Radioactive waste immobilization of Hanford sludge in magnesium potassium phosphate ceramic forms

This paper evaluates immobilization of Hanford K-Basin tank sludge in magnesium potassium phosphate ceramic forms. The waste forms were produced using two simulated non-radioactive sludge streams, each with distinct characteristics and composition. Ceramicrete with wollastonite as filler was used as...

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Bibliographic Details
Published in:	Progress in nuclear energy (New series) Vol. 152; no. C; p. 104315
Main Authors:	Sayenko, S.Yu, Shkuropatenko, V.A., Pylypenko, O.V., Karsim, S.O., Zykova, A.V., Kutnii, D.V., Wagh, Arun S.
Format:	Journal Article
Language:	English
Published:	United States Elsevier Ltd 01-10-2022 Elsevier
Subjects:	Immobilization Magnesium potassium phosphate Nuclear Science & Technology Radioactive K-Basin waste Radioactive K-Basin waste Immobilization Magnesium potassium phosphate
Online Access:	Get full text
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Summary:	This paper evaluates immobilization of Hanford K-Basin tank sludge in magnesium potassium phosphate ceramic forms. The waste forms were produced using two simulated non-radioactive sludge streams, each with distinct characteristics and composition. Ceramicrete with wollastonite as filler was used as the matrix for this purpose. The resulting waste forms were tested for their mechanical properties, radiation stability, and leaching resistance. In another series of tests, the samples were vitrified in borosilicate glass and glass waste forms were produced. The Product Consistency Test, the American Nuclear Society's ANS 16.1 test, and the Toxicity Characteristic Leaching Procedure, which are used to develop waste acceptance criteria in the United States for permanent storage of treated waste, were used for evaluation of the leaching resistance of all waste forms. [Display omitted] •Ceramicrete technology is evaluated for immobilizing Hanford K-Basin waste using simulated waste streams that represent actual waste with high level of fission products and actinides in it.•Both room-temperature immobilization technique as well as high-temperature vitrification of the immobilized waste to reduce its volume are employed and their performance is evaluated.•The waste forms were irradiated with 108 rads of γ- and 1010 rads of β-radiation and the effect of internal radiation on the durability is analyzed.•Mechanical properties and leaching results show that both room temperature stabilized and vitrified waste forms perform equally well within the required disposal limits.
Bibliography:	AC02-06CH11357 USDOE
ISSN:	0149-1970
DOI:	10.1016/j.pnucene.2022.104315