SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln

Benson, Michael T.; King, James A.; Mariani, Robert D.; Marshall, M. Craig

doi:10.1016/j.jnucmat.2017.07.057

SEM characterization of two advanced fuel alloys: U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln

Journal Article · Mon Jul 31 00:00:00 EDT 2017 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2017.07.057· OSTI ID:1474100

^[1]; ^[1]; Mariani, Robert D. ^[1]; Marshall, M. Craig ^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)

Tin is being investigated as a potential additive to metallic fuel to control fuel-cladding chemical interaction (FCCI). A primary cause of FCCI is the lanthanide fission products moving to the fuel periphery and interacting with the cladding. This interaction will lead to wastage of the cladding and eventually to a cladding breach. The current paper is a scanning electron microscopy (SEM) characterization of as-cast and annealed U-10Zr-4.3Sn and U-10Zr-4.3Sn-4.7Ln, where Ln = 53Nd-25Ce-16Pr-6La. Finally, the present study shows that tin preferentially binds the lanthanides, which will prevent lanthanide migration and interaction with the cladding.

View Accepted Manuscript (DOE)

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE; USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1474100

Alternate ID(s):: OSTI ID: 1495577

Report Number(s):: INL/JOU-17-42347-Rev000

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 494; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Evaluation of Tellurium as a Fuel Additive in Neodymium-Containing U-Zr Metallic Fuel Jerred, Nathan D.; Khanal, Rabi; Benson, Michael T. Scientific Reports, Vol. 9, Issue 1 https://doi.org/10.1038/s41598-019-51852-z	journal	November 2019

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