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Transfer operations with tritium -- A review

Description: Controlled thermonuclear reactors will involve pumping operations with tritium that may involve pressures ranging from submillipascals to megapascals. A variety of pumps is available that can cover portions of this range, and these can be staged to cove the entire pressure range. Some of these pumps can be adapted to virtually any size requirement currently anticipated. Special attention must be paid to operating features and construction materials.
Date: December 31, 1975
Creator: Folkers, C.L. & Gede, V.P.
Partner: UNT Libraries Government Documents Department

Characterization of actinide-bearing sediments underlying liquid waste disposal facilities at Hanford

Description: Past liquid waste disposal practices at the U. S. Energy Research and Development Administration's Hanford Reservation have included the discharges of solutions containing trace quantities of actinides directly into the ground via structures collectively termed ''trenches''. Characterization of samples from two of these trenches, the 216-Z-9 and the 216-Z-1A(a), has been initiated to determine the present form and migration potential of plutonium stored in sediments which received high salt, acidic waste liquids. Analysis of samples acquired by drilling has revealed that the greatest measured concentration of Pu, approximately 10$sup 6$ $mu$Ci $sup 239$Pu/liter of sediment, occurs in both facilities just below the points of release of the waste liquids. This concentration decreases to approximately 10$sup 3$ $mu$Ci $sup 239$Pu/liter of sediment within the first 2 meters of the underlying sediment columns and to approximately 10 $mu$Ci $sup 239$Pu/liter of sediment at the maximum depth sampled (9 meters). Examination of relatively undisturbed sediment cores illustrated two types of Pu occurrence responsible for this distribution. One of these types is composed of Pu particles (greater than 70 wt percent PuO$sub 2$) added to the disposal site in the same form. This ''particulate'' type was ''filtered out'' within the upper 1 meter of the sediment column, accounting for the high concentration of Pu/liter of sediment in this region. The second type of Pu (less than 0.5 wt percent PuO$sub 2$) was originally disposed of as soluble Pu(IV). This ''nonparticulate'' type penetrated deeper within the sediment profile and was deposited in association with silicate hydrolysis of the sediment fragments. (auth)
Date: September 1, 1975
Creator: Price, S.M. & Ames, L.L.
Partner: UNT Libraries Government Documents Department

Glass forms for alpha waste management

Description: No Description Available.
Date: July 1, 1975
Creator: Kupfer, M.J.; Schulz, W.W.; Hobbick, C.W. & Mendel, J.E.
Partner: UNT Libraries Government Documents Department

Processing of radioactive waste solutions in a vacuum evaporator- crystallizer

Description: Results of the first 18 months' operation of Hanford's vacuum evaporator- crystallizer are reported. This process reduces the volume of radioactive waste solutions and simultaneously converts the waste to a less mobile salt cake. The evaporator-crystallizer is operating at better than design production rates and has reduced the volume of radioactive wastes by more than 15 million gallons. A process description, plant performance data, mechanical difficulties, and future operating plans are discussed. Also discussed is a computer model of the evaporator-crystallizer process. (auth)
Date: September 26, 1975
Creator: Petrie, J.C.; Donovan, R.I.; Van der Cook, R.E. & Christensen, W.R.
Partner: UNT Libraries Government Documents Department

Conceptual design considerations for the storage of solidified high-level waste in canisters at a commercial fuel reprocessing plant

Description: Onsite storage of canisters of solidified high-level waste generated by the commercial fuel reprocessing plants (FRP) may be required prior to shipping these canisters to a Federal repository. The most likely storage concept is to hold the waste-filled canisters in water storage basins. In the Retrievable Surface Storage Facility conceptual design studies, air-cooled and water-cooled storage of solidified high-level wastes has been considered. The studies of water-cooled storage included design considerations, as part of the conceptual design of the canisters and water storage basins, that would apply also to the conceptual design of similar facilities at an FRP. These similar considerations include: types of corrosion likely to develop on canisters stored in water, conditions that promote stress corrosion cracking (SCC), prevention of SCC, routine basin water cleanup, cleanup of a grossly contaminated water basin, effluent discharge discussions, storage basin integrity, and designing for decommissioning. (auth)
Date: November 1, 1975
Creator: LaRiviere, J.R. & Moore, E.L.
Partner: UNT Libraries Government Documents Department

Man-made geothermal reservoirs

Description: None
Date: January 1, 1975
Creator: Smith, M.C.; Aamodt, R.L.; Potter, R.M. & Brown, D.W.
Partner: UNT Libraries Government Documents Department

Geothermal energy

Description: None
Date: January 1, 1975
Creator: Tester, J.W. & Milora, S.L.
Partner: UNT Libraries Government Documents Department