Abstract
SiC is a promising material for nuclear applications and is a critical component in the construction of tristructural isotropic (TRISO) fuel. A primary issue with TRISO fuel operation is the observed release of 110mAg from intact fuel particles. The release of Ag has prompted research efforts to directly measure the transport mechanism of Ag in bulk SiC. Recent experimental efforts have focused primarily on Ag ion implantation designs. The effect of the thermal exposure system on the ion implantation surface has been investigated. Results indicate the utilization of a mated sample geometry and the establishment of a static thermal exposure environment is critical to maintaining an intact surface for diffusion analysis. The nature of the implantation surface and its potential role in Ag diffusion analysis are discussed.
Original language | English |
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Pages (from-to) | 281-286 |
Number of pages | 6 |
Journal | Journal of Nuclear Materials |
Volume | 456 |
DOIs | |
State | Published - Jan 2015 |
Externally published | Yes |
Funding
A portion of this research utilized National Science Foundation (NSF) supported shared facilities at the University of Wisconsin. This work supported by the US DOE, Office of Nuclear Energy Nuclear Energy University Program (NEUP) , Award no. 11-2988 and by the US DOE, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07-051D14517, as part of an ATR-NSUF experiment. The authors would also like to thank Dr. Ovidiu Toader for conducting the Ag implantations at the MIBL and Dr. Jerry Hunter for conducting the SIMS analysis at ICTAS at Va. Tech.