Experimental assessment of antimony (Sb) in pure uranium for immobilizing fission product lanthanides

Zhuo, Weiqian; Xie, Yi; Benson, Michael T.; Wu, Huali; Mariani, Robert D.; Zhang, Jinsuo

doi:10.1016/j.jnucmat.2020.152135

Title: Experimental assessment of antimony (Sb) in pure uranium for immobilizing fission product lanthanides

Journal Article · Mon Apr 06 00:00:00 EDT 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152135· OSTI ID:1608935

^[1]; Xie, Yi ^[2]; Benson, Michael T. ^[2]; Wu, Huali ^[1]; Mariani, Robert D. ^[2]; Zhang, Jinsuo ^[1]

Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

The use of fuel additives is one of the concepts to mitigate fuel cladding chemical interaction (FCCI) for metallic fuel because fission product lanthanides are expected to be immobilized by the additive. Antimony (Sb) has been discovered to be a good candidate in UZr fuel. The present study focuses on its mechanism for immobilization in pure uranium, U–4Sb alloy was fabricated to understand the Sb behavior, while U–4Sb–4Ce was fabricated to simulate the case when lanthanides are generated. Both of the as-cast and annealed samples were characterized by scanning electron microscope (SEM) and energy dispersive spectrometer (EDS). U–Sb precipitates are formed in U–4Sb alloy, while U–Sb and Ce–Sb were found in U–4Sb–4Ce alloy, thermal exposure does not change the Sb-precipitation morphologies or chemical composition. Furthermore, diffusion couple tests between those alloys and cladding materials (Fe or HT9) under 650 °C for 500 h were performed and analyzed using SEM/EDS. Diffusion couple tests demonstrate the reaction between cladding and uranium, while no reaction between Sb-precipitations and cladding materials was found.

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Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States); The Ohio State Univ., Columbus, OH (United States)

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

Grant/Contract Number:: AC07-05ID14517; NE0008574

OSTI ID:: 1608935

Alternate ID(s):: OSTI ID: 1615384

Journal Information:: Journal of Nuclear Materials, Vol. 534, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 1 work

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