Multiphase Flow Dynamics 5 (Record no. 101944)

000 -LEADER
fixed length control field 03877nam a22004815i 4500
001 - CONTROL NUMBER
control field 978-3-642-20601-6
003 - CONTROL NUMBER IDENTIFIER
control field DE-He213
005 - DATE AND TIME OF LATEST TRANSACTION
control field 20140220083257.0
007 - PHYSICAL DESCRIPTION FIXED FIELD--GENERAL INFORMATION
fixed length control field cr nn 008mamaa
008 - FIXED-LENGTH DATA ELEMENTS--GENERAL INFORMATION
fixed length control field 111016s2012 gw | s |||| 0|eng d
020 ## - INTERNATIONAL STANDARD BOOK NUMBER
International Standard Book Number 9783642206016
-- 978-3-642-20601-6
024 7# - OTHER STANDARD IDENTIFIER
Standard number or code 10.1007/978-3-642-20601-6
Source of number or code doi
050 #4 - LIBRARY OF CONGRESS CALL NUMBER
Classification number TA357-359
072 #7 - SUBJECT CATEGORY CODE
Subject category code TGMF
Source bicssc
072 #7 - SUBJECT CATEGORY CODE
Subject category code TGMF1
Source bicssc
072 #7 - SUBJECT CATEGORY CODE
Subject category code TEC009070
Source bisacsh
072 #7 - SUBJECT CATEGORY CODE
Subject category code SCI085000
Source bisacsh
082 04 - DEWEY DECIMAL CLASSIFICATION NUMBER
Classification number 620.1064
Edition number 23
100 1# - MAIN ENTRY--PERSONAL NAME
Personal name Kolev, Nikolay Ivanov.
Relator term author.
245 10 - TITLE STATEMENT
Title Multiphase Flow Dynamics 5
Medium [electronic resource] :
Remainder of title Nuclear Thermal Hydraulics /
Statement of responsibility, etc by Nikolay Ivanov Kolev.
264 #1 -
-- Berlin, Heidelberg :
-- Springer Berlin Heidelberg,
-- 2012.
300 ## - PHYSICAL DESCRIPTION
Extent XXXIV, 818p. 405 illus., 356 illus. in color.
Other physical details online resource.
336 ## -
-- text
-- txt
-- rdacontent
337 ## -
-- computer
-- c
-- rdamedia
338 ## -
-- online resource
-- cr
-- rdacarrier
347 ## -
-- text file
-- PDF
-- rda
505 0# - FORMATTED CONTENTS NOTE
Formatted contents note From 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 ## - SUMMARY, ETC.
Summary, etc 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.
650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Engineering.
650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Thermodynamics.
650 #0 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Hydraulic engineering.
650 14 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Engineering.
650 24 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Engineering Fluid Dynamics.
650 24 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Engineering Thermodynamics, Heat and Mass Transfer.
650 24 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Fluid- and Aerodynamics.
650 24 - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Thermodynamics.
710 2# - ADDED ENTRY--CORPORATE NAME
Corporate name or jurisdiction name as entry element SpringerLink (Online service)
773 0# - HOST ITEM ENTRY
Title Springer eBooks
776 08 - ADDITIONAL PHYSICAL FORM ENTRY
Display text Printed edition:
International Standard Book Number 9783642206009
856 40 - ELECTRONIC LOCATION AND ACCESS
Uniform Resource Identifier http://dx.doi.org/10.1007/978-3-642-20601-6
912 ## -
-- ZDB-2-ENG

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