Glass formulation and lab-scale testing of glasses designed for in-can Melter and in-container Vitrification of high-assay low-enriched uranium aqueous polishing Raffinate waste

Oshiro, Jared M.; Gervasio, Vivianaluxa; Crum, Jarrod V.; Riley, Brian J.; Reiser, Joelle T.; Snyder, Michelle Valenta; Dixon, Derek R.; Nienhuis, Emily T.; Droubay, Timothy C.; Vienna, John D.

doi:10.1016/j.jnucmat.2024.155102

Title: Glass formulation and lab-scale testing of glasses designed for in-can Melter and in-container Vitrification of high-assay low-enriched uranium aqueous polishing Raffinate waste

Journal Article · 15 April 2024 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2024.155102 · OSTI ID:2441218

^[1];

^[1]; Crum, Jarrod V. ^[1];

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^[1]; Snyder, Michelle Valenta ^[1]; Dixon, Derek R. ^[1];

^[1]; Droubay, Timothy C. ^[1];

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Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

Glasses were designed for processing a nuclear waste from aqueous polishing of high-assay low-enriched uranium using either In-Can Melter (ICM) or GeoMelt® In-Container Vitrification™ (ICV) technologies, which operate at temperatures of T_p ≤ 1100 °C and T_p ≤ 1450 °C, respectively. Due to the different operating conditions, the melt and glass properties were optimized differently for each technology. Each glass was designed to optimize for maximum waste loading while simultaneously satisfying processing (e.g., crystallization, viscosity, and conductivity) and product quality (e.g., durability, hazard characteristic, and crystal content) constraints. Here, the raffinate waste contains high nitric acid (4 M) and low total solids (9 g·L^-1) concentrations. Feed preparation processes were tested to facilitate concentration and nitrate destruction/removal while controlling redox of the melter feed. A successful feed process including sugar addition and spray-drying was performed to generate an adequate melter feed for ICV processing.

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Research Organization:: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)

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

Grant/Contract Number:: AC05-76RL01830

OSTI ID:: 2441218

Report Number(s):: PNNL-SA--193734

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 597; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Title: Glass formulation and lab-scale testing of glasses designed for in-can Melter and in-container Vitrification of high-assay low-enriched uranium aqueous polishing Raffinate waste

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