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The D&D of SM-1A
With the recent mobilization at the site of the former SM-1A nuclear power plant at Fort Greely, Alaska, the Radiological Health Physics Regional Center of Expertise, located at the U.S. Army Corps of Engineers’ Baltimore District, began its work toward the decommissioning and dismantlement of its third nuclear power plant, this time located just 175 miles south of the Arctic Circle.
Dhanpat Rai, Janet A. Schramke, Dean A. Moore, Gary L. McVay
Nuclear Technology | Volume 75 | Number 3 | December 1986 | Pages 350-355
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33847
Articles are hosted by Taylor and Francis Online.
Americium-doped glass (0.053 wt% 241Am) was contacted with dilute salt solutions (0.001 MNaClO4), pH buffers, Permian Basin brine (PBB1), and tentimes-diluted PBB1 to determine the aqueous americium concentrations that can be expected in equilibrium with this glass. The americium concentrations in all of these solutions were similar and decreased with increasing pH; americium concentrations decreased to the detection limit (∼10−11.6M) at a pH value of ∼7 and remained at or near the detection limit at pH values >7. Americium concentrations in glass suspensions with pH >5 were found to be controlled by the dissolution of an americium-solid. The value of the log of the equilibrium constant for the solubility of this americium-solid (Am-solid+3H+ = Am3++ H3-solid) was determined to be ∼10.3. The americium-solid is found to effectively control aqueous americium to very low concentrations under slightly acidic to alkaline conditions. The high ionic strength and the high Cl−concentrations in brine are found not to measurably affect the americium-solid solubility.