TAILIEUCHUNG - NUCLEAR REACTOR THERMAL HYDRAULICS AND OTHER APPLICATIONS

This book includes contributions from researchers around the world on numerical developments and applications to predict fluid flow and heat transfer, with an emphasis on thermal hydraulics computational fluid dynamics. Our ability to simulate larger problems with greater fidelity has vastly expanded over the past decade. The collection of material presented in this book augments the ever-increasing body of knowledge concerning the important topic of thermal hydraulics. Featured topics include coolant channel analysis, thermal hydraulic transport and mixing, as well as hydrodynamics and heat transfer processes. The contents of this book will interest researchers, scientists, engineers and graduate students | NUCLEAR REACTOR THERMAL HYDRAULICS AND OTHER APPLICATIONS Edited by Donna Post Guillen Nuclear Reactor Thermal Hydraulics and Other Applications http 45830 Edited by Donna Post Guillen Contributors Alois Hoeld Weidong Huang Osama Abd-Elkawi Ten-See Wang Sergey Karabasov Alex Obabko Paul Fischer Tim Tautges Vasily Goloviznin Mihail Zaitsev Vladimir Chudanov Valerii Pervichko Anna Aksenova Hernan Tinoco Published by InTech Janeza Trdine 9 51000 Rijeka Croatia Copyright 2013 InTech All chapters are Open Access distributed under the Creative Commons Attribution license which allows users to download copy and build upon published articles even for commercial purposes as long as the author and publisher are properly credited which ensures maximum dissemination and a wider impact of our publications. After this work has been published by InTech authors have the right to republish it in whole or part in any publication of which they are the author and to make other personal use of the work. Any republication referencing or personal use of the work must explicitly identify the original source. Notice Statements and opinions expressed in the chapters are these of the individual contributors and not necessarily those of the editors or publisher. No responsibility is accepted for the accuracy of information contained in the published chapters. The publisher assumes no responsibility for any damage or injury to persons or property arising out of the use of any materials instructions methods or ideas contained in the book. Publishing Process Manager Iva Simcic Technical Editor InTech DTP team Cover InTech Design team First published February 2013 Printed in Croatia A free online edition of this book is available at Additional hard copies can be obtained from orders@ Nuclear Reactor Thermal Hydraulics and Other Applications Edited by Donna Post Guillen p. cm. ISBN 978-953-51-0987-7 INTECH open science I open minds free .

• Hoá dầu
• Nuclear Reactor
• Thermal Hydraulics
• Light Water
• Momentum Source
• Tank Reactors
• Nuclear engineering and technology
• Nuclear reactor vessel water level prediction during severe accidents
• Deep neural networks
• Nuclear power plants
• Maintain nuclear reactor integrity
• Comparison of applicability of current transition temperature shift models
• SA533B 1 reactor pressure vessel steel of Korean nuclear reactors
• Korean nuclear reactors
• Aged reactor pressure vessels
• Wavelet operator for multiscale modeling of a nuclear reactor
• Multiscale modeling of a nuclear reactor
• Multivariable system onto projection space
• The single scale approach
• Digital reactitvity meter
• Reactor power
• Reactor period
• Dalat nuclear research reactor
• Inverse kinetics equations
• experimental investigation
• Reactor Technology
• Doppler Broadening
• Function Calculation
• Nuclear Fuels
• Thermal Analysis
• Feed water pump
• Main circulation pump
• Safety system
• Nuclear reactor WWER 1000 simulator developed
• Modal characteristic analysis
• The apr1400 nuclear reactor internals for seismic analysis
• The apr1400 nuclear reactor internals
• Scaled down Model
• Fluid–structure Interaction
• Finite Element Method
• Results of operation
• Utilization of the Dalat nuclear research reactor
• Nuclear research reactor
• Yearly operation time of the DNRR
• Natural convection
• Nordic research and development cooperation
• Strengthen nuclear reactor safety after the Fukushima accident
• The Fukushima accident
• Nordic Nuclear Safety Research
• The concept of the innovative power reactor
• The innovative power reactor
• Passive Safety System
• Nuclear power plant
• Monte carlo simulation
• Serpent 2 monte carlo code
• Different reactor conditions
• Generating multi group neutron cross sections
• Nuclear energy
• Research reactor
• Neutron multiplicity
• Monte carlo simulations
• Associated nuclear data
• Reactor Critical Facility
• Homogenized cross section
• 3D kinetics calculations
• Plate type model
• Thermal hydraulics feedbacks
• Multi group neutron
• 3D reactor kinetics code
• Computational design of subcritical reactor assembly with TRIGA fuel
• Characterization of a subcritical reactor assembly with TRIGA fuel
• Subcritical reactor assembly
• Different fuel configuration
• Calculate physical parameters
• Neutronics analysis of TRIGA Mark II research reactor
• TRIGA Mark II research reactor
• Isotope production General Atomics
• Reactor In core Analysis
• Winfrith Improved Multi group
• Semiempirical model for wet scrubbing of bubble rising
• Liquid pool of sodium cooled fast reactor
• Sodium cooled fast reactor
• Sodium cooled Fast Reactor Safety
• Reactivity balance for a soluble boron free small modular reactor
• Soluble boron free small modular reactor
• The SMR model
• Small Modular Reactor
• Soluble Boron Free
• Measurement of vibration for APR 1400 reactor internals
• Measurement of stress for APR 1400 reactor internals
• APR 1400 reactor internals
• Comprehensive Vibration Assessment
• Structural assessment of reactor pressure vessel
• Multi layered corium formation conditions
• External reactor vessel cooling
• Representative reactor pressure vessel
• Reactor shielding for nuclear engineers
• Nuclear engineers
• Sources of radiation
• Interactions of radiation with matter
• Radition transrort
• Monte carlo methods
• Radiation transport
• Experimental validation of a nuclear forensics methodology
• Source reactor type discrimination of chemically separated plutonium
• Chemically separated plutonium
• Fuel burnup simulations
• Identification of nonregular indication according
• Change of grain size surface geometry
• Nuclear power plant (NPP) reactor vessel
• Upper head alloy 690 penetration
• Labelled KIT
• Nuclear medicine
• Production of radioisotopes
• Utilization of domestic radioisotopes
• Event event coincidence
• Thermal neutron beam
• Nuclear structure
• Gamma two step cascade method