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Was - Fundamentals of Radiation Materials Science: Metals and Alloys

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Was Fundamentals of Radiation Materials Science: Metals and Alloys
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Part I Radiation Damage -- 1 The Radiation Damage Event -- 2 The Displacement of Atoms -- 3 The Damage Cascade -- 4 Point Defect Formation and Diffusion -- 5 Radiation-Enhanced and Diffusion Defect Reaction Rate Theory -- Part II Physical Effects of Radiation Damage -- 6 Radiation-Induced Segregation -- 7 Dislocation Microstructure -- 8 Irradiation-Induced Voids and Bubbles -- 9 Phase Stability Under Irradiation -- 10 Unique Effects of Ion Irradiation -- 11 Simulation of Neutron Irradiation Effects with Ions -- Part III Mechanical Effects of Radiation Damage -- 12 Irradiation Hardening and Deformation -- 13 Irradiation Creep and Growth -- 14 Fracture and Embrittlement -- 15 Corrosion and Stress Corrosion Cracking Fundamentals -- 16 Effects of Irradiation on Corrosion and Environmentally Assisted Cracking -- Index.;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, end-of-chapter problem sets and an online solutions manual. Aimed primarily and students of materials sciences and nuclear engineering, the book will also provide a valuable resource for academic and industrial research professionals.

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Part I
Radiation Damage
Springer Science+Business Media New York 2017
GARY S. WAS Fundamentals of Radiation Materials Science 10.1007/978-1-4939-3438-6_1
1. The Radiation Damage Event
Gary S. Was 1
(1)
Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 1921 Cooley Bldg., 2355 Bonisteel Blvd., Ann Arbor, MI 48109-2104, USA
Gary S. Was
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The radiation damage event is defined as the transfer of energy from an incident projectile to the solid and the resulting distribution of target atoms after completion of the event. The radiation damage event is actually composed of several distinct processes. These processes and their order of occurrence are as follows:
The interaction of an energetic incident particle with a lattice atom.
The transfer of kinetic energy to the lattice atom giving birth to a primary knock-on atom (PKA).
The displacement of the atom from its lattice site.
The passage of the displaced atom through the lattice and the accompanying creation of additional knock-on atoms.
The production of a displacement cascade (collection of point defects created by the PKA).
The termination of the PKA as an interstitial.
The radiation damage event is concluded when the PKA comes to rest in the lattice as an interstitial. The result of a radiation damage event is the creation of a collection of point defects (vacancies and interstitials) and clusters of these defects in the crystal lattice. It is worth noting that this entire chain of events consumes only about 1011 s (see Table ). Subsequent events involving the migration of the point defects and defect clusters and additional clustering or dissolution of the clusters are classified as radiation damage effects .
Table 1.1
Approximate timescale for the production of defects in irradiated metals (from [])
Time (s)
Event
Result
1018
Energy transfer from the incident particle
Creation of a primary knock-on atom (PKA)
1013
Displacement of lattice atoms by the PKA
Displacement cascade
1011
Energy dissipation, spontaneous recombination, and clustering
Stable Frenkel pairs (single interstitial atoms (SIA) and vacancies) and defect clusters
>108
Defect reactions by thermal migration
SIA and vacancy recombination, clustering, trapping, defect emission
What we first need to know in order to understand and quantify radiation damage is how to describe the interaction between a particle and a solid that produces displacements, and later on how to quantify this process. The most simple model is one that approximates the event as colliding hard spheres with displacement occurring when the transferred energy is high enough to knock the struck atom off its lattice site. In addition to energy transfer by hard sphere collisions, the moving atom loses energy by interactions with electrons, the Coulomb field of nearby atoms, the periodicity of the crystalline lattice, etc. The problem is reduced to the following. If we can describe the energy-dependent flux of the incident particle and the energy transfer cross sections (probabilities) for collisions between atoms, then we can quantify the PKA production in a differential energy range and utilize this to determine the number of displaced atoms.
In this chapter, we will concentrate on quantifying the energy transferred between interacting bodies as well as describing the energy transfer cross section. We will begin with neutronnucleus reactions since the neutrality of the neutron makes the interaction particularly straightforward. Following creation of the PKA, subsequent interactions occur between atoms, and the positive charge of the nucleus and the negative charge of the electron cloud become important in understanding how atoms interact. In fact, atomatom interaction is the low-energy limit of ionatom interactions that occur in reactor cores and via ion irradiation using accelerators over a wide energy range and can lead to the last type of interaction: ionization collisions.
1.1 NeutronNucleus Interactions
1.1.1 Elastic Scattering
By virtue of their electrical neutrality, elastic collisions between neutrons and nuclei can be represented as colliding hard spheres. When neutrons pass through a solid, there is a finite probability that they will collide with a lattice atom, imparting a recoil energy to the struck atom. This probability is defined by the double differential scattering cross section (in energy and angle), s ( E i, E f, ), where E i and E f are the incident and final energies and is the solid angle into which the neutron is scattered. We are often only interested in the scattering probability as a function of E i and the scattering angle. The single differential scattering cross section is as follows:
11 The total scattering probability for neutrons of energy E i is as - photo 1
(1.1)
The total scattering probability for neutrons of energy E i is as follows:
12 In the study of irradiation effects we are interested in the behavior of - photo 2
(1.2)
In the study of irradiation effects, we are interested in the behavior of the struck atom. So we are seeking s ( E i, T ); the energy transfer cross section, or the probability that a neutron of energy E i elastically scattering against an atom of mass M , will impart a recoil energy T to the struck atom. But first it is necessary to find T in terms of the neutron energy and the scattering angle. To do this, let us consider the dynamics of binary elastic collisions in the center-of-mass and laboratory frames.
Figure (a) shows the trajectories of a neutron and the target nucleus before and after scattering, as seen from both the laboratory reference system and the center-of-mass system. The easiest way to obtain a relationship between the incident neutron energy, scattering angle, and transferred energy is to analyze the dynamics of the collision in the center-of-mass (CM) system. When the collision is viewed in the center-of-mass system, the recoiling particles appear to move away from each other in opposite directions. Momentum conservation along the axes of approach and departure yields the following:
Fundamentals of Radiation Materials Science Metals and Alloys - image 3
(1.3)
and conservation of kinetic energy requires that:
14 Fig 11 Vector velocities a in the laboratory and - photo 4
(1.4)
Fig 11 Vector velocities a in the laboratory and center-of-mass CM - photo 5
Fig. 1.1
Vector velocities ( a ) in the laboratory and center-of-mass (CM) systems and ( b ) composite diagram relating velocities in the two systems
Using Eq. () to eliminate and we get 15 Therefore - photo 6
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