Effect of sucrose on the oxidation-reduction conditions and retention of rhenium during vitrification of low-activity waste

Khawand, John; Kloužek, Jaroslav; Vernerová, Miroslava; Cincibusová, Petra; Hrma, Pavel; Kruger, Albert A.; Pokorný, Richard

doi:10.1016/j.jnucmat.2022.154155

Effect of sucrose on the oxidation-reduction conditions and retention of rhenium during vitrification of low-activity waste

Journal Article · Thu Nov 17 00:00:00 EST 2022 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2022.154155· OSTI ID:2424439

Khawand, John ^[1]; ^[2]; ^[2]; Cincibusová, Petra ^[2]; Hrma, Pavel ^[3]; ^[3]; ^[2]

University of Chemistry and Technology Prague (Czech Republic)
University of Chemistry and Technology Prague (Czech Republic); Institute of Rock Structure and Mechanics of the Czech Academy of Sciences, Prague (Czech Republic)
U.S. Department of Energy, Richland, WA (United States)

Technetium speciation and solubility during nuclear waste vitrification are affected by oxygen partial pressure in the melt. Thus, reducing agents such as sucrose, which are routinely added to nuclear waste feeds to repress foaming, can significantly affect the volatilization of Tc and increase its retention in glass. Using Re as a surrogate for Tc, we measured the effect of sucrose addition to two low-activity waste melter feeds on the Re retention, oxygen partial pressure, and iron redox as functions of temperature. As expected, Re retention in glass increased as the sucrose content increased. Furthermore, this is attributed to sucrose reaction with nitrates and nitrites in the feed. Destruction of nitrates and nitrites reduces the salt phase fraction and thus likely promotes Re diffusion into the glass-forming melt. In agreement with available literature, we discuss that a modest increase in the sucrose content (compared to current practice) can significantly improve the Tc retention without reducing Fe²⁺ to metal.

View Accepted Manuscript (DOE)

Research Organization:: USDOE Office of River Protection (ORP), Richland, WA (United States)

Sponsoring Organization:: USDOE

OSTI ID:: 2424439

Alternate ID(s):: OSTI ID: 1899232

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 573; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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