000 03877nam a22004815i 4500
001 978-3-642-20601-6
003 DE-He213
005 20140220083257.0
007 cr nn 008mamaa
008 111016s2012 gw | s |||| 0|eng d
020 _a9783642206016
_9978-3-642-20601-6
024 7 _a10.1007/978-3-642-20601-6
_2doi
050 4 _aTA357-359
072 7 _aTGMF
_2bicssc
072 7 _aTGMF1
_2bicssc
072 7 _aTEC009070
_2bisacsh
072 7 _aSCI085000
_2bisacsh
082 0 4 _a620.1064
_223
100 1 _aKolev, Nikolay Ivanov.
_eauthor.
245 1 0 _aMultiphase Flow Dynamics 5
_h[electronic resource] :
_bNuclear Thermal Hydraulics /
_cby Nikolay Ivanov Kolev.
264 1 _aBerlin, Heidelberg :
_bSpringer Berlin Heidelberg,
_c2012.
300 _aXXXIV, 818p. 405 illus., 356 illus. in color.
_bonline resource.
336 _atext
_btxt
_2rdacontent
337 _acomputer
_bc
_2rdamedia
338 _aonline resource
_bcr
_2rdacarrier
347 _atext file
_bPDF
_2rda
505 0 _aFrom the content: 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.
520 _aThe 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.
650 0 _aEngineering.
650 0 _aThermodynamics.
650 0 _aHydraulic engineering.
650 1 4 _aEngineering.
650 2 4 _aEngineering Fluid Dynamics.
650 2 4 _aEngineering Thermodynamics, Heat and Mass Transfer.
650 2 4 _aFluid- and Aerodynamics.
650 2 4 _aThermodynamics.
710 2 _aSpringerLink (Online service)
773 0 _tSpringer eBooks
776 0 8 _iPrinted edition:
_z9783642206009
856 4 0 _uhttp://dx.doi.org/10.1007/978-3-642-20601-6
912 _aZDB-2-ENG
999 _c101944
_d101944