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ME 4803 DEO

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ME 4803 DEO
Chaitanya Deo
NRE
NRE/ME 4803 Special Topics Course: Nuclear Reactor Materials
Fall 2012
Catalog Description:
This course investigates the relationship between the structure
and properties of materials used in nuclear reactors specifically nuclear cladding and fuel under irradiation.
Prerequisites
MSE 2001 or equivalent
Textbook:
Gary Was "Fundamental Radiation Materials Science", Wiley,
3540494715
References:
Don Olander "Fundamental Aspects of Nuclear reactor Fuel
elements"
Arthur Motta and Don Olander "Light Water Reactor Materials"
- new book not yet published
Instructor
Chaitanya S. Deo
Goals
This course provides a background on the types of materials
used in nuclear reactors and their response to neutron
irradiation. Materials problems encountered in the operation of
nuclear power reactors for energy production are discussed
here. The objective of the course is to give nuclear engineering
students a background in materials, so they understand the
limitations put on reactor operations and reactor design by
materials performance.
Grading
Homework
Tests
30%
70%
Topics Covered:
The Radiation Damage Event
Neutron–Nucleus Interactions
Interactions Between Ions and Atoms
Interatomic Potentials
Collision Kinematics
Ionization Collisions
Energy Loss Theory
Range Calculations
The Displacement of Atoms
Elementary Displacement Theory
Displacement Probability
The Kinchin and Pease Model for Atom Displacements
The Displacement Energy
The Electron Energy Loss Limit .
Energy Transfer Cross Sections
Energy Loss by Electronic Excitation
1
Chaitanya Deo
NRE
Effects of Crystallinity
The Displacement Cross Section
Displacement Rates
The Damage Cascade
Displacement Mean Free Path
Primary Recoil Spectrum
Cascade Damage Energy and Cascade Volume
Stages of Cascade Development .
Behavior of Defects within the Cascade
Point Defect Formation and Diffusion
Properties of Irradiation-Induced Defects
Thermodynamics of Point Defect Formation
Diffusion of Point Defects
Correlated Diffusion
Diffusion in Multi-component Systems
Diffusion along High Diffusivity Paths
Radiation-Enhanced and Diffusion Defect Reaction Rate Theory
Point Defect Balance Equations
Radiation-Enhanced Diffusion
Defect Reactions
Reaction Rate-Controlled Processes
Diffusion-Limited Reactions
Defect–Grain Boundary Reactions
Examples of Materials in Nuclear reactors -Light water reactors and Gen IV designs
Oxide fuels - LWR
Zirconium Alloys LWR
Metal, Carbide and Nitride fuels Gen IV
Steel and other metallic alloys Gen IV
Phenomena encountered in nuclear reactors (pick 2-3 topics)
Voids and cavities in Solids
Fission Product Behavior
Water Chemistry and its Influence on Corrosion
Waterside Corrosion and Hydriding of Zr Cladding
Fuel Rod Failure Mechanisms
Phase Transformations under irradiation
Inter Granular Stress-Corrosion Cracking (IGSCC)
Irradiation Induced Mechanical Property Changes: Hardening and Embrittlement
Irradiation Creep and growth
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