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Study mapping U-10Zr porosity informs metallic fuel design
Researchers at Idaho National Laboratory and the Massachusetts Institute of Technology have conducted a three-dimensional study of irradiated U-10Zr—uranium alloyed with 10 percent zirconium—across key radial regions, providing new insights into how the material swells, transfers heat, and interacts with the fuel cladding.
U-10Zr was extensively tested in historical sodium-cooled fast reactors and is now attracting attention for use in next-generation advanced reactors.
H. T. Lee, Y. Ohtsuka, Y. Ueda, K. Sugiyama, E. Markina, N. Yoshida
Fusion Science and Technology | Volume 63 | Number 1 | May 2013 | Pages 233-236
doi.org/10.13182/FST13-A16913
Articles are hosted by Taylor and Francis Online.
The structure and concentration distribution of He, H, and D in the ion implanted zone following simultaneous He-D irradiation in W was characterized. A shift in He bubble size from nanometer to tens of nanometers was observed between 800 K < T < 1000 K. The bubble field was found to extend to depths of 30-40 nm with mean concentrations of 4-5 at.%.. An order of magnitude increase in He trapping was observed at 800 K when the ion energy was increased from 0.3 to 1.0 keV. Depth profiles of the trapped D at 500 K indicatea marked decrease in the trapped amount coinciding with the He bubble layer. Conversely, enrichment in hydrogen concentration was observed. One hydrogen atom was found to trap in ratio with ~6 He atoms. Such preferential trapping of hydrogen appears to be an important process in the reduction of D diffusion into W due to He effects.