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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.
C. Parisi, E. Negrenti, M. Pecchia
Nuclear Science and Engineering | Volume 178 | Number 4 | December 2014 | Pages 524-538
Technical Paper | doi.org/10.13182/NSE14-40
Articles are hosted by Taylor and Francis Online.
This paper summarizes the evaluation for core I and core VIII of the Babcock & Wilcox Spectral Shift Control Reactor critical experiment program. The Spectral Shift Control Reactor concept, moderated and cooled by a variable mixture of heavy and light water, envisaged changing of the thermal neutron spectrum during the operation to encourage breeding and to sustain the core criticality. Core I contained 484 fuel rods with 4% UO2 fuel in light water while core VIII contained 2188 fuel rods with 93% enriched UO2-ThO2 fuel in a moderator mixture of heavy and light water. For core I, the criticality experiment and measurements of the thermal disadvantage factor were evaluated. For core VIII, only the criticality experiment was evaluated. For both cores, experimental uncertainties were determined confirming the good level of accuracy achieved by the experimentalists. Based on the experimental configurations, benchmarks were proposed, and their biases were determined.