AbstractThis paper evaluates three-dimensional turbulent flow and convective heat transfer through mixing split vane in a single-phase and steady-state sub-channel of AP1000 nuclear reactor core by using general computational fluid dynamics code, Fluent6.3.26.Realizable K-ɛ model is used as a turbulent closure model, and the sub-channel is analyzed by numerical simulation. The results show that the mixing split vanes, which affect strongly the heat transfer in the sub-channel, are lateral flow, swirl and turbulent intensity between the sub-channels, and give reasonable agreements with experimental equations and AP1000 thermal hydraulic design
The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged ...
In order to ramp up the conversion ratios and burn-up of nuclear reactors, it is inevitable to go to...
AbstractThe details of flow and conjugate heat transfer in Advanced Gas-cooled Reactors are currentl...
AbstractThis paper evaluates three-dimensional turbulent flow and convective heat transfer through m...
CFD investigations of the flow in a 5x5 rod bundle with mixing vane spacer grid were performed with ...
Enhancing heat transfer between fuel rods and coolant is one of the main goals of nuclear engineerin...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisti...
학위논문 (석사)-- 서울대학교 대학원 : 공과대학 에너지시스템공학부, 2018. 8. 조형규.As the recent computing environment increases, ...
This dissertation focuses on computational design of a PWR-type small modular nuclear reactor (SMR),...
In this research, direct numerical simulations are performed for the evolution of a mixing layer in ...
The development of new practices in nuclear research reactor safety aspects and optimization of rece...
Paper presented at 2018 Canadian Society of Mechanical Engineers International Congress, 27-30 May 2...
This paper presents the results of an analysis of lateral coolant flow between adjacent fuel assembl...
The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged ...
In order to ramp up the conversion ratios and burn-up of nuclear reactors, it is inevitable to go to...
AbstractThe details of flow and conjugate heat transfer in Advanced Gas-cooled Reactors are currentl...
AbstractThis paper evaluates three-dimensional turbulent flow and convective heat transfer through m...
CFD investigations of the flow in a 5x5 rod bundle with mixing vane spacer grid were performed with ...
Enhancing heat transfer between fuel rods and coolant is one of the main goals of nuclear engineerin...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
This paper presents a novel Computational Fluid Dynamics (CFD)-based sub-channel framework for nucle...
This paper presents the results of an analysis of flow distribution in VVER-1000 mixed core consisti...
학위논문 (석사)-- 서울대학교 대학원 : 공과대학 에너지시스템공학부, 2018. 8. 조형규.As the recent computing environment increases, ...
This dissertation focuses on computational design of a PWR-type small modular nuclear reactor (SMR),...
In this research, direct numerical simulations are performed for the evolution of a mixing layer in ...
The development of new practices in nuclear research reactor safety aspects and optimization of rece...
Paper presented at 2018 Canadian Society of Mechanical Engineers International Congress, 27-30 May 2...
This paper presents the results of an analysis of lateral coolant flow between adjacent fuel assembl...
The fuel assemblies of the Pressurized Water Reactors (PWR) are constituted of rod bundles arranged ...
In order to ramp up the conversion ratios and burn-up of nuclear reactors, it is inevitable to go to...
AbstractThe details of flow and conjugate heat transfer in Advanced Gas-cooled Reactors are currentl...