TAILIEUCHUNG - NUCLEAR REACTORS

This book presents a comprehensive review of studies in nuclear reactors technology from authors across the globe. Topics discussed in this compilation include: thermal hydraulic investigation of TRIGA type research reactor, materials testing reactor and high temperature gas-cooled reactor; the use of radiogenic lead recovered from ores as a coolant for fast reactors; decay heat in reactors and spent-fuel pools; present status of two-phase flow studies in reactor components; thermal aspects of conventional and alternative fuels in supercritical water?cooled reactor; two-phase flow coolant behavior in boiling water reactors under earthquake condition; simulation of nuclear reactors core; fuel life control in. | NUCLEAR REACTORS Edited by Amir Zacarias Mesquita Nuclear Reactors Edited by Amir Zacarias Mesquita 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 Iva Simcic Technical Editor Teodora Smiljanic Cover Designer InTech Design Team First published February 2012 Printed in Croatia A free online edition of this book is available at Additional hard copies can be obtained from orders@ Nuclear Reactors Edited by Amir Zacarias Mesquita p. cm. ISBN 978-953-51-0018-8 INTECH open science I open minds free online editions of InTech Books and Journals can be found at .

• Cơ khí - Chế tạo máy
• Flow Instability
• Material Testing Reactors
• IPR R1 TRIGA
• Nuclear Reactor
• Decay Heat
• Nuclear Data
• Nuclear engineering and technology
• Integral nuclear data validation
• Experimental spent nuclear fuel compositions
• Economic Co operation and Development
• Nuclear Energy Agency
• Nuclear Criticality Safety
• Expanded spent fuel isotopic compositions
• Uncertainty quantification methodologies
• Evaluating nuclear data
• Contradictory experimental data
• Nuclear data evaluation
• Nuclear data types
• European nuclear data
• Nuclear data research
• Nuclear data improvement
• JRC action EUFRAT
• Nuclear energy industry
• Impact of the nuclear data
• Neutron emission and spectra
• Spent nuclear fuels
• Swiss power plants
• LWR spent nuclear fuels
• Big Data Analysis
• Public Acceptance of Nuclear Power in Korea
• Social Networking Services
• Common big data analyses
• The public toward nuclear power
• Evaluated nuclear data file b viii
• 0b4 cross section library
• Critical experimental benchmark
• The monte carlo code MCNP(X) and NJOY2016
• Evaluated nuclear data Fil
• The Monte Carlo N Particle
• Uncertainty evaluation process
• Data utilization in V&V
• Nuclear parameter covariance data
• Challenging cross cutting scientific issues
• Nuclear data users’ requirements
• Statistical analysis on the fluence factor
• Surveillance test data of Korean nuclear power plants
• Korean nuclear power plants
• Mixed effect model
• The Conservation Laws
• The Data of Nuclear Reactonsn
• The Nuclear Model
• Nuclear Level Widths
• Nuclear Fission
• Comparisons of calculated
• Used nuclear fuels
• Quality of nuclear data
• JEFF 3 1 1 library
• Integral data assimilation
• Improving nuclear data
• 137Cs/238U concentration ratio
• Cumulated thermal fission yield
• Post irradiation experiments
• Nuclear data adjustment
• Bayesian set of equation
• Random nuclear data
• Nuclear data correlation
• Bigten criticality benchmark
• Bayesian Monte Carlo method
• Nuclear core management
• Data Assimilation techniques
• Best Unbiased Linear Estimation
• Nuclear core activity reconstruction
• Heterogeneous instruments with data assimilation
• Neutron Data Standards
• Validating nuclear data
• Physical Uncertainty Bounds
• PUBs enclose ENDF/B VIII 0
• Governing physics sub processes
• Public perceptions of nuclear energy in South Korea
• Evidence from Big Data
• Linguistic Inquiry and Word
• Wellknown social media
• Development of field programmable gate arrayebased encryption module
• Mitigate man in the middle attack
• Nuclear power plant data communication network
• Field programmable gate array
• Neutron activation analysis
• k0 standardized method
• k0 based neutron activation analysis
• Nuclear power
• Nuclear energy
• Nuclear power plant outage
• Computer vision
• Automatically detecting abnormal human
• Field operation and preparation
• Data driven simulation
• NEA Data Bank
• JEFF 3 3T4 covariances
• Nuclear data covariances
• JENDL 4 0 updated files
• JEFF 3 2 library
• Nuclear data uncertainty propagation
• Typical pwr fuel assembly with burnup
• The OECD Nuclear Energy Agency UAM
• The Monte Carlo transport
• Burnup code SERPENT
• Expert working group
• 137 Cs dispersion
• Fukushima daiichi nuclear power plant
• FLEXPART–WRF model
• ERA5 reanalysis data
• Refined Resonating
• Standard Neutron
• Cross Sections
• Reaction Calculations
• Heat Calculations
• cardiovascular nuclear
• potential substitute
• Nuclear Cardiology
• data documenting
• RISK STRATIFICATION
• PATIENT MANAGEMENT
• Nuclear science and technology
• The journal of Nuclear science and technology
• Experimental data
• Low energy experiments
• Multigroup cross sections
• Filtered neutron beam
• Nuclear data measurement
• Nuclear research reactor
• Filtered neutron beams development
• Applications at the horizontal channels