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Kilogram-scale purification of americium by ion exchange

Description: Sequential anion and cation exchange processes have been used for the final purification of /sup 241/Am recovered during the reprocessing of aged plutonium metallurgical scrap. Plutonium was removed by absorption of Dowex 1, X-3.5 (30 to 50 mesh) anion exchange resin from 6.5 to 7.5 M HNO/sub 3/ feed solution. Following a water dilution to 0.75 to 1.0 M HNO/sub 3/, americium was absorbed on Dowex 50W, X-8 (50 to 100 mesh) cation exchange resion. Final purification was accomplished by elution of… more
Date: January 1, 1979
Creator: Wheelwright, E. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Transuranium processing plant report of production, status, and plans for the period January 1, 1978--September 30, 1978

Description: During this period transuranium elements were obtained from 13 irradiated HFIR targets. The final purifications of three batches of /sup 248/Cm were completed. Forty-two product shipments were made from TRU. Six HFIR targets were fabricated; each contained approximately 2 g of /sup 243/Am and 7.5 g of cerium. The precision of the fast-neutron counting system in the TURF Californium Facility was improved sufficiently to permit assay of the /sup 252/Cf content in pellets, sources, and shipping pa… more
Date: June 1, 1979
Creator: King, L. J.; Bigelow, J. E. & Collins, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Separation of macro quantities of actinides by high-pressure cation exchange

Description: Several kilograms of /sup 244/Cm and /sup 243/Am and several milligrams of /sup 252/Cf were produced by irradiation of a mixture of plutonium isotopes. The plutonium was separated by solvent extraction, and the other actinides were separted from each other and from large quantities of fission-product rare earths by displacement-development chromatography in a system of pressurized steel columns in high level caves. The elutriant was 0.05 M DTPA buffered with ammonium hydroxide. Part of one of t… more
Date: January 1, 1979
Creator: Burney, G. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Actinide cross section data and inertial confinement fusion for long term waste disposal

Description: Actinide cross section data at thermonuclear neutron energies are needed for the calculation of ICF pellet center burnup of fission reactor waste, viz. 14 MeV neutron fission of the very long-lived actinides that pose storage problems. A major advantage of pellet center burnup is safety: only milligrams of highly toxic and active material need to be present in the fusion chamber, whereas blanket burnup requires the continued presence of tons of actinides in a small volume. The actinide data tab… more
Date: January 15, 1979
Creator: Meldner, Heiner
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Interaction of radionuclides with geomedia from the Nevada Test Site

Description: Aqueous/solid distribution coefficients have been measured for {sup 137}Cs, {sup 85}Sr, {sup 99}Tc, {sup 152}Eu, {sup 144}Ce, {sup 238}Pu, {sup 243}Am and {sup 244}Cm on powdered argillite and hornfels obtained from the Nevada Test Site. The fluid phases included a groundwater simulant and deionized water preequilibrated with powdered argillite. Distribution coefficients for lanthanides and actinides are generally high and Eleana shale was found to effectively sorb technetium.
Date: December 31, 1979
Creator: Lynch, A.W. & Dosch, R.G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Interaction of radionuclides with argillite from the Eleana Formation on the Nevada Test Site

Description: Distribution coefficients have been determined for {sup 137}Cs, {sup 85}Sr, {sup 144}Ce, {sup 99}Tc, {sup 152}Eu, {sup 238}Pu, {sup 244}Cm, and {sup 243}Am between argillite from the Eleana Formation on the Nevada Test Site (NTS) and several aqueous phases. Radionuclide concentrations in the range of 1 to 0.001 {mu}Ci/ml were used with contact times of 14, 28, and 56 days. Reaction mechanism, concentration effects, exchange capacity, equilibration times, and particle size effects were addressed… more
Date: February 1, 1979
Creator: Dosch, R.G. & Lynch, A.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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