Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation.
Based on research findings, the book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors. It discusses a database of MOX properties, including oxygen potential, melting temperature, the lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients, that was used to derive a science-based model of MOX properties (Sci-M Pro) for fuel-performance code development.
Features
Concisely covers the essential aspects of MOX nuclear fuels.
Explores MOX nuclear fuels by systematically evaluating various physical property values using a behavior model.
Presents fuel property simulation technology.
Considers oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion.
Discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients.
The book will be useful for researchers and engineers working in the field of nuclear fuels and nuclear materials.
Author(s): Masato Kato, Masahiko Machida
Publisher: CRC Press
Year: 2022
Language: English
Pages: 182
City: Boca Raton
Cover
Half Title
Title Page
Copyright Page
Table of Contents
Preface
Contributors
Chapter 1 Introduction
Chapter 2 Experimental Techniques
2.1 Sample Preparation
2.2 O/M Control
2.3 Reaction with High-Temperature Material
Chapter 3 Properties
3.1 Lattice Parameters
3.2 Thermal Expansion
3.3 Oxygen Potential
3.4 Oxygen Diffusion Coefficients
3.5 Melting Temperature
3.6 Electrical Conduction
3.7 Sound Speeds and Mechanical Properties
3.8 Heat Capacity
3.9 Thermal Conductivity
3.10 Self-Radiation Effects
3.11 Phase Separation
Notation
References
Chapter 4 Theoretical and Computational Works on Oxide Nuclear Fuel Materials
4.1 Overview
4.2 DFT Calculations and Some Related Remarks
4.2.1 Ground States of Actinide Dioxides
4.2.2 DFT Calculation Methods
4.2.3 UO[sub(2)]
4.2.4 PuO[sub(2)]
4.2.5 Other Actinide Dioxides
4.3 MD with Interatomic Potentials: Empirical and Machine Learning
4.3.1 MD Simulations with Empirical Interatomic Potentials
4.3.2 MLMD Simulations for ThO[sub(2)]
4.4 Brief Introductory Review on Mesoscale Approaches
4.4.1 Kinetic Monte Carlo Method
4.4.2 Phase Field Model
4.4.3 Rate Theory
4.5 High-Temperature Thermodynamical Properties
4.5.1 Heat Capacity
4.5.2 Thermal Conductivity
4.6 Defect Chemistry and Related High-Temperature Dynamics
4.7 Brief Notes on Multiscale Modeling of Fuel Materials
4.7.1 Heat Transport
4.7.2 Matter Transport
4.7.3 Fission Gas Behaviors
4.7.4 Restructuring
4.7.5 Pellet-Cladding Interaction
4.7.6 Impacts and Future Directions of Multiscale Approaches
Abbreviations
References
Chapter 5 Fuel Technologies for Irradiation Performance Analysis
5.1 Relationship between Model and Properties
5.2 Bredig Transition Representation
5.3 Temperature Profile Analysis
5.4 O/M Redistribution
5.5 Restructuring Caused by Vapor Pressure
5.6 Chemical Stability of Fission Products
5.7 Other Fuel Behaviors
References
Chapter 6 Science-Based Physical Property Model and Outlook for Fuel Development
Appendixes: Database for MOX Properties
Index
