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Nuclear Reactor Physics Experiments
B5変並製・130頁
ISBN: 9784876989591
発行年月: 2010/03
記述言語: 英語
- 本体： 3,300円（税込 3,630円）
-
在庫なし
京都大学が保有する臨界集合体実験装置は，原子炉物理学の基礎研究を行う世界でも稀有の研究炉として知られる．本書は京都大学臨界集合体実験装置（KUCA）において35年にわたって行われた大学院実験コースを基に、原子力関連分野を専攻する学生や技術者の原子力教育および訓練の国際コースのテキストとして編纂された．臨界近接や制御棒校正にはじまり原子炉物理の基本パラメータの測定方法をも含む本書は，アジア地域における原子力教育の拠点を目指すうえでの機軸となろう．
『日本原子力学会誌』Vol.52, No.11(2010)、53頁、評者：山根義宏氏
Tsuyoshi Misawa (BS, 1984; MS, 1986; Ph. D., 1989, nuclear engineering, Kyoto University, Japan) is an Associate Professor of Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University. His background includes reactor physics, nuclear design calculations, and nuclear education.
Hironobu Unesaki (BS, 1985; MS, 1987, nuclear engineering, Osaka University, Japan; Ph. D., 2001, energy science, Kyoto University, Japan) is a Professor of Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University. His background includes reactor physics, nuclear design calculations, and nuclear fuel management.
Cheolho Pyeon (BS, 1995; MS, 1997, nuclear engineering, Nagoya University, Japan; Ph. D., 2000, energy science, Kyoto University, Japan) is an Assistant Professor of Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University. His background includes reactor physics, nuclear design calculations, and nuclear education.
Hironobu Unesaki (BS, 1985; MS, 1987, nuclear engineering, Osaka University, Japan; Ph. D., 2001, energy science, Kyoto University, Japan) is a Professor of Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University. His background includes reactor physics, nuclear design calculations, and nuclear fuel management.
Cheolho Pyeon (BS, 1995; MS, 1997, nuclear engineering, Nagoya University, Japan; Ph. D., 2000, energy science, Kyoto University, Japan) is an Assistant Professor of Nuclear Engineering Science Division, Research Reactor Institute, Kyoto University. His background includes reactor physics, nuclear design calculations, and nuclear education.
Contents
Preface
List of Contributors
Introduction to Kyoto University Critical Assembly (KUCA)
1. General Description of KUCA Facility
1-1 KUCA Facility
1-2 Solid-Moderated-Cores (A- and B-cores)
1-3 Light-Water-Moderated Core (C-core)
1-4 Pulsed Neutron Source
1-5 Control Room
2. Details of the Light-Water-Moderated Core (C-core)
2-1 Overall Structure
2-2 Core Tank and Grid Plate
2-3 Fuel Plate and Fuel Frame
2-4 Core Configuration
Chapter 1 Approach to Criticality
1-1 Fission Chain Reaction, Neutron Multiplication, and Approach to Criticality
1-1-1 Fission Chain Reaction
1-1-2 Neutron Multiplication
1-1-3 Inverse Count Rate and Approach to Criticality
1-2 Experiments
1-2-1 Neutron Detectors
1-2-2 Actual Procedure of Experiments
1-2-3 Determination of Infinite Reflector Thickness
1-3 Discussion
1-4 Preparatory Report
1-4-1 Numerical Simulation of Approach to Criticality Experiment
1-4-2 Two-Energy-Group Diffusion Calculation of Reflected Reactor
Appendix 1
1A. Analytical Solution of Two-Energy-Group Diffusion Equation
1B. Solution for Core Region
1C. Solution for Reflector Region
1D. Determination of Critical Core Size
1E. Neutron Flux Distribution
Chapter 2 Control Rod Calibration
2-1 Purpose
2-2 Principle
2-2-1 Reactor Kinetic Equation
2-2-2 Positive Period Method
2-2-3 Control Rod Drop Method
2-2-4 Compensation Method
2-3 Experiments
2-3-1 Core Configuration
2-3-2 Period Method Experiment
2-3-3 Rod Drop Method Experiment
2-4 Discussion
2-5 Preparatory Report
Appendix 2
2A. Neutron Lifetime
2B. Delayed Neutron Data and Basic Parameters of KUCA
2C. First-Order Perturbation Theory
2D. Control Rod Calibration Curve
Chapter 3 Measurement of Reaction Rate
3-1 Purpose
3-2 Principle
3-2-1 Features of Neutron Activation Detector
3-2-2 Measurement of Neutron Flux Using Activation Detector
3-2-3 Measurement of Radioactivity Using Gold (Au) Activation Foil
3-2-4 Detection Efficiency
3-3 Activation Reaction Rate Contributed by Thermal Neutron Flux
3-3-1 Neutron Spectrum in Reactor Core
3-3-2 Activation Reaction Rate Contributed by Thermal Neutrons
3-4 Experiments
3-4-1 Core Configuration
3-4-2 Equipment and Irradiation of Gold Wires and Foils
3-4-3 Measurement of Radiation of Gold Wires and Foils
3-5 Discussion
3-6 Preparatory Report
Appendix 3
3A. Activation Reaction Rate by 4- Coincidence Method
3A-1 Principle of 4- Coincidence Method
3A-2 Absolute Measurement by 4- Coincidence Method
3B. Outline of the HPGe Detector
Chapter 4 Feynman- Method
4-1 Purpose
4-2 Variance-to-Mean Ratio in Multiplication System
4-2-1 Decay Constant
4-2-2 Value Expressed by Reactivity
4-2-3 Value
4-2-4 Asymptotic Behavior of Value
4-2-5 Value in a Critical System by Delayed Neutrons
4-2-6 Relationship between Power and Value
4-3 Experiments
4-3-1 Experimental Equipment
4-3-2 Experimental Methods
4-3-3 Data Processing
4-4 Discussion
Appendix 4
4A. Derivation of Equations for Feynman- Method
4A-1 Steady State
4A-2 Consideration of Delayed Neutrons
4A-3 Initial Correlation Correction, Spatial Dependence, and Fission Counter
Chapter 5 Pulsed Neutron Method
5-1 Purpose
5-2 Principle
5-3 Experimental Equipment
5-4 Experimental Methods
5-5 Data Processing
5-6 Discussion
Preface
List of Contributors
Introduction to Kyoto University Critical Assembly (KUCA)
1. General Description of KUCA Facility
1-1 KUCA Facility
1-2 Solid-Moderated-Cores (A- and B-cores)
1-3 Light-Water-Moderated Core (C-core)
1-4 Pulsed Neutron Source
1-5 Control Room
2. Details of the Light-Water-Moderated Core (C-core)
2-1 Overall Structure
2-2 Core Tank and Grid Plate
2-3 Fuel Plate and Fuel Frame
2-4 Core Configuration
Chapter 1 Approach to Criticality
1-1 Fission Chain Reaction, Neutron Multiplication, and Approach to Criticality
1-1-1 Fission Chain Reaction
1-1-2 Neutron Multiplication
1-1-3 Inverse Count Rate and Approach to Criticality
1-2 Experiments
1-2-1 Neutron Detectors
1-2-2 Actual Procedure of Experiments
1-2-3 Determination of Infinite Reflector Thickness
1-3 Discussion
1-4 Preparatory Report
1-4-1 Numerical Simulation of Approach to Criticality Experiment
1-4-2 Two-Energy-Group Diffusion Calculation of Reflected Reactor
Appendix 1
1A. Analytical Solution of Two-Energy-Group Diffusion Equation
1B. Solution for Core Region
1C. Solution for Reflector Region
1D. Determination of Critical Core Size
1E. Neutron Flux Distribution
Chapter 2 Control Rod Calibration
2-1 Purpose
2-2 Principle
2-2-1 Reactor Kinetic Equation
2-2-2 Positive Period Method
2-2-3 Control Rod Drop Method
2-2-4 Compensation Method
2-3 Experiments
2-3-1 Core Configuration
2-3-2 Period Method Experiment
2-3-3 Rod Drop Method Experiment
2-4 Discussion
2-5 Preparatory Report
Appendix 2
2A. Neutron Lifetime
2B. Delayed Neutron Data and Basic Parameters of KUCA
2C. First-Order Perturbation Theory
2D. Control Rod Calibration Curve
Chapter 3 Measurement of Reaction Rate
3-1 Purpose
3-2 Principle
3-2-1 Features of Neutron Activation Detector
3-2-2 Measurement of Neutron Flux Using Activation Detector
3-2-3 Measurement of Radioactivity Using Gold (Au) Activation Foil
3-2-4 Detection Efficiency
3-3 Activation Reaction Rate Contributed by Thermal Neutron Flux
3-3-1 Neutron Spectrum in Reactor Core
3-3-2 Activation Reaction Rate Contributed by Thermal Neutrons
3-4 Experiments
3-4-1 Core Configuration
3-4-2 Equipment and Irradiation of Gold Wires and Foils
3-4-3 Measurement of Radiation of Gold Wires and Foils
3-5 Discussion
3-6 Preparatory Report
Appendix 3
3A. Activation Reaction Rate by 4- Coincidence Method
3A-1 Principle of 4- Coincidence Method
3A-2 Absolute Measurement by 4- Coincidence Method
3B. Outline of the HPGe Detector
Chapter 4 Feynman- Method
4-1 Purpose
4-2 Variance-to-Mean Ratio in Multiplication System
4-2-1 Decay Constant
4-2-2 Value Expressed by Reactivity
4-2-3 Value
4-2-4 Asymptotic Behavior of Value
4-2-5 Value in a Critical System by Delayed Neutrons
4-2-6 Relationship between Power and Value
4-3 Experiments
4-3-1 Experimental Equipment
4-3-2 Experimental Methods
4-3-3 Data Processing
4-4 Discussion
Appendix 4
4A. Derivation of Equations for Feynman- Method
4A-1 Steady State
4A-2 Consideration of Delayed Neutrons
4A-3 Initial Correlation Correction, Spatial Dependence, and Fission Counter
Chapter 5 Pulsed Neutron Method
5-1 Purpose
5-2 Principle
5-3 Experimental Equipment
5-4 Experimental Methods
5-5 Data Processing
5-6 Discussion
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