Nuclear materials / Michael P. Hemsworth, editor.

Format:

Book

Contributor:

Hemsworth, Michael P.

Series:

Physics research and technology.

Materials science and technologies series.

Physics research and technology

Materials science and technologies

Language:

English

Subjects (All):

Nuclear reactors--Materials.

Nuclear reactors.

Nuclear chemistry.

Radioactive wastes.

Physical Description:

1 online resource (238 p.)

Edition:

1st ed.

Place of Publication:

Hauppauge, N.Y. : Nova Science Publishers, 2011.

Language Note:

English

Summary:

Gathers topical research in the study of nuclear materials. This book discusses topics that include experimental studies in nuclear fuel alloys for research reactors; the removal of arsenic from ground and surface waters using lanthanides; and, simulation of fission product transport from fuel to primary coolant of PWRs.

Contents:

Intro

NUCLEAR MATERIALS

Contents

Preface

Co-Precipitation Model Coupled with Prediction Model for the Removal of Arsenic from Ground and Surface Waters Using Lanthanides

Abstract

1. Introduction

1.1. Sources of Arsenic in Ground Water

1.2. Removal of Arsenic through Adsorption on Solid Surfaces

1.3. Objectives of This Chapter

2. Background

2.1. Factors Influencing Arsenic Migration in Natural Waters

Inorganic Carbon Concentration

Phosphate and Silicate Concentration

Organic Matter Content

2.2. Aqueous Speciation of Arsenic

2.3. Surface Speciation of Arsenic

2.4. Surface Complexation Models for Arsenic Adsorption

2.5. Solubility of Rare Earth Arsenates Compared to Arsenates of Other Ions

Suitability of Calcium and Magnesium Arsenates

Suitability of Iron (III) Arsenates

Suitability of Lead Arsenates

Suitability of Arsenates of Lanthanides and Actinides

3. Methods

3.1. Predictive Model for Arsenic Removal from Soil

3.1.1. Integrity of Data Used for Developing and Testing the Predictive Model

3.1.2. Integrity of Data Used in Model Fitting

3.1.3. Predictive Model Fitting

3.1.4. Measured Adsorption Surfaces as a Function of Soils Parameters

3.1.5. Adsorption Contours of Arsenic as a Function of Soil Parameters

3.1.6. Adsorption Envelops of Arsenic

3.2. Surface Precipitation Model for Arsenic Adsorption

3.2.1. Linear Free Energy Model

3.2.2. Model Adaptation for Surface Precipitation of Arsenic

3.2.3. Surface Precipitation Reactions

3.2.4. Calculating Equilibrium Surface Precipitation Constants

4. Results and Discussion

4.1. Fitted Predictive Model for Arsenic Adsorption

4.1.1. Validation of Prediction Model

4.2. Surface Precipitation of Arsenic onto Hydrated Oxides of Lanthanides and Actinides

5. Conclusions.

References

Experimental Studies and First Principles Calculations in Nuclear Fuel Alloys for Research Reactors

1.1. Role of Interaction Energies in U(Mo) Phase Stability

1.2. Interaction Layer between the U(Mo) Fuel and the Aluminum Matrix

1.2.1. The Pseudo-Binary Phase Diagram USi3-UAl3 as a Basis for the Characterization of The Reaction Layer in U-Mo/Al-Si Alloys Diffusion Couples

1.2.2. Low Silicon U(Al,Si)3 Stabilization by Zr Addition

1.2.3. UAl3-Al Interaction Layer Growth

1.3. U-Al System and UAl4 Stability

1.4. Monolithic Fuel

2. Modeling Tools

2.1. First-Principles Calculations of Thermodynamic Properties of Ordered Solids

2.2. First-Principles Calculations of Thermodynamics of Disordered Solids. The Cluster Expansion Formalism

2.3. CALPHAD Modeling of Thermodynamics

2.4. CALPHAD Modeling of Atomic Mobility

3. Results and Discussion

3.1. Cluster Expansion in the Bcc U-Mo System. U(Mo) Phase Stability

3.2. UAl3 Stabilization by Si Addition. UAl3-USi3 Pseudobinary System Ground State

3.3. Low Silicon U(Al,Si)3 Stabilization by Zr Addition. Experimental Results

3.4. Kinetics of Interaction Layer Growth in an UAl3/Al Diffusion Couple

3.5. U-Al System and UAl4 Stability

3.6. Elastic Constants of (U(Mo) Alloys

Conclusion

Acknowledgments

References

Radiation Damage and Recovery of Crystals: Frenkel vs. Schottky Defect Production

2. Irradiation Creep

2.1. SIPA and SIPE Mechanisms of Creep

2.2. Radiation-Induced Emission of Vacancies from Extended Defects

2.2.1. Unstable Frenkel Pairs

2.2.2. Focusons

2.2.3. Quodons

2.3. Creep Due to Radiation and Stress Induced Preference in Emission (RSIPE)

2.4. SIPE vs. SIPA Summary

3. Irradiation Swelling.

3.1. Experimental Observations of the Radiation-Induced Void Annealing

3.1.1. Irradiation of Nickel with Cr Ions

3.1.2. Irradiation of Nickel with Protons

3.1.3. Irradiation of Copper with Protons

3.2. Quodon Model of the Radiation-Induced Void Annealing

4. Void Lattice Formation

5. Conclusion

Fuel Restructuring and Actinide Radial Redistributions in Americium-Containing Uranium-Plutonium Mixed Oxide Fuels Irradiated in a Fast Reactor

2. Experimental

2.1. Fuel Fabrication

2.2. Irradiation Conditions

2.4. Post-Irradiation Examinations (PIEs)

3.1. NDES for B14 Test

3.1.1. Nondestructive Observation by X-Ray CT

3.2. Destructive Examinations

3.2.1. Observation of Fuel Microstructure

3.2.2. Axial Distribution of Central Void Diameter

3.2.3. Dependence of Linear Heating Rate on Fuel Restructuring

3.2.4. Radial Redistribution of Fuel Constituents

4. Summary

Microstructural Characterization of Structural Materials of Pressurized Heavy Water Reactor

Introduction

2. Experimental Details

2.1. Specimen Preparation

2.1.1. Powdered and Cold Worked Samples

2.1.2. Irradiation of Zircaloy-2, Zr-1%Nb-1%Sn-0.1Fe, Zr-1Nb, using Light Ion (Proton) and Heavy Ions (O5+ or Ne6+)

2.2. Data Collection for XRD Analysis

3. Method of Analysis

3.1. Warren Averbach Technique

3.1. Williamson-Hall Technique

3.2. Modified Rietveld Technique

3.3. Simplified Breadth Method

3.4. Double Voigt Technique

3.5. MarqX Method

3.6. Evaluation of Dislocation Density in a Material

4.1. Analysis of Deformed Powdered Sample

4.2. Analysis of Cold Rolled Sample

4.3. Analysis of Irradiated Samples

References.

Current Trends in Mathematical Modeling and Simulation of Fission Product Transport from Fuel to Primary Coolant of PWRs

Glossary

2. Experimental Efforts

2.1. In-Pile Tests

2.2. Out-of-Pile Tests

3. Review of Fission Product Activity Simulation Codes

4. Kinetic Modeling

4.1. Computational Scheme

4.2. Steady State Analysis

4.3. Power Perturbations

4.4. Flow-Rate Transients

5. Stochastic Modeling

6. Conclusions

Recent Advances in Molecular Dynamics Modelling of Radiation Effects in -Zr

2. Simulation Technique

2.1. MD Method

2.2. Modelling the Cascade Ballistic Stage

2.3. Identification of Point Defects and Point Defect Clusters

3. Number of Frenkel Pairs

4. Fraction of Point Defects in Point Defect Clusters

5. Typical Point Defect Clusters Found in Displacement Cascades

5.1. SIA Clusters

5.2. Vacancy Clusters

6. Atomic-Scale Modelling of Edge

Dislocations in α-Zirconium

6.1. Simulation Technique and Identification of Dislocation Core

6.2. Atomic Displacement and Structure of Dislocation Core

6.3. Peierls Stress and Dislocation Core Energy

7. Interaction of 1/3&lt

112‾0&gt

(0001) Edge Dislocations with Point Defect Clusters Created in Displacement

Cascades in α-Zr

7.1. Interaction with Triangular SIA Cluster in Basal Plane

7.2. Interaction with Irregular 3D SIA Cluster

7.3. Interaction with Prismatic Vacancy Loop

7.4. Interaction with Pyramid Vacancy Cluster

8. Interaction of 1/3&lt

[112‾0](11‾00)} Edge Dislocations with Point Defect Clusters Found in Collision

Cascades in α-Zirconium

8.1. Interaction with Triangular SIA Cluster in Basal Plane

8.2. Interaction with Irregular 3D SIA Point Defect Cluster

8.3. Interaction with SIA Dislocation Loops.

9. Summary

Index.

Notes:

Description based upon print version of record.

Includes bibliographical references and index.

Description based on print version record.

ISBN:

1-62081-968-6

OCLC:

839301781