Browse > Article
http://dx.doi.org/10.4191/KCERS.2005.42.8.575

Fabrication and Ion Irradiation Characteristics of SiC-Based Ceramics for Advanced Nuclear Energy Systems  

Kim, Weon-Ju (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute)
Kang, Seok-Min (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute)
Park, Kyeong-Hwan (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute, Institute of Advanced Energy, Kyoto University)
Kohyama Akira (Institute of Advanced Energy, Kyoto University)
Ryu, Woo-Seog (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute)
Park, Ji-Yeon (Division of Nuclear Materials Technology and Development, Korea Atomic Energy Research Institute)
Publication Information
Journal of the Korean Ceramic Society / v.42, no.8, 2005 , pp. 575-581 More about this Journal
Abstract
SiC-based ceramics are considered as candidate materials for the advanced nuclear energy systems such as the generation IV reactors and the fusion reactors due to their excellent high-temperature strength and irradiation resistance. The advanced nuclear energy systems and their main components adopting ceramic composites were briefly reviewed. A novel fabrication method of $SiC_f/SiC$ composites by introducing SiC whiskers was also described. In addition, the charged-particle irradiation ($Si^{2+}$ and $H^{+}$ ion) into CVD SiC was carried out to simulate the severe environments of the advanced nuclear reactors. SiC whiskers grown in the fiber preform increased the matrix infiltration rate by more than $60\%$ compared to the conventional CVI process. The highly crystalline and pure SiC showed little degradation in hardness and elastic modulus up to a damage level of 10 dpa at $1000^{\circ}C$.
Keywords
Advanced nuclear reactors; CVI process; Ion irradiation;
Citations & Related Records
연도 인용수 순위
  • Reference
1 W. Yang, T. Noda, H. Araki, J. Yu, and A. Kohyama, ' Mechanical Properties of Several Advanced Tyranno-SA Fiber-Reinforced CVI-SiC Matrix Composites,' Mater. Sci. Eng. A, 345 28-35 (2003)   DOI   ScienceOn
2 K. H. Park, Y. Katoh, H. Kishimoto, and A. Kohyama, ' Evaluation of Dual-Ion Irradiated $\beta$-SiC by Means of Indentation Methods,' J. Nucl. Mater., 307-311 1187-90 (2002)   DOI   ScienceOn
3 M. C. Osborne, J. C. Hay, L. L. Snead, and D. Steiner, 'Mechanical-and Physical-Property Changes of Neutron-Irradiated Chemical-Vapor-Deposited Silicon Carbide,' J. Am. Ceram. Soc., 82 [9] 2490-96 (1999)   DOI
4 L. L. Snead and J. C. Hay, 'Neutron Irradiation Induced Amorphization of Silicon Carbide,' J. Nucl. Mater., 273 213-20 (1992)   DOI   ScienceOn
5 T. Iseki, T. Yano, and H. Miyazaki, 'X-Ray Line Broadening in Neutron Irradiated Silicon Carbide,' J. Nucl. Mater., 191-194 588-91 (1992)   DOI   ScienceOn
6 J. F. Ziegler, J. P. Biersack, and U. Littmark, 'The Stopping and Range of Ions in Solids,' Vol. 1, pp. 233-63, Pergamon Press, New York (1985)
7 W. C. Oliver and G. M. Pharr, 'An Improved Technique for Determining Hardness and Elastic Modulus Using Load and Displacement Sensing Indentation Experiments,' J. Mater. Res., 7 [6] 1564-83 (1992)   DOI
8 S. M. Kang, J. Y. Park, W.-J. Kim, S. G. Yoon, and W. S. Ryu, 'Densification of $SiC_{f}$/SiC Composite by the Multi-Step of Whisker Growing and Matrix Filling,' J. Nucl. Mater., 329-333 530-33 (2004)   DOI   ScienceOn
9 A. Kohyama, Y. Katoh, M. Ando, and K. Jimbo, 'A New Multiple Beams Material Interaction Research Facility for Radiation Damage Studies in Fusion Materials,' Fus. Eng. Des., 51-52 789-95 (2000)   DOI   ScienceOn
10 W. Schenk and H. Nabielek, 'High-Temperature Reactor Fuel Fission Product Release and Distribution at 1600 and $1800^{\circ}C$,' Nucl. Tech., 96 323-36 (1991)   DOI
11 Y. Katoh and L. L. Snead, 'Strength and Elastic Modulus of Neutron-Irradiated Cubic Silicon Carbide'; pp. 33-43 in Fusion Materials Semiannual Progress Report, DOE/ER-0313/36, 2004
12 K. H. Park, S. Ikeda, T. Hinoki, and A. Kohyama, 'Influence of Ion Irradiation on the Mechanical and Fracture Behavior of SiC for Core Component in Advanced Nuclear Reactors,' Paper 5468 in Proceedings of ICAPP '05, Seoul, Korea, 2005
13 Annual Book of ASTM Standard, 'Neutron Radiation Damage Simulation by Charged-Particle Irradiation,' ASTM, 12.02, E521-83, 233-58
14 Generation IV Nuclear Energy Systems Ten-Year Program Plan, US DOE-NE, March 2005, http://gen-iv.ne.doe.gov/documents/gen _iv_program_plan(public).pdf
15 L. Giancarli, H. Golfier, S. Nishio, R. Raffray, C. Wong, and R. Yamada, 'Progress in Blanket Designs Using $SiC_{f}$/SiC Composites,' Fus. Eng. Des., 61-62 307-18 (2002)   DOI   ScienceOn
16 G. Baccaglini et al., 'Very High Temperature Reactor (VHTR), Survey of Materials Research and Development Needs to Support Early Deployment,' INEEL/EXT-03- 00141, Idaho National Laboratory, Idaho Falls, 2003
17 W Hoffelner, 'High Temperature Materials-The Challenge for Future Advanced Gas Cooled Reactors,' pp. 380-87 in Proceedings of ICAPP '04, Pittsburgh, USA, 2004