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Sample Description. The sample used in this test was derived from an AN-107 archive sample. This material was collected and processed to remove cesium before its use for the BNFL project (Hendrickson 1997). It was collected as 45 grab samples in 125-mL bottles taken during January 1997. Approximately 5.4 L of in-tank material was transferred to the 222-S laboratory and 0.53 M sodium hydroxide was added to dilute the waste to 5 M sodium and adjust the free hydroxide concentration to "0.24M. Solids were separated from the supernatant by settling. The supematant was decanted and passed through small columns containing cesium-selective crystalline silicotitanate material. Analysis of the waste after cesium removal indicated the free hydroxide concentration to be 0.126 M. Following cesium removal, the sample was transfemed to the Pacific Northwest National Laboratory in five 1-L poly bottles where it has been stored in the Shielded Analytical Laboratory hot cells in the Radiochemical Processing Laboratory. As part of an effort to prepare feed for sulfate-removal tests, a subsample of the AN-1 07 archive sample was further treated to remove Sr/transuranic (TRU) components (Hallen et al. 2000) by precipitation. This activity involved adjusting the subsample to a hydroxide concentration of 0.8 M with the addition of 19 M NaOH. A solution of 1 M strontium nitrate was added to provide a Sr concentration of 0.05 M, and a solution of 1 M sodium permanganate was added to provide a permanganate concentration of 0.03 M. The precipitated solids were separated using a 0.45-micron dead-end filter. "The clarified liquid was used for the tests described in this report.

No abstract

DISCLAXMER

SummaryAn N-Reactor outer fuel element that had been stored underwater in the Hanford 100 Area K-West Basin was subjected to a combination of low-and high-temperature vacuum drying treatments. These studies are part of a series of tests being conducted by Pacific Northwest National Laboratory on the drying behavior of spent nuclear fuel elements removed from both the K-West and K-East Basins.The drying test series was designed to test fuel elements that ranged from intact to severely damaged. The fuel element discussed in this report was removed from K-West canister 0309M during the second fuel selection campaign, conducted in 1996, and has remained in wet storage in the Postirradiation Testing Laboratory (PTL, 327 Building) since that time. The fuel element was broken in two pieces, with a relatively clean fracture, and the larger piece was tested. A gray/white coating was observed. This was the first test of a damaged fuel element in the furnace. K-West canisters can hold up to seven complete fuel assemblies, but, for purposes of this report, the element tested here is designated as Element 0309M.The drymg test was conducted in the Whole Element Furnace Testing System located in G-Cell within the PTL. The test system is composed of three basic systems: the in-cell furnace equipment, the system gas loop, and the analytical instrument package. Element 0309M was subjected to drymg processes based on those proposed under the Integrated Process Strategy, which included a hot drying step. Approximately 5 ml of water were observed in the condenser during the condenser pumpdown phase of CVD. Two Pressure Rise Tests were conducted following CVD. The first Pressure Rise Test did not meet the criterion of d . 6 T o r r h and, therefore, a second test was successfully conducted. Approximately 4 mg of water were removed during both Pressure Rise Tests, likely fromfiee water, trapped under the observed surface coating on the fuel element, which was not completely released during CVD.Approximately 2 g of water were released during HVD, with the largest amount (-1.7 g) removed during the temperature increment from -8OOC to -4OOOC. Thermal decomposition of hydrated species was significant in controlling the removal of water from the system during the HVD. As a result, a temperature above 400°C may be required for complete drying of the hydrated species within a reasonable period of time.iii Hydrogen was also observed during HVD starting at about 1 5OoC. Two main peaks were evident, at -222OC fiom oxidation of the fuel by water, and at -270OC fiom the decomposition of uranium hydride. Total hydrogen release during HVD was -19 mg.