ENGLISH

Ceramics in Nuclear and Alternative Energy Applications: Ceramic Engineering and Science Proceedings, Volume 27, Issue 5

Book information

ISBN
9780470080559, 9780470291344
DOI
10.1002/9780470291344
Language
english
Format
PDF
Filesize
4 MB (3950330 bytes)
Series
Ceramic Engineering and Science Proceedings
Pages
177\177
Orientation
yes
Scanned
yes
Time added
2013-08-01 04:00:00

Description

Content: Chapter 1 (GENIV) Next Generation Nuclear Power and Requirements for Standards, Codes and Data Bases for Ceramic Matrix Composites (pages 2–7): Michael G. Jenkins, Edgar Lara?Curzio and William E. WindesChapter 2 Determination of Promising Inert Matrix Fuel Compounds (pages 11–17): C. R. Stanek, J. A. Valdez, K. E. Sickafus, K. J. McClellan and R. W. GrimesChapter 3 Densification Mechanism and Microstructural Evolution of SiC Matrix in Nite Process (pages 19–27): Kazuya Shimoda, Joon?Soon Park, Tatsuya Hinoki and Akira KohyamaChapter 4 Optimization of Sintering Parameters for Nitride Transmutation Fuels (pages 29–38): John T. Dunwoody, Christopher R. Stanek, Kenneth J. McClellan, Stewart L. Voit, Thomas Hartmann, Kirk Wheeler, Manuel Parra and Pedro D. PeraltaChapter 5 Ceramics in Non?Thermal Plasma Discharges for Hydrogen Generation (pages 39–46): R. Vintila, G. Mendoza?Suarez, J. A. Kozinski and R. A. L. DrewChapter 6 Piezoelectric Ceramic Fiber Composites for Energy Harvesting to Power Electronic Components (pages 47–54): Richard Cass, Farhad Mohammadi and Stephen LeschinChapter 7 Design Factor Using a SiC/SiC Composites for Core Component of Gas Cooled Fast Reactor. I. Hoop Stress (pages 55–63): Jae?Kwang Lee and Masayuki NaganumaChapter 8 Characterisations of Ti3SiC2 as Candidate for the Structural Materials of High Temperature Reactors (pages 65–76): Fabienne Audubert, Guillaume Abrivard and Christophe TallaronChapter 9 Influence of Specimen Type and Loading Configuration on the Fracture Strength of SiC Layer in Coated Particle Fuel (pages 77–87): T. S. Byun, S. G. Hong, L. L. Snead and Y. KatohChapter 10 Investigation of Aluminides as Potential Matrix Materials for Inert Matrix Nuclear Fuels (pages 89–99): Damn D. Byler, Kenneth J. McClellan, James A. Valdez, Pedro D. Peralta and Kirk WheelerChapter 11 Fluidised Bed Chemical Vapour Deposition of Pyrolytic Carbon (pages 101–114): E. Lopez Honorato, P. Xiao, G. Marsh and T. AbramChapter 12 Strength Testing of Monolithic and Duplex Silicon Carbide Cylinders in Support of Use as Nuclear Fuel Cladding (pages 117–125): Denwood F. Ross and William R. HendrichChapter 13 Subcritical Crack Growth in Hi?Nicalon Types Fiber CV1?S1C/S1C Composites (pages 127–144): Charles H. HenagerChapter 14 Electrical Conductivity of Proton Conductive Ceramics Under Reactor Irradiation (pages 145–156): Tatsuo Shikama, Bun Tsuchiya, Shinji Nagata and Kentaro TohChapter 15 The Effects of Irradiation?Induced Swelling of Constituents on Mechanical Properties of Advanced SiC/SiC Composites (pages 157–167): Kazumi Ozawa, Takashi Nozawa, Tatsuya Hinoki and Akira KohyamaChapter 16 Behaviors of Radioluminescence of Optical Ceramics for Nuclear Applications (pages 169–178): T. Shikama, S. Nagata, K. Toh, B. Tsuchiya and A. Inouye

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