University of Aberdeen (UK), is aime...
Taking into account the expected increase in global energy demands and increasing climate change iss...
This work is part of a benchmarking excise organized by IAEA CRP in SCWR thermal-hydraulics aimed at...
Thermal-hydraulics is recognized as a key scientific issue in the development of innovative nuclear ...
A large set of experimental data, obtained in Russia, was analyzed and a new heat-transfer correlati...
Heat transfer in supercritical water reactors (SCWR) shows a complex behavior, especially when the ...
Nationwide, the demand for electricity due to population and industrial growth is on the rise. Howev...
Paper presented at 2018 Canadian Society of Mechanical Engineers International Congress, 27-30 May 2...
The paper further explores the application of computational fluid dynamics (CFD) codes for the stu...
A SuperCritical Water-cooled Nuclear Reactor (SCWR) is a Generation IV concept currently being devel...