Author: Chung-Nin Channy Wong
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages : 876
Book Description
Wire-wrapped Rod Bundle Heat Transfer Analysis for Liquid Metal Fast Breeder Reactor
Author: Chung-Nin Channy Wong
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages : 876
Book Description
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages : 876
Book Description
Thermal Analysis of Liquid-metal Fast Breeder Reactors
Author: Yu S. Tang
Publisher: American Nuclear Society
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 432
Book Description
This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.
Publisher: American Nuclear Society
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 432
Book Description
This monograph is written as a treatise on the state-of-the-art of liquid-metal fast breeder reactor thermal and hydraulic design and analysis.
Heat Transfer Analysis of Core Models of a Liquid Metal Fast Breeder Reactor
Author: Michael Eugene Balmert
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 152
Book Description
Publisher:
ISBN:
Category : Breeder reactors
Languages : en
Pages : 152
Book Description
Heat Transfer in Rod Bundles
Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 184
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 184
Book Description
Simplified Approach for Predicting Temperature Distribution in Wire Wrapped Assemblies
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A novel semi-empirical method has been developed for predicting temperature distributions in wire wrapped rod bundles of a Liquid Metal Fast Breeder Reactor. The lumped eddy difiusivity model developed greatly simplifies the prediction and computational procedure yet takes into account the important, identifiable, modes of energy re-distribution within the rod bundle. The accuracy of predictions was found to be as good as the more complicated subchannel analysis codes. Two dimensionless groups necessary for predicting energy redistribution within the bundle are identifiable and their dependence on various geometrical parameters of the rod bundle is quantitatively established with the help of existing data. 17 references. (auth).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
A novel semi-empirical method has been developed for predicting temperature distributions in wire wrapped rod bundles of a Liquid Metal Fast Breeder Reactor. The lumped eddy difiusivity model developed greatly simplifies the prediction and computational procedure yet takes into account the important, identifiable, modes of energy re-distribution within the rod bundle. The accuracy of predictions was found to be as good as the more complicated subchannel analysis codes. Two dimensionless groups necessary for predicting energy redistribution within the bundle are identifiable and their dependence on various geometrical parameters of the rod bundle is quantitatively established with the help of existing data. 17 references. (auth).
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages :
Book Description
Nuclear Science Abstracts
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 912
Book Description
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 912
Book Description
TID.
Author:
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 720
Book Description
Publisher:
ISBN:
Category : Energy development
Languages : en
Pages : 720
Book Description
CFD Applications in Nuclear Engineering
Author: Wenxi Tian
Publisher: Frontiers Media SA
ISBN: 2832533264
Category : Technology & Engineering
Languages : en
Pages : 219
Book Description
High fidelity nuclear reactor thermal hydraulic simulations are a hot research topic in the development of nuclear engineering technology. The three-dimensional Computational Fluid Dynamics (CFD) and Computational Multi-phase Fluid Dynamics (CMFD) methods have attracted significant attention in predicting single-phase and multi-phase flows under steady-state or transient scenarios in the field of nuclear reactor engineering. Compared with three-dimensional thermal hydraulic methods, the traditional one-dimensional system analysis method contains inherent defects in the required accuracy and spatial resolution for a number of important nuclear reactor thermal-hydraulic phenomena. At present the CFD method has been widely adopted in the nuclear industry, across both light water reactors and liquid metal cooled fast reactors, providing an effective solution for complex issues of thermal hydraulic analysis. However, the CFD method employs empirical models for turbulence simulation, heat transfer, multi-phase interaction and chemical reactions. Such models must be validated before they can be used with confidence in nuclear reactor applications. In addition, user practice guidelines play a critical role in achieving reliable results from CFD simulations.
Publisher: Frontiers Media SA
ISBN: 2832533264
Category : Technology & Engineering
Languages : en
Pages : 219
Book Description
High fidelity nuclear reactor thermal hydraulic simulations are a hot research topic in the development of nuclear engineering technology. The three-dimensional Computational Fluid Dynamics (CFD) and Computational Multi-phase Fluid Dynamics (CMFD) methods have attracted significant attention in predicting single-phase and multi-phase flows under steady-state or transient scenarios in the field of nuclear reactor engineering. Compared with three-dimensional thermal hydraulic methods, the traditional one-dimensional system analysis method contains inherent defects in the required accuracy and spatial resolution for a number of important nuclear reactor thermal-hydraulic phenomena. At present the CFD method has been widely adopted in the nuclear industry, across both light water reactors and liquid metal cooled fast reactors, providing an effective solution for complex issues of thermal hydraulic analysis. However, the CFD method employs empirical models for turbulence simulation, heat transfer, multi-phase interaction and chemical reactions. Such models must be validated before they can be used with confidence in nuclear reactor applications. In addition, user practice guidelines play a critical role in achieving reliable results from CFD simulations.
Energy Research Abstracts
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 564
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 564
Book Description