Properties of radioactive wastes and waste containers. Quarterly progress report, April-June 1981

Technical Report · Sun Nov 01 04:00:00 EST 1981

DOI:https://doi.org/10.2172/5361625· OSTI ID:5361625

Morcos, N.; Weiss, A. J.

An empirical relationship has been developed to estimate the cumulative fractional releases of /sup 137/Cs from simulated waste forms as a function of leaching time and the geometric surface-to-volume ratios. Data from an ongoing leaching study were used. The simulated waste forms consisted of organic cation exchange resins solidified in Portland I cement at a waste-to-cement ratio of 0.6 and water-to-cement ratio of 0.4. The nominal specimen dimensions were: 1-inch diameter x 1-inch high, 2-inch diameter x 2-inch high, 2-inch diameter x 4-inch high, 3-inch diameter x 3-inch high, 6-inch diameter x 6-inch high, 6-inch diameter x 12-inch high, and 12-inch diameter x 12-inch high. The waste forms were leached in deionized water using a modified IAEA leaching procedure. A study designed to evalate the leachability of /sup 137/Cs, /sup 85/Sr, and /sup 60/Co from simulated boric acid waste solidified in Portland III cement and to measure the compressive strength of the ensuing waste forms before and after leaching was concluded. Leaching data extending over 229 days are presented. The simulated waste forms were leached in deionized water using a modified IAEA leaching procedure. The compressive strength of the specimens was measured initially and after their exposure to a leaching environment for 352 days.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5361625
• Report Number(s): NUREG/CR-2193-Vol.1-No.2; BNL-NUREG-51410-Vol.1-No.2; ON: DE82015212
• Country of Publication: United States
• Language: English

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