Dilute condition corrosion behavior of glass-ceramic waste form

Journal Article · 01 December 2016 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2016.08.002 · OSTI ID:1380038

Crum, Jarrod V.; Neeway, James J. ; Riley, Brian J.; Zhu, Zihua; Olszta, Matthew J.; Tang, Ming

Borosilicate glass-ceramics are being developed to immobilize high-level waste generated by aqueous reprocessing into a stable waste form. The corrosion behavior of this multiphase waste form is expected to be complicated by multiple phases and crystal-glass interfaces. A modified single-pass flow-through test was performed on polished monolithic coupons at a neutral pH (25 °C) and 90 °C for 33 d. The measured glass corrosion rates by micro analysis in the samples ranged from 0.019 to 0.29 g m^-2 d^-1 at a flow rate per surface area = 1.73 × 10^-6 m s^-1. The crystal phases (oxyapatite and Ca-rich powellite) corroded below quantifiable rates, by micro analysis. While, Ba-rich powellite corroded considerably in O10 sample. The corrosion rates of C1 and its replicate C20 were elevated an order of magnitude by mechanical stresses at crystal-glass interface caused by thermal expansion mismatch during cooling and unique morphology (oxyapatite clustering).

• Research Organization: Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Biological and Environmental Research (BER)
• Grant/Contract Number: AC0576RL01830
• OSTI ID: 1380038
• Alternate ID(s): OSTI ID: 1335865
• Journal Information: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Vol. 482 Journal Issue: C; ISSN 0022-3115
• Publisher: ElsevierCopyright Statement
• Country of Publication: Netherlands
• Language: English