000			04068nam a22003255i 4500
001			103203
003			DE-He213
005			20230102113119.0
007			cr nn 008mamaa
008			150402s2015 gw | s |||| 0|eng d
020			_a9783319151564
024	7		_a10.1007/978-3-319-15156-4 _2doi
050		4	_aTA357.5.M84 _bK654 2015 EB
040			_aES-MaUEC _bspa
100	1		_aKolev, Nikolay Ivanov _eautor. _4aut _4http://id.loc.gov/vocabulary/relators/aut _0http://id.loc.gov/authorities/names/n85256841 _1http://viaf.org/viaf/16216394/
245	1	0	_aMultiphase Flow Dynamics 5 _bNuclear Thermal Hydraulics _cby Nikolay Ivanov Kolev.
250			_a3rd edition
264		1	_aCham _bSpringer International Publishing _c2015
300			_a1 recurso en línea (XL, 886 páginas 494 ilustraciones, 438 ilustraciones a color.)
505	0		_aHeat 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 Hydraulics -- Flow Boiling and Condensation Stability Analysis -- Critical Multiphase Flow -- Steam Generators -- Moisture Separation -- Pipe Networks -- Some Auxiliary Systems -- Emergency Condensers, Reheaters, Moisture Separators and Reheaters -- Core Degradation -- Melt-Coolant Interaction -- Coolability of Layers of Molten Reactor Material -- External Cooling of Reactor Vessels During Severe Accident -- Thermo-Physical Properties for Severe Accident Analysis -- Lead, Bismuth and Lead-Bismuth Eutectic Alloy -- Containment Thermal-Hydraulics.
520	3		_aThis 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 third edition includes various updates, extensions, improvements and corrections.
650		7	_aMecánica de fluidos _2embne _9138336
650		7	_aIngeniería hidráulica _2embne _9138022
776	0	8	_iEdición impresa: _z9783319151571
776	0	8	_iEdición impresa: _z9783319151557
776	0	8	_iEdición impresa: _z9783319374499
856	4	0	_uhttps://go.openathens.net/redirector/universidadeuropea.es?url=https://doi.org/10.1007/978-3-319-15156-4 _zAcceso a este recurso digital (usuarios Universidad Europea de Madrid)
490	0		_aEngineering (Springer-11647)
998			_b03/2019 _dz _ef _feng _ggw _h0
999			_c103203 _d103203 _x1