| Description |
1 online resource (xxxii, 745 pages) : illustrations |
| Contents |
Heat release in the reactor core -- Temperature inside the fuel elements -- The "simple" steady boiling flow in a pipe -- The "simple" steady three-fluid boiling flow in a pipe -- Core thermal hydraulic -- Flow boiling and condensation stability analysis -- Critical multiphase flow -- Steam generators -- Moisture separation -- Pipe networks -- Some auxiliary systems -- Emergency condensers -- Core degradation -- Melt-water interaction -- Coolability of layers of molten reactor material -- External cooling of reactor vessels during severe accident -- Thermo-physical properties for severe accident analysis |
| Summary |
Annotation Volume 4 of the successful book package "Multiphase Flow" 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 a rod bundles the analysis of complete vessel including the reactor is finally demonstrated. Then powerful method for non-linear 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 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 |
| Bibliography |
Includes bibliographical references and index |
| Notes |
Print version record |
| In |
Springer eBooks |
| Subject |
Nuclear reactors -- Fluid dynamics.
|
|
Heat -- Transmission.
|
|
Multiphase flow -- Mathematical models
|
|
Nuclear engineering.
|
|
Engineering.
|
|
Nuclear energy.
|
|
Thermodynamics.
|
|
Engineering
|
|
Nuclear Energy
|
|
Thermodynamics
|
|
heat transmission.
|
|
engineering.
|
|
nuclear power.
|
|
thermodynamics.
|
|
TECHNOLOGY & ENGINEERING -- Material Science.
|
|
Nuclear reactors -- Fluid dynamics.
|
|
Heat -- Transmission.
|
|
Multiphase flow -- Mathematical models.
|
|
Nuclear engineering.
|
|
Ingénierie.
|
|
Heat -- Transmission
|
|
Multiphase flow -- Mathematical models
|
|
Nuclear engineering
|
|
Nuclear reactors -- Fluid dynamics
|
| Form |
Electronic book
|
| ISBN |
9783540929185 |
|
3540929185 |
|
9783540929178 |
|
3540929177 |
|
