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Comprehensive Nuclear Materials
原子力材料全書(全5巻)

¥ 272,995 (tax included)

Description

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《《 東北大学 小無健司准教授 》》

原子力エネルギーの研究は、1942年に物理学者エンリコフェルミが米国シカゴで最初の原子炉CP1を建設して以来長年に亘って続けられている。原子力エネルギーの特徴は、化石エネルギーや自然エネルギーに比べて桁違いに大きなエネルギーを持っていることである。核分裂反応や核融合反応に伴って高エネルギーの放射線が発生し、原子炉を構成する材料や核燃料は、この放射線の影響を受けることになる。そのため、この影響を評価すること、またこれに耐える材料を開発することが原子力材料工学分野での共通したテーマとなっている。
このハンドブックは、この様な原子力エネルギー特有のテーマを含めて、核分裂炉および核融合炉を実現化するための材料の科学と技術に関する知見をまとめたものである。全体で5分冊から構成され、合計で100以上の章から構成されている。ここで取り上げられている研究のトピックスの中には、原子力の開発当初から長年研究開発が続けられて来たものが多く含まれている。それらに対しては、このハンドブックは積み重ねられてきた技術の蓄積を過去に遡る道しるべとして活用することが出来る。それとは対照的に、第一原理計算や分子動力学計算などの計算科学手法のように近年注目が高まっているトピックスがある。それらに対しては、新たにその分野の研究を始める際の良質の参考書として利用できる。
欧米と日本の多くの第一線の研究者がこのハンドブックの執筆に貢献しており、次の世代の研究者への技術の継承に役立つばかりでなく、今後原子力を導入しようとしている国々の研究者と情報を分かち合う良い情報源にもなると期待される。

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アクチノイドからジルコニウム合金まで、核物質に関する最新の知見を網羅。極端な原子力環境における材料の応用、選択、評価、検証についても言及しており、核分裂、核融合炉と高出力加速器燃料に適した材料や被覆管、減速材と制御材料、構造、機能および廃棄物など燃料における多様な機能に適した材料に関する全ての分類について解説されている。

More than 50 years after the introduction of nuclear energy for peaceful uses, with rapid growth in the 1960s and 1970s, and stagnation at the end of the 20th century, a global renaissance for nuclear energy seems ahead of us.

Although the nuclear field is typically known for its incremental progress, the challenges posed by the Generation IV initiative have stimulated renewed interest in advanced fission reactor concepts, often by revisiting ideas from the past. At the same time fusion reactor research is facing its next milestone by the construction of ITER in Cadarache.

Within the context of strict international regulatory guidance and mandatory performance characteristics, materials for modern nuclear systems need to demonstrate ever-increasing standards of dimensional stability, mechanical properties, reduction of waste byproducts and optimal cost-effectiveness.

The progress in numerical simulation of the material evolution on scientific and engineering scale is particularly notable. Simulation techniques at the atomistic or meso scale (e.g. electronic structure calculations, molecular dynamics, kinetic Monte Carlo) are increasingly helping to unravel the complex processes occurring in materials under extreme conditions, and give insight in the causes and thus helping to design remedies.

Comprehensive Nuclear Materials encapsulates a panorama of fundamental information on the vast variety of materials employed in the broad field of nuclear technology. The work addresses, in five volumes, 3,400 pages and over 120 chapter-length articles, the full panorama of historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. It synthesizes the most pertinent research to support the selection, assessment, validation and engineering of materials in extreme nuclear environments. The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.


Key Features
* Encompasses a rich seam of current information on the vast and multidisciplinary field of nuclear materials employed in fission and prototype fusion systems.

* Discussion includes both historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers.

* Synthesizes pertinent current science to support the selection, assessment, validation and engineering of materials in extreme nuclear environments.

* The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.

Contents

Fundamental Properties of Defects in Metals
Fundamental Point Defect Properties in Ceramics
Radiation-Induced Effects on Microstructure
Radiation-Induced Effects on Material Properties of Metals (Mechanical and Dimensional)
Radiation-Induced Effects on Material Properties of Ceramics (Mechanical and Dimensional)
The Effects of Helium in Irradiated Structural Alloys
Radiation Damage Using Ion Beams
Ab Initio Electronic Structure Calculations for Nuclear Materials
Molecular Dynamics
Interatomic Potential Development
Primary Radiation Damage Formation
Atomic-Level Level Dislocation Dynamics in Irradiated Metals
Mean Field Reaction Rate Theory
Kinetic Monte Carlo Simulations of Irradiation Effects
Phase Field Methods
Dislocation Dynamics
Computational Thermodynamics: Application to Nuclear Materials
Radiation-Induced Segregation
The Actinides Elements: Properties and Characteristics
Thermodynamic and Thermophysical Properties of the Actinide Oxides
Thermodynamic and Thermophysical Properties of the Actinide Nitrides
Thermodynamic and Thermophysical Properties of the Actinide Carbides
Phase Diagrams of Actinide Alloys
The U-F System
Zirconium Alloys: Properties and Characteristics
Nickel Alloys: Properties and Characteristics
Properties of Austenitic Steels for Nuclear Reactor Applications
Graphite: Properties and Characteristics
Neutron Reflector Materials (Be, Hydrides)
Proerties and Characteristics of SiC and SiC/SiC Composites
Proerties and Characteristics of ZrC
Properties of Liquid Metal Coolants
Uranium Oxide and MOX Production
Burnable Poison-Doped Fuel
Thermal Properties of Irradiated UO2 and MOX
Radiation Effects in UO2
Fuel Performance of Light Water Reactors (Uranium Oxide and MOX)
Fission Product Chemistry in Oxide Fuels
Fuel Performance of Fast Spectrum Oxide Fuel
Transient Response of LWR Fuels (RIA)
Behaviour of LWR Fuel During Loss-of_Coolant Accidents
Behaviour of Fast Reactor Fuels During Transient and Accident Conditions
Core Concrete Interaction
Metal Fuel
Nitride Fuel
Carbide Fuel
Thorium Oxide Fuel
Actinide Bearing Fuels and Transmutation Targets
TRISO Fuel Production
TRISO-Coated Particle Fuel Performance
Advanced Concepts in TRISO Fuel
Inert Matrix Fuel
Composite Fuel (CERMET, CERCER)
Sphere-Pac and VIPAC Fuel
Uranium-Zirconium Hydride Fuel
Molten Salt Reactor Fuel and Coolant
Uranium Inter-Metallic Fuels (U-Al, U-Si, U-Mo)
Metal Fuel-Cladding Interaction
Ceramic Fuel-Cladding Interaction
Thermal Spectrum Control Rod Materials
Fast Spectrum Control Rod Materials
Oxide Fuel Performance Modelling and Simulation
Modeling of Fission-Gas Induced Swelling of Nuclear Fuels
Matter Transport in Fast Reactor Fuels
Modelling of Pellet Cladding Interaction
Metal Fuel Performance Modelling and Simulation
TRISO Fuel Performance Modelling and Simulation
Modeling of Sphere-Pac Fuel
Radiation Effects in Zirconium Alloys
Radiation Damage in Austenitic Steels
Ferritic Steels and Advanced Ferritic-Martensitic Steels
Radiation Effects in Nickel-Based Alloys
Radiation Damage of Reactor Pressure Vessel Steels
Radiation Effects in Refractory Metals and Alloys
Radiation Effects in SiC and SiC-SiC
Oxide Dispersion Strengthened Steels
Welds for Nuclear Systems
Radiation Effects in Graphite
Graphite in Gas-Cooled Reactors
Vanadium for Nuclear Systems
Concrete
Fracture Toughness Master Curve of BCC Steels
Ceramic Breeder Materials
Tritium Barriers and Tritium Diffusion in Fusion Reactors
Tungsten as a Plasma-Facing Material
Carbon as a Fusion Plasma-Facing Material
Beryllium as a Plasma-Facing Material for Near-Term Fusion Devices
Physical and Mechanical Properties of Copper and Copper Alloys
Ceramic Coating as Insulators
Radiation Effects on the Physical Properties of Dielectric Insulators for Fusion Reactors
Corrosion and Compatibility
Water Chemistry Control in LWRs
Corrosion of Zirconium Alloys
Corrosion and Stress Corrosion Cracking of Ni-Base Alloys
Corrosion and Stress Corrosion Cracking of Austenitic Stainless Steels
Corrosion and Environmentally-Assisted Cracking of Carbon and Low-Alloy Steels
Performance of Aluminium in Research Reactors
Irradiation Assisted Stress Corrosion Cracking
Material Performance in Lead-Alloys
Material Performance in Molten Salts
Material Performance in Helium-Cooled Systems
Material Performance in Supercritical Water
Material Performance in Sodium
Spent Fuel Dissolution and Reprocessing Processes
Degradation Issues in Aqueous Reprocessing Systems
Spent Fuel as Waste Material
Waste Containers
Waste Glass
Ceramic Waste Forms
Metallic Waste Forms
Graphite
Minerals and Natural Analogues