Book contents
- Frontmatter
- Contents
- Figures and Table
- Foreword
- Foreword
- Foreword
- Nomenclature
- Preface
- Acknowledgments
- 1 Introduction
- 2 Averaging relations
- 3 Phasic conservation equations and interfacial balance equations
- 4 Local volume-averaged conservation equations and interfacial balance equations
- 5 Time averaging of local volume-averaged conservation equations or time-volume-averaged conservation equations and interfacial balance equations
- 6 Time averaging in relation to local volume averaging and time-volume averaging versus volume-time averaging
- 7 Novel porous media formulation for single phase and single phase with multicomponent applications
- 8 Discussion and concluding remarks
- Appendix A
- Appendix B
- Appendix C
- Appendix D
- References
- Index
Foreword
Published online by Cambridge University Press: 07 October 2011
- Frontmatter
- Contents
- Figures and Table
- Foreword
- Foreword
- Foreword
- Nomenclature
- Preface
- Acknowledgments
- 1 Introduction
- 2 Averaging relations
- 3 Phasic conservation equations and interfacial balance equations
- 4 Local volume-averaged conservation equations and interfacial balance equations
- 5 Time averaging of local volume-averaged conservation equations or time-volume-averaged conservation equations and interfacial balance equations
- 6 Time averaging in relation to local volume averaging and time-volume averaging versus volume-time averaging
- 7 Novel porous media formulation for single phase and single phase with multicomponent applications
- 8 Discussion and concluding remarks
- Appendix A
- Appendix B
- Appendix C
- Appendix D
- References
- Index
Summary
Dr. William (Bill) T. Sha is insightful, inventive, and the epitome of professionalism in his technical work.
I have had extensive contacts with Bill Sha, first at Argonne National Laboratory, and later at the U.S. Nuclear Regulatory Commission's Office of Nuclear Regulatory Research. In the latter capacity, I was charged, following the accident at TMI-2, with developing and executing a plan of reactor safety research focused on severe accidents. A major problem facing us was that of knowing whether, when, and how a badly damaged nuclear reactor core could be cooled by natural convection. The obvious problem was that the coolant flow paths were not readily described analytically, even if we knew precisely what they were. We turned to Bill Sha for help with this problem. The response, in a refreshingly short time, was the COMMIX code.
- Type
- Chapter
- Information
- Novel Porous Media Formulation for Multiphase Flow Conservation Equations , pp. xxiii - xxviPublisher: Cambridge University PressPrint publication year: 2011