"Atomic Resolution Imaging of Black Spot Defects in Ion Irradiated Silicon Carbide" Li He, Hao Jiang, Yizhang Zhai, Cheng Liu, Izabela Szlufarska, Beata Tyburska-Puschel, Kumar Sridharan, Paul Voyles, Microscopy and Microanalysis Vol. 21 2015 1337-1338 Link | ||
"Effect of carbon ion irradiation on Ag diffusion in SiC"
Tyler Gerczak, bin leng, Kumar Sridharan, Izabela Szlufarska, Hyunseok Ko, Jie Deng, Andrew Giordani, Jerry Hunter, Dane Morgan,
Journal of Nuclear Materials
Vol. 471
2017
220-232
Link
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. |
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"Evolution of small defect clusters in ion-irradiated 3C-SiC: Combined cluster dynamics modeling and experimental study" Cheng Liu, Li He, Yizhang Zhai, Beata Tyburska-Puschel, Paul Voyles, Kumar Sridharan, Dane Morgan, Izabela Szlufarska, Acta Materialia Vol. 125 2017 377-389 Link | ||
"High-Resolution Scanning Transmission Electron Microscopy Study of Black Spot Defects in Ion Irradiated Silicon Carbide" Li He, Yizhang Zhai, Cheng Liu, Chao Jiang, Izabela Szlufarska, Beata Tyburska-Puschel, Kumar Sridharan, Paul Voyles, Microscopy and Microanalysis Vol. 20 2014 1824-1825 Link | ||
"Radiation-induced mobility of small defect clusters in covalent materials" Hao Jiang, Li He, Dane Morgan, Paul Voyles, Izabela Szlufarska, Physical Review B Vol. 94 2016 024107 Link | ||
"Size distribution of black spot defects and their contribution to swelling in irradiated SiC" Beata Tyburska-Puschel, Yizhang Zhai, Li He, Cheng Liu, Alexandre Boulle, Paul Voyles, Izabela Szlufarska, Kumar Sridharan, Journal of Nuclear Materials Vol. 476 2016 132-139 Link | ||
"STEM-EDS Analysis of Fission Products in Neutron-Irradated TRISO Fuel Particles from AGR-1 Experiment"
bin leng, Kumar Sridharan, Izabela Szlufarska, Yaqiao Wu, Isabella van Rooyen,
Journal of Nuclear Materials
Vol. 475
2016
62-70
Link
Historic and recent post-irradiation-examination from the German AVR and Advanced Gas Reactor Fuel Development and Qualification Project have shown that 110 m Ag is released from intact tristructural isotropic (TRISO) fuel. Although TRISO fuel particle research has been performed over the last few decades, little is known about how metallic fission products are transported through the SiC layer, and it was not until March 2013 that Ag was first identified in the SiC layer of a neutron-irradiated TRISO fuel particle. The existence of Pd- and Ag-rich grain boundary precipitates, triple junction precipitates, and Pd nano-sized intragranular precipitates in neutron-irradiated TRISO particle coatings was investigated using Scanning Transmission Electron Microscopy and Energy Dispersive Spectroscopy analysis to obtain more information on the chemical composition of the fission product precipitates. A U-rich fission product honeycomb shape precipitate network was found near a micron-sized precipitate in a SiC grain about ∼5 μm from the SiC-inner pyrolytic carbon interlayer, indicating a possible intragranular transport path for uranium. A single Ag-Pd nano-sized precipitate was found inside a SiC grain, and this is the first research showing such finding in irradiated SiC. This finding may possibly suggest a possible Pd-assisted intragranular transport mechanism for Ag and may be related to void or dislocation networks inside SiC grains. Preliminary semi-quantitative analysis indicated the micron-sized precipitates to be Pd2Si2U with carbon existing inside these precipitates. However, the results of such analysis for nano-sized precipitates may be influenced by the SiC matrix. The results reported in this paper confirm the co-existence of Cd with Ag in triple points reported previously. |
Investigation of Silver Grain Boundary Diffusion in Irradiated Silicon Carbide - FY 2013 RTE Solicitation, #393
Microstructural and Irradiation Effects on Ag and Cs Diffusion in CVD-SiC - FY 2010 RTE Solicitation, #281
STEM/LEAP Study of Fission Product Transportation in Neutron Irradiated TRISO Fuel Particles - FY 2013 RTE Solicitation, #412
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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