Ceramics in Nuclear and Alternative Energy

This volume focuses on recent developments and advances of ceramics and ceramic matrix composites for use in fission and fusion reactors, nuclear fuels and alternative energy applications. With the continued increasing demands for energy, nuclear energy has experienced a renewed interest. Recent developments associated with advanced fuel cycles have resulted in new research efforts on nuclear fuel materials. The effects of radiation on the properties of ceramics and ceramic matrix composites are also addressed.

Andrew A. Wereszczak received his Ph.D. in Materials Science & Engineering from the University of Delaware in 1992, and while his research is varied, the study and interpretation of the relationship between mechanical properties and microstructure (of monolithic ceramics, structural materials, and electronic materials) are common denominators. Micromechanical characterization of structural and armor ceramics using instrumented static and dynamic indentation (e.g., Hertzian) with acoustic emission analysis, and adapting those measured performances and damage mechanism analyses to strength, rolling contact fatigue, wear, machining, and ballistic performances is a primary objective.

Additionally, ceramic strength and fatigue testing, ceramic fractographical and flaw population analyses, Weibull analysis strength-size-scaling, and probabilistic life prediction and design of structural ceramic components constitutive another primary research objective. In support of all these efforts, both conventional and microstructural-level finite element stress analyses and microstructure characterization are performed. He is the author or co-author of over 100 technical publications and has given over 80 presentations, and is the co-developer of µ-FEA software.

Preface
Introduction
Irradiation Effects in Ceramics.(GenlV)
Next Generation Nuclear Power and Requirements for Standards, Codes and Data Bases for Ceramic Matrix Composites
Determination of Promising Inert Matrix Fuel Compounds
Densification Mechanism and Microstructural Evolution of Sic Matrix in NlTE Process
Optimization of Sintering Parameters for Nitride Transmutation Fuels
Ceramics in Non-Thermal Plasma Discharges for Hydrogen Generation
Piezoelectric Ceramic Fiber Composites for Energy Harvesting to Power Electronic Components
Design Factor Using a SiC/SiC Composites for Core Component of Gas Cooled Fast Reactor. I: Hoop Stress
Characterizations of Ti,SiC, as Candidate for the Structural Materials of High Temperature Reactors
Influence of Specimen Type and Loading Configuration on the Fracture Strength of Sic Layer in Coated Particle Fuel
Investigation of Aluminides as Potential Matrix Materials for Inert Matrix Nuclear Fuels
Fluidised Bed Chemical Vapour Deposition of Pyrolytic Carbon
Ceramics for Advanced Nuclear and Alternative Energy Applications
Strength Testing of Monolithic and Duplex Silicon Carbide Cylinders in Support of Use as Nuclear Fuel Cladding
Subcritical Crack Growth in Hi-Nicalon Type-S Fiber CVI-SiC/SiC Composites
Electrical Conductivity of Proton Conductive Ceramics Under Reactor Irradiation
The Effects of Irradiation-Induced Swelling of Constituents on Mechanical Properties of Advanced SiCISiC Composites
Behaviors of Radioluminescence of Optical Ceramics for Nuclear Applications
Author Index
Table of Contents provided by Publisher. All Rights Reserved.

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Ceramics in Nuclear and Alternative Energy Applications, Volume 27, Issue 5

Summary

Author Biography

Table of Contents

Supplemental Materials