TY - GEN
T1 - Ceramic composites for near term reactor application
AU - Snead, Lance L.
AU - Katoh, Yutai
AU - Windes, William E.
AU - Shinavski, Robert J.
AU - Burchell, Timothy D.
PY - 2009
Y1 - 2009
N2 - Currently, two composites types are being developed for in-core application: carbon fiber carbon composite (CFC), and silicon carbide fiber composite (SiC/SiC.) Irradiation effects studies have been carried out over the past few decades yielding radiation-tolerant CFC's and a composite of SiC/SiC with no apparent degradation in mechanical properties to very high neutron exposure. While CFC's can be engineered with significantly higher thermal conductivity, and a slight advantage in manufacturability than SiC/SiC, they do have a neutron irradiation-limited lifetime. The SiC composite, while possessing lower thermal conductivity (especially following irradiation), appears to have mechanical properties insensitive to irradiation. Both materials are currently being produced to sizes much larger than that considered for nuclear application. In addition to materials aspects, results of programs focusing on practical aspects of deploying composites for near-term reactors will be discussed. In particular, significant progress has been made in the fabrication, testing, and qualification of composite gas-cooled reactor control rod sheaths and the ASTM standardization required for eventual qualification.
AB - Currently, two composites types are being developed for in-core application: carbon fiber carbon composite (CFC), and silicon carbide fiber composite (SiC/SiC.) Irradiation effects studies have been carried out over the past few decades yielding radiation-tolerant CFC's and a composite of SiC/SiC with no apparent degradation in mechanical properties to very high neutron exposure. While CFC's can be engineered with significantly higher thermal conductivity, and a slight advantage in manufacturability than SiC/SiC, they do have a neutron irradiation-limited lifetime. The SiC composite, while possessing lower thermal conductivity (especially following irradiation), appears to have mechanical properties insensitive to irradiation. Both materials are currently being produced to sizes much larger than that considered for nuclear application. In addition to materials aspects, results of programs focusing on practical aspects of deploying composites for near-term reactors will be discussed. In particular, significant progress has been made in the fabrication, testing, and qualification of composite gas-cooled reactor control rod sheaths and the ASTM standardization required for eventual qualification.
UR - http://www.scopus.com/inward/record.url?scp=70349931312&partnerID=8YFLogxK
M3 - Conference contribution
AN - SCOPUS:70349931312
SN - 9780791848548
T3 - 2008 Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008
SP - 1
EP - 10
BT - 2008 Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008
T2 - 2008 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008
Y2 - 28 September 2008 through 1 October 2008
ER -