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Influence of humic-acid complexing on the mobility of Americium in the soil aquatic environment

Description: Diffusion data indicate the Am, Cm and Np migrate 1.2, 0.8, and 26 centimeters, respectively, in a thousand years. Thus, excluding mass transport by moving water or wind, actinide elements, such as Cm, Am, and Np that find their way to the soil-aquatic environment are relatively immobile. Measured diffusion coefficients, corrected for distribution between the aqueous and soil phases, tortuosity, negative absorption, and relative fluidity are in reasonable agreement with aqueous diffusion coeffi… more
Date: March 1, 1982
Creator: Sheppard, J.C.; Campbell, M.J. & Kittrick, J.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Separation of Am-Cm from Al(NO/sub 3/)/sub 3/ waste solutions by in-canyon-tank precipitation as oxalates

Description: A process for recovery of Am-Cm residues from high-activity waste concentrates has been developed specifically for application in Savannah River Plant (SRP) canyon tanks. The Am-Cm residues were collected from a campaign to produce plutonium containing high isotopic concentrations of /sup 242/Pu. The separation of Am-Cm from the high-activity waste stream, containing about 2M Al(NO/sub 3/)/sub 3/, is necessary to produce an acceptable feed solution for a later pressurized cation exchange chroma… more
Date: April 1, 1982
Creator: Gray, L. W.; Burney, G. A.; Wilson, T. W.; McKibben, J. M.; Bibler, N. E.; Holtzscheiter, E. W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Isolating /sup 241/Am from waste solutions containing Al, Ca, Fe, and Cr

Description: About 2.4 kg of /sup 241/Am contaminated with calcium and aluminum had been recovered from low-activity waste during recycle of 11% /sup 240/Pu. A process was developed and demonstrated to purify the americium before shipment as /sup 241/AmO/sub 2/. The americium and some of the calcium were batch extracted into 50% TBP-n-paraffin from 2.2M Al(NO/sub 3/)/sub 3/ - 0.3M HNO/sub 3/ solution in a canyon tank. Pregnant solvent was scrubbed first with 2.1M Al/sup 3 +/-0.3M Li/sup +/-6.7M NO/sub 3/- a… more
Date: January 1, 1982
Creator: Gray, L. W.; Burney, G. A. & King, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pyrochemical processing of plutonium. Technology review report

Description: Non-aqueous processes are now in routine use for direct conversion of plutonium oxide to metal, molten salt extraction of americium, and purification of impure metals by electrorefining. These processes are carried out at elevated temperatures in either refractory metal crucibles or magnesium-oxide ceramics in batch-mode operation. Direct oxide reduction is performed in units up to 700 gram PuO/sub 2/ batch size with molten calcium metal as the reductant and calcium chloride as the reaction flu… more
Date: September 8, 1982
Creator: Coops, M.S.; Knighton, J.B. & Mullins, L.J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Hydrolysis and formation constants at 25/sup 0/C

Description: A database consisting of hydrolysis and formation constants for about 20 metals associated with the disposal of nuclear waste is given. Complexing ligands for the various ionic species of these metals include OH, F, Cl, SO/sub 4/, PO/sub 4/ and CO/sub 3/. Table 1 consists of tabulated calculated and experimental values of log K/sub xy/, mainly at 25/sup 0/C and various ionic strengths together with references to the origin of the data. Table 2 consists of a column of recommended stability const… more
Date: May 1, 1982
Creator: Phillips, S.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Review of plutonium process chemistry at Rocky Flats

Description: Plutonium metal scrap, oxide, and other residues are processed at Rocky Flats using both pyrochemical and aqueous methods. The pyrochemical processes currently in production include electrorefining, fluorination, hydriding, molten salt extraction (MSE), calcination, and reduction operations. Aqueous processing and waste-treatment methods involve nitric acid dissolution, ion exchange, solvent extraction, and precipitation techniques. An overview of the chemistry involved in these operations will… more
Date: September 1, 1982
Creator: Baldwin, C.E. & Navratil, J.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Effect of radiolysis on leachability of plutonium and americium from 76-101 glass. [Glass containing 2 mole % plutonium]

Description: One aspect of the leachability of actinide-bearing glass which has not been adequately addressed is the effect of radiolysis of the system (glass-water) on the amount of actinides liberated from the glass. In the present study, we have investigated the leaching of plutonium and americium from 76-101 glass samples (containing 2 mole % plutonium) in the presence of a one megaRad/hour gamma-radiation field. The presence of the radiation field was found to increase the leaching rate of both plutoni… more
Date: January 1, 1982
Creator: Nash, K.L.; Fried, S.; Friedman, A.M.; Susak, N.; Rickert, P.; Sullivan, J.C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hybrid Chemical and Nondestructive-Analysis Technique

Description: A hybrid chemical/NDA technique has been applied at the Los Alamos National Laboratory to the assay of plutonium in ion-exchange effluents. Typical effluent solutions contain low concentrations of plutonium and high concentrations of americium. A simple trioctylphosphine oxide (TOPO) separation can remove 99.9% of the americium. The organic phase that contains the separated plutonium can be accurately assayed by monitoring the uranium L x-ray intensities.
Date: 1982~
Creator: Hsue, S.-T.; Marsh, S. F. & Marks, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Geochemical assessment of nuclear-waste isolation. Testing of methods for the separation of solid and aqueous phases

Description: Measurement of the solubilities of certain waste radionuclide compounds will be necessary to adequately assess and predict the ability of potential underground waste storage facilities to meet federally established performance criteria. During such measurements, it is usually necessary to physically separate solid and solution phases. Experiments have been conducted to test and compare the relative efficacy of three commonly used separation methods, i.e. gravity settling, centrifugation and fil… more
Date: April 15, 1982
Creator: Silva, R. J. & Yee, A. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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