TAILIEUCHUNG - NUCLEAR POWER PLANTS

This book covers various topics, from thermal-hydraulic analysis to the safety analysis of nuclear power plant. It does not focus only on current power plant issues. Instead, it aims to address the challenging ideas that can be implemented in and used for the development of future nuclear power plants. This book will take the readers into the world of innovative research and development of future plants. Find your interests inside this book!Steam Generator | NUCLEAR POWER PLANTS Edited by Soon Heung Chang Nuclear Power Plants Edited by Soon Heung Chang Published by InTech Janeza Trdine 9 51000 Rijeka Croatia Copyright 2012 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. As for readers this license allows users to download copy and build upon published chapters 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. 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 Sandra Bakic Technical Editor Teodora Smiljanic Cover Designer InTech Design Team First published March 2012 Printed in Croatia A free online edition of this book is available at Additional hard copies can be obtained from orders@ Nuclear Power Plants Edited by Soon Heung Chang p. cm. ISBN 978-953-51-0408-7 INTECH open science I open minds free online editions of InTech Books and Journals can be found at .

• Cơ khí - Chế tạo máy
• Steam Generator
• RBMK Reactors
• Environmental Considerations
• Nuclear Power
• SBLOCA Scenario
• Nuclear Waste Samples
• The excitation system of synchronous generator
• Aynchronous generator in steam power plant unit 3
• Aynchronous generator in steam power plant unit 4
• Steam power plant
• PJB uP gresik
• Nuclear engineering and technology
• Computer code for thermalehydraulic design
• Analysis of helically coiled tube once through steam generator
• Tube once through steam generator
• Once through Steam Generator
• Key findings from the artist project on aerosol retention
• Dry steam generator
• Fission Product Retention
• Steam Generator Tube Rupture
• The Aerosol Trapping In Steam GeneraTor
• Prognostics for integrity of steam generator tubes
• The general path model
• Nuclear power plants
• ROSA LSTF test and RELAP5 code analyses
• PWR steam generator tube rupture accident with recovery actions
• PWR steam generator tube rupture accident
• The operation of highpressure injection
• Performance analysis of synchronous generator
• PT POMI paiton unit 7 probolinggo
• Synchronous generator performance analysis
• Steam power plant PT POMI Paiton unit 7 Probolinggo
• Steam generator tube integrity analysis
• Heat sinks accident for wolsong NPP unit 1
• DCRV discharge capacity
• Steam Generator Tube
• Degasser Condenser Relief Valve
• Analysis of steam power generators in fulfilling electricity needs
• Steam power generators in fulfilling electricity needs
• Steam power generator
• Electric power in PT Madubaru Yogyakarta
• Generator Tubing
• Temperature Alkaline
• Leaded Solution
• Power Engineering
• Degraded Steam
• Generator Tubes
• Numerical validation of burst pressure estimation equations
• Steam generator tubes with multiple axial surface cracks
• Multiple axial surface cracks
• Giving sufficient confidence
• Low frequency modes in the fluid structure interaction
• U tube model for the steam generator in a PWR
• Fluid structure interaction
• Flow induced vibration
• Computational fluid dynamics
• The structure optimization
• The operation scheme design
• Double tube once through steam generator
• Particle Swarm Optimization
• Low power level
• Helical tube of steam generator
• Comparative study of corrosion resistance
• Nickel base alloys as the primary materials
• The harsh environment of reactor
• Chemical composition of passive film
• Containment bypass
• Extended SBO sequence
• SCDAP/RELAP5 code
• Evaluation of the potential
• The mesynthesis of water level control in steam generators
• Analysis of water level control in steam generators
• Water level control in steam generators
• The U tube system generator
• Power plant engineering
• Fundamental of power plant
• Non conventional energy resources
• Power plant economics
• Variable load problem
• RCD success criteria estimation
• Allowable coping time
• Small break LOCA
• Rapid cool down
• Safety injection systems
• Application of particle filtering for prognostics
• Measurement uncertainty in nuclear power plants
• Model based method
• PWSCC growth assessment model considering stress triaxiality factor
• Primary alloy 600 components
• The macroscopic phenomenological damage mechanics approach
• SCC Growth Simulation
• Nuclear energy
• Secondary water chemistry
• System component integrity
• Stress corrosion cracking
• Flow accelerated corrosion
• Nuclear engineering and design
• Severe accidents
• Two phase flow
• Fission products
• Steam generator secondary side
• Measurement point
• Multivariate analysis of critical parameters influencing the reliability
• Thermal hydraulic passive safety system
• Critical parameters influencing the reliability
• Two multivariate analysis methods
• The identified key CPs
• Water cooled steam generator
• Activated cooling water
• Fusion reactor
• Cooling pipes