Author: Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 1284
Book Description
Energy Research Abstracts
Author: Boiling
Author: Yasuo KoizumiPublisher: Elsevier
ISBN: 0081011172
Category : Technology & Engineering
Languages : en
Pages : 849
Book Description
Boiling: Research and Advances presents the latest developments and improvements in the technologies, instrumentation, and equipment surrounding boiling. Presented by the Japan Society of Mechanical Engineers, the book takes a holistic approach, first providing principles, and then numerous practical applications that consider size scales. Through six chapters, the book covers contributed sections from knowledgeable specialists on various topics, ranging from outlining boiling phenomena and heat transfer characteristics, to the numerical simulation of liquid-gas two phase flow. It summarizes, in a single volume, the state-of-the-art in boiling heat transfer and provides a valuable resource for thermal engineers and practitioners working in the thermal sciences and thermal engineering. - Explores the most recent advancements in boiling research and technology from the last twenty years - Provides section content written by contributing experts in their respective research areas - Shares research being conducted and advancements being made on boiling and heat transfer in Japan, one of the major research hubs in this field
Multiphase Flow Dynamics 5
Author: Nikolay Ivanov KolevPublisher: Springer Science & Business Media
ISBN: 3642206018
Category : Technology & Engineering
Languages : en
Pages : 839
Book Description
The present Volume 5 of the successful book package "Multiphase Flow Dynamics" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materials due to nuclear reactions into its environment. It step by step introduces into the heat release inside the fuel, temperature fields in the fuels, the "simple" boiling flow in a pipe described using ideas of different complexity like equilibrium, non equilibrium, homogeneity, non homogeneity. Then the "simple" three-fluid boiling flow in a pipe is described by gradually involving the mechanisms like entrainment and deposition, dynamic fragmentation, collisions, coalescence, turbulence. All heat transfer mechanisms are introduced gradually discussing their uncertainty. Different techniques are introduced like boundary layer treatments or integral methods. Comparisons with experimental data at each step demonstrate the success of the different ideas and models. After an introduction of the design of the reactor pressure vessels for pressurized and boiling water reactors the accuracy of the modern methods is demonstrated using large number of experimental data sets for steady and transient flows in heated bundles. Starting with single pipe boiling going through boiling in the rod bundles the analysis of complete vessel including the reactor is finally demonstrated. Then a powerful method for nonlinear stability analysis of flow boiling and condensation is introduced. Models are presented and their accuracies are investigated for describing critical multiphase flow at different level of complexity. Basics of designing of steam generators, moisture separators and emergency condensers are presented. Methods for analyzing a complex pipe network flows with components like pumps, valves etc. are also presented. Methods for analysis of important aspects of the severe accidents like melt-water interactions, external cooling and cooling of layers of molten nuclear reactor material are presented. Valuable sets of thermo-physical and transport properties for severe accident analysis are presented for the following materials: uranium dioxide, zirconium dioxide, stainless steel, zirconium, aluminum, aluminum oxide, silicon dioxide, iron oxide, molybdenum, boron oxide, reactor corium, sodium, lead, bismuth, and lead-bismuth eutectic alloy. The emphasis is on the complete and consistent thermo dynamical sets of analytical approximations appropriate for computational analysis. Therefore the book presents a complete coverage of the modern Nuclear Thermal Hydrodynamics. This present second edition includes various updates, extensions, improvements and corrections. This present second edition includes various updates, extensions, improvements and corrections.
Journal of Nuclear Science and Technology
Author: Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 592
Book Description
Includes English language abstracts from Japanese articles in Nihon Genshiryoku Gakkai Shi (Journal of the Atomic Energy Society of Japan).
Government reports annual index
Author: Nuclear Science Abstracts
Author: INIS Atomindex
Author: Annular Two-Phase Flow
Author: Geoffrey HewittPublisher: Elsevier
ISBN: 1483285235
Category : Technology & Engineering
Languages : en
Pages : 327
Book Description
Annular Two-Phase Flow presents the wide range of industrial applications of annular two-phase flow regimes. This book discusses the fluid dynamics and heat transfer aspects of the flow pattern. Organized into 12 chapters, this book begins with an overview of the classification of the various types of interface distribution observed in practice. This text then examines the various regimes of two-phase flow with emphasis on the regions of occurrence of the annular flow regime. Other chapters consider the single momentum and energy balances, which illustrate the differences and analogies between single- and two-phase flows. This book discusses as well the simple modes for annular flow with consideration to the calculation of the profile of shear stress in the liquid film. The final chapter deals with the techniques that are developed for the measurement of flow pattern, entrainment, and film thickness. This book is a valuable resource for chemical engineers.
Handbook on Thermal Hydraulics in Water-Cooled Nuclear Reactors
Author: Francesco D'AuriaPublisher: Elsevier
ISBN: 0323856071
Category : Business & Economics
Languages : en
Pages : 932
Book Description
Handbook on Thermal Hydraulics of Water-Cooled Nuclear Reactors, Volume 1, Foundations and Principles includes all new chapters which delve deeper into the topic, adding context and practical examples to help readers apply learnings to their own setting. Topics covered include experimental thermal-hydraulics and instrumentation, numerics, scaling and containment in thermal-hydraulics, as well as a title dedicated to good practices in verification and validation. This book will be a valuable reference for graduate and undergraduate students of nuclear or thermal engineering, as well as researchers in nuclear thermal-hydraulics and reactor technology, engineers working in simulation and modeling of nuclear reactors, and more. In addition, nuclear operators, code developers and safety engineers will also benefit from the practical guidance provided. - Presents a comprehensive analysis on the connection between nuclear power and thermal hydraulics - Includes end-of-chapter questions, quizzes and exercises to confirm understanding and provides solutions in an appendix - Covers applicable nuclear reactor safety considerations and design technology throughout
Two-phase Flow and Heat Transfer in the Power and Process Industries
Author: A. E. BerglesPublisher: Hemisphere Pub
ISBN:
Category : Chemical plants
Languages : en
Pages : 730
Book Description