Current status and critical issues for development of SiC composites for fusion applications
Y. Katoha, , , L.L. Sneada, C.H. Henager Jr.b, A. Hasegawac, A. Kohyamad, B. Riccardie and H. Hegemanf
aOak Ridge National Laboratory, Materials Science and Technology Division, P.O. Box 2008, MS-6138, Oak Ridge, TN 37831-6138, USA bPacific Northwest National Laboratory, P.O. Box 999, Richland, WA 99352, USA cDepartment of Quantum Science and Energy Engineering, Tohoku University, Sendai 980-8579, Japan dInstitute of Advanced Energy, Kyoto University, Kyoto 611-0011, Japan eEFDA CSU Garching, Boltzmannstr. 2, 85748 Garching bei München, Germany fNRG, P.O. Box 25, 1755 ZG Petten, The Netherlands
Available online 19 March 2007.
Abstract
Silicon carbide (SiC)-based ceramic composites have been studied for fusion applications for more than a decade. The potential for these materials have been widely discussed and is now understood to be (1) the ability to operate in temperature regimes much higher than for metallic alloys, (2) an inherent low level of long-lived radioisotopes that reduces the radiological burden of the structure, and (3) perceived tolerance against neutron irradiation up to high temperatures. This paper reviews the recent progress in development, characterization, and irradiation effect studies for SiC composites for fusion energy applications. It also makes the case that SiC composites are progressing from the stage of potential viability and proof-of-principle to one where they are ready for system demonstration, i.e., for flow channel inserts in Pb–Li blankets. Finally, remaining general and specific technical issues for SiC composite development for fusion applications are identified.
Journal of Nuclear Materials Volumes 367-370, Part 1, 1 August 2007, Pages 659-671 Proceedings of the Twelfth International Conference on Fusion Reactor Materials (ICFRM-12), Proceedings of the Twelfth International Conference on Fusion Reactor Materials (ICFRM-12)
