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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.
Govind Kumar Mishra, M. Sakthivel, S. L. N. Swamy, K. Madhusoodanan
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 96-102
Technical Note | doi.org/10.13182/NSE10-74
Articles are hosted by Taylor and Francis Online.
The 500-MW(electric)-capacity Prototype Fast Breeder Reactor (PFBR) using sodium as a coolant is under construction at Indira Gandhi Centre for Atomic Research, Kalpakkam, India. Instrumentation for the measurement of physical and chemical characteristics of liquid sodium in reactor coolant and related applications is described. Various properties of liquid sodium are used for measurement of flow, temperature, level, and leaks. Temperature-dependent solubility of impurities in the liquid sodium is a basis principle of instruments for monitoring the general purity and the specific impurities of oxygen, hydrogen, and carbon. This technical note deals with the properties of sodium that are relevant to successful sodium instrumentation used for PFBR.