A Derivation of the Nonlocal Volume-Averaged Equations for Two-Phase Flow Transport
Author
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2012, Issue 2012 (31 Dec. 2012), pp.1-8, 8 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2012-09-16
Country of Publication
Egypt
No. of Pages
8
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
In this paper a detailed derivation of the general transport equations for two-phase systems using a method based on nonlocal volume averaging is presented.
The local volume averaging equations are commonly applied in nuclear reactor system for optimal design and safe operation.
Unfortunately, these equations are limited to length-scale restriction and according with the theory of the averaging volume method, these fail in transition of the flow patterns and boundaries between two-phase flow and solid, which produce rapid changes in the physical properties and void fraction.
The non-local volume averaging equations derived in this work contain new terms related with non-local transport effects due to accumulation, convection diffusion and transport properties for two-phase flow; for instance, they can be applied in the boundary between a two-phase flow and a solid phase, or in the boundary of the transition region of two-phase flows where the local volume averaging equations fail.
American Psychological Association (APA)
Espinosa-Paredes, Gilberto. 2012. A Derivation of the Nonlocal Volume-Averaged Equations for Two-Phase Flow Transport. Science and Technology of Nuclear Installations،Vol. 2012, no. 2012, pp.1-8.
https://search.emarefa.net/detail/BIM-505768
Modern Language Association (MLA)
Espinosa-Paredes, Gilberto. A Derivation of the Nonlocal Volume-Averaged Equations for Two-Phase Flow Transport. Science and Technology of Nuclear Installations No. 2012 (2012), pp.1-8.
https://search.emarefa.net/detail/BIM-505768
American Medical Association (AMA)
Espinosa-Paredes, Gilberto. A Derivation of the Nonlocal Volume-Averaged Equations for Two-Phase Flow Transport. Science and Technology of Nuclear Installations. 2012. Vol. 2012, no. 2012, pp.1-8.
https://search.emarefa.net/detail/BIM-505768
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-505768