Abstract
Transport of Ag fission product through the silicon-carbide (SiC) diffusion barrier layer in TRISO fuel particles is of considerable interest given the application of this fuel type in high temperature gas-cooled reactor (HTGR) and other future reactor concepts. The reactor experiments indicate that radiation may play an important role in release of Ag; however so far the isolated effect of radiation on Ag diffusion has not been investigated in controlled laboratory experiments. In this study, we investigate the diffusion couples of Ag and polycrystalline 3C-SiC, as well as Ag and single crystalline 4H-SiC samples before and after irradiation with C2+ ions. The diffusion couple samples were exposed to temperatures of 1500°C, 1535°C, and 1569°C, and the ensuing diffusion profiles were analyzed by secondary ion mass spectrometry (SIMS). Diffusion coefficients calculated from these measurements indicate that Ag diffusion was greatly enhanced by carbon irradiation due to a combined effect of radiation damage on diffusion and the presence of grain boundaries in polycrystalline SiC samples.
Original language | English |
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Pages (from-to) | 220-232 |
Number of pages | 13 |
Journal | Journal of Nuclear Materials |
Volume | 471 |
DOIs | |
State | Published - Apr 1 2016 |
Funding
This is 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 like to thank Dr. Beata Tyburska-Pueschel for helping with the carbon irradiation and also thank Dr. Ovidiu Toader for conducting the Ag implantation at the MIBL.
Funders | Funder number |
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U.S. Department of Energy | DE-AC07-051D14517 |
Office of Nuclear Energy | |
Nuclear Energy University Program | 11-2988 |
Keywords
- Diffusion
- Radiation
- Silicon carbide
- Silver
- TRISO