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Multiphase Flow Dynamics 5: Nuclear Thermal Hydraulics

✍ Scribed by Nikolay Ivanov Kolev (auth.)


Publisher
Springer Berlin Heidelberg
Year
2012
Tongue
English
Leaves
838
Edition
2nd ed.
Category
Library

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✦ Synopsis


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. Therefore the book presents a complete coverage of the modern Nuclear Thermal Hydrodynamics.

This present second edition includes various updates, extensions, improvements and corrections.

✦ Table of Contents


Front Matter....Pages -
Heat release in the reactor core....Pages 1-14
Temperature inside the fuel elements....Pages 15-43
The β€œsimple” steady boiling flow in a pipe....Pages 45-86
The β€œsimple” steady three-fluid boiling flow in a pipe....Pages 87-116
Core thermal hydraulics....Pages 117-194
Flow boiling and condensation stability analysis....Pages 195-213
Critical multiphase flow....Pages 215-300
Steam generators....Pages 301-354
Moisture separation....Pages 355-432
Pipe networks....Pages 433-459
Some auxiliary systems....Pages 461-477
Emergency condensers....Pages 479-496
Core degradation....Pages 497-501
Melt-coolant interaction....Pages 503-520
Coolability of layers of molten reactor material....Pages 521-564
External cooling of reactor vessels during severe accident....Pages 565-616
Thermo-physical properties for severe accident analysis....Pages 617-807
Back Matter....Pages -

✦ Subjects


Engineering Fluid Dynamics;Engineering Thermodynamics, Heat and Mass Transfer;Fluid- and Aerodynamics;Thermodynamics


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