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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.
Deokjung Lee, Joel Rhodes, Kord Smith
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 79-86
Technical Paper | doi.org/10.13182/NSE12-20
Articles are hosted by Taylor and Francis Online.
The huge absorption cross sections of 155Gd and 157Gd cause strong spatial shielding effects in Gd-bearing pins. A high-order depletion method has been developed for CASMO-5 to address the issue of the small depletion steps typically required for Gd-bearing fuel assemblies. In this method, the microscopic absorption reaction rates of gadolinium isotopes are assumed to be quadratic functions of the number density of 155Gd rather than the constant reaction rate assumption in the conventional predictor-corrector (PC) method. This quadratic function assumption models the variations of the spatial shielding effects over the depletion step and therefore improves the accuracy of depletion calculations with a negligible amount of calculation time increase. With this new method, a depletion step size four times larger than the step size used in a conventional PC method can be used for Gd-bearing assemblies without compromising accuracy.