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Fundamentals of Radiation Materials Science GARY S. WAS

Fundamentals of Radiation Materials Science By GARY S. WAS

Fundamentals of Radiation Materials Science by GARY S. WAS


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Summary

Chapter 15 focuses on the fundamentals of corrosion and stress corrosion cracking, covering forms of corrosion, corrosion thermodynamics, corrosion kinetics, polarization theory, passivity, crevice corrosion, and stress corrosion cracking.

Fundamentals of Radiation Materials Science Summary

Fundamentals of Radiation Materials Science: Metals and Alloys by GARY S. WAS

The revised second edition of this established text offers readers a significantly expanded introduction to the effects of radiation on metals and alloys. It describes the various processes that occur when energetic particles strike a solid, inducing changes to the physical and mechanical properties of the material. Specifically it covers particle interaction with the metals and alloys used in nuclear reactor cores and hence subject to intense radiation fields. It describes the basics of particle-atom interaction for a range of particle types, the amount and spatial extent of the resulting radiation damage, the physical effects of irradiation and the changes in mechanical behavior of irradiated metals and alloys.

Updated throughout, some major enhancements for the new edition include improved treatment of low- and intermediate-energy elastic collisions and stopping power, expanded sections on molecular dynamics and kinetic Monte Carlo methodologies describing collision cascade evolution, new treatment of the multi-frequency model of diffusion, numerous examples of RIS in austenitic and ferritic-martensitic alloys, expanded treatment of in-cascade defect clustering, cluster evolution, and cluster mobility, new discussion of void behavior near grain boundaries, a new section on ion beam assisted deposition, and reorganization of hardening, creep and fracture of irradiated materials (Chaps 12-14) to provide a smoother and more integrated transition between the topics.

The book also contains two new chapters. Chapter 15 focuses on the fundamentals of corrosion and stress corrosion cracking, covering forms of corrosion, corrosion thermodynamics, corrosion kinetics, polarization theory, passivity, crevice corrosion, and stress corrosion cracking. Chapter 16 extends this treatment and considers the effects of irradiation on corrosion and environmentally assisted corrosion, including the effects of irradiation on water chemistry and the mechanisms of irradiation-induced stress corrosion cracking.

The book maintains the previous style, concepts are developed systematically and quantitatively, supported by worked examples, references for further reading and end-of-chapter problem sets. Aimed primarily at students of materials sciences and nuclear engineering, the book will also provide a valuable resource for academic and industrial research professionals.

Reviews of the first edition:

...nomenclature, problems and separate bibliography at the end of each chapter allow to the reader to reach a straightforward understanding of the subject, part by part. ... this book is very pleasant to read, well documented and can be seen as a very good introduction to the effects of irradiation on matter, or

as a good references compilation for experimented readers. - Pauly Nicolas, Physicalia Magazine, Vol. 30 (1), 2008

The text provides enough fundamental material to explain the science and theory behind radiation effects in solids, but is also written at a high enough level to be useful for professional scientists. Its organization suits a graduate level materials or nuclear science course... the text was written by a noted expert and active researcher in the field of radiation effects in metals, the selection and organization of the material is excellent... may well become a necessary reference for graduate students and researchers in radiation materials science. - L.M. Dougherty, 07/11/2008, JOM, the Member Journal of The Minerals, Metals and Materials Society.

About GARY S. WAS

Professor Gary Was is the Walter J. Weber, Jr. Professor of Sustainable Energy, Environmental and Earth Systems Engineering and holds appointments in Nuclear Engineering and Radiological Sciences, and Materials Science and Engineering at the University of Michigan. He has held positions as Director of the Michigan Memorial Phoenix Energy Institute, Associate Dean of the College of Engineering and Chair of the Nuclear Engineering and Radiological Sciences Department. Professor Was' research is focused on materials for advanced nuclear energy systems and radiation materials science, including environmental effects on materials, radiation effects, ion beam surface modification of materials and nuclear fuels. His current research includes development of structural materials for the SFR, behavior of fuel in the VHTR, fuel behavior modeling in LWRs, irradiation assisted stress corrosion cracking and irradiation-accelerated corrosion in water reactor environments. He is a Fellow of the Materials Research Society, ASM International, NACE International and the American Nuclear Society. Professor Was has published over 200 technical articles in referred, archival journals, presented over 300 conference papers, delivered 180 invited talks and seminars, and has published a graduate level textbook on Radiation Materials Science. Professor Was received the Presidential Young Investigator award from NSF,

the Champion H. Matthewson Award from TMS, the Outstanding and Special Achievement Awards by the Materials Science and Technology Division of the American Nuclear Society, the Henry Marion Howe Medal from ASM, and the Lee Hsun Award from the Chinese Academy of Sciences.

Table of Contents

Part I Radiation Damage.

1. The Radiation Damage Event.
1.1 Neutron-Nucleus Interactions. 1.2 Interactions Between Ions and Atoms. 1.3 Energy Loss Nomenclature. Problems. References.

2. The Displacement of Atoms.
2.1 Elementary Displacement Theory. 2.2 Modifications to the K-P Displacement Model. 2.3 The Displacement Cross Section. 2.4 Displacement Rates. 2.5 Correlation of Property Changes and Irradiation Dose. 2.6 Displacements from Charged Particle Irradiation. Nomenclature. Problems. References.

3. The Damage Cascade.
3.1 Displacement Mean Free Path. 3.2 Primary Recoil Spectrum. 3.3 Cascade Damage Energy and Cascade Volume. 3.4 Computer Simulations of Radiation Damage. 3.5 Stages of Cascade Development. 3.6 Behavior of Defects within the Cascade. Nomenclature. Problems. References.

4. Point Defect Formation and Diffusion.
4.1 Properties of Irradiation-Induced Defects. 4.2 Thermodynamics of Point Defect Formation. 4.3 Diffusion of Point Defects. 4.4 Correlated Diffusion. 4.5 Diffusion in Multicomponent Systems. 4.6 Diffusion along High Diffusivity Paths. Nomenclature. Problems. References.

5. Radiation-Enhanced and Diffusion Defect Reaction Rate Theory.
5.1 Point Defect Balance Equations. 5.2 Radiation-Enhanced Diffusion. 5.3 Defect Reactions. 5.4 React

ion Rate-Controlled Processes. 5.5 Diffusion-Limited Reactions. 5.6 Mixed Rate Control. 5.7 Defect-Grain Boundary Reactions. 5.8 Coherent Precipitates and Solutes. 5.9 Point Defect Recovery. Nomenclature. Problems. References.

Part II Physical Effects of Radiation Damage

6. Radiation-Induced Segregation.
6.1 Radiation-Induced Segregation in Concentrated Binary Alloys. 6.2 RIS in Ternary Alloys. 6.3 Effect of Local Composition Changes on RIS. 6.4 Effect of Solutes on RIS. 6.5 Examples of RIS in Austenitic Alloys. 6.6 RIS in Ferritic Alloys. 6.7 Effect of Grain Boundary Structure on RIS. Nomenclature. Problems. References.

7. Dislocation Microstructure.
7.1 Dislocation Lines. 7.2 Faulted Loops and Stacking Fault Tetrahedra. 7.3 Defect Clusters. 7.4 Extended Defects. 7.5 Effective Defect Production. 7.6 Nucleation and Growth of Dislocation Loops. 7.7 Dislocation Loop Growth. 7.8 Recovery. 7.9 Evolution of the Interstitial Loop Microstructure. Nomenclature. Problems. References.

8. Irradiation-Induced Voids and Bubbles.
8.1 Void Nucleation. 8.2 Void Growth. 8.3 Void Growth Equation. 8.4 Bubble Growth. Nomenclature. Problems. References.

9. Phase Stability Under Irradiation.
9.1 Radiation-Induced Segregation and Radiation-Induced Precipitation. 9.2 Recoil Dissolution. 9.3 Radiati

on Disordering. 9.4 Incoherent Precipitate Nucleation. 9.5 Coherent Precipitate Nucleation. 9.6 Examples of Radiation-induced Precipitation. 9.7 Metastable Phases. 9.8 Amorphization. 9.9 Phase Stability in Reactor Core Component Alloys. Nomenclature. Problems. References.

10. Unique Effe

cts o

f Ion Irradiation.
10.1 Ion Irradiation Techniques. 10.2 Composition Changes. 10.3 Other Effects of Ion Implantation. 10.4 High Dose Gas Loading: Blistering and Exfoilation. 10.5 Solid Phases and Inert Gas Bubble Lattices. 10.6 Displacements due to Electronic Excitation. 10.7 Ion Beam Assisted Deposition. Nomenclature. Problems. References.

11. Simulation of Neutron Irradiation Effects with Ions.
11.1 Motivation for Using Ion Irradiation as a Surrogate for Neutron Irradiation. 11.2 Review of Aspects of Radiation Damage Relevant to Ion Irradiation. 11.3 Particle Type Dependence of RIS. 11.4 Advantages and Disadvantages of the Various Particle Types. 11.5 Irradiation Parameters for Particle Irradiations. 11.6 Emulation of Neutron Irradiation Damage with Proton Irradiation. 11.7 Emulation of Neutron Irradiation Damage with Self-Ion Irradiation. Nomenclature. Problems. References.

Part III Mechanical Effects of Radiation Damage.

12 Irradiation Hardening and Deformation.
12.1 Elastic and Plastic Deformation. 12.2 Irradiation Hardening. 12.

3 Deformation in Irradiated Metals. Nomenclature. Problems. References.

13. Irradiation Creep and Growth.
13.1 Thermal Creep. 13.2 Irradiation Creep. 13.3 Irradiation Growth and Creep in Zirconium Alloys. Nomenclature. Problems. References.

14. Fracture and Embrittlement.
14.1 Types of Fracture. 14.2 The Cohesive Strength of Metals. 14.3 Fracture Mechanics. 14.4 Fractu

re

Mechanics T

ests. 14.5 Elastic-plastic Fracture Mechanics. 14.6 Brittle Fracture. 14.7 Irradiation-Induced Embrittlement in Ferritic Steels. 14.8 Fracture and Fatigue of Austenitic Alloys at Low to Intermediate Temperatures. 14.9 High-Temperature Embrittlement. Nomenclature. Problems. References.

15. Corrosion and Stress Corrosion Cracking Fundamentals.
15.1 Forms of Corrosion. 15.2 Thermodynamics of Corrosion. 15.3 Kinetics of Corrosion. 15.4 Polarization. 15.5 Passivity. 15.6 Crevice Corrosion. 15.7 Stress Corrosion Cracking.

16. Effects of Irradiation on Corrosion and Environmentally Assisted Cracking.
16.1 Effects of Irradiation on Water Chemistry. 16.2 Effects of Irradiation on Oxide. 16.3 Effects of Irradiation on Stress Corrosion Cracking. 16.4 Mechanism of IASCC. Nomenclature. Problems. References.

Index.

Additional information

NGR9781493934362
9781493934362
1493934368
Fundamentals of Radiation Materials Science: Metals and Alloys by GARY S. WAS
New
Hardback
Springer-Verlag New York Inc.
2016-07-09
1002
N/A
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