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Modification of base-side {sup 99}MO production processes for LEU metal-foil targets.

Description: Argonne National Laboratory is cooperating with the National Atomic Energy Commission of the Argentine Republic (CNEA) to convert their {sup 99}Mo production process, which uses high enriched uranium (HEU), to low-enriched uranium (LEU), The program is multifaceted; however, discussed in this paper are (1) results of laboratory experiments to develop means for substituting LEU metal-foil targets into the current process and (2) preparation of uranium-alloy or uranium-metal/aluminum-dispersion t… more
Date: September 30, 1999
Creator: Vandegrift, G. F.; Leonard, R. A.; Aase, S.; Sedlet, J.; Koma, Y.; Conner, C. et al.
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Partner: UNT Libraries Government Documents Department
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Preliminary Plan for Treating Mixed Waste

Description: A preliminary waste treatment plan was developed for disposing of radioactive inorganic liquid wastes that contain hazardous metals and/or hazardous acid concentrations at Argonne National Laboratory. This plan, which involves neutralization and sulfide precipitation followed by filtration, reduces the concentration of hazardous metals and the acidity so that the filtrate liquid is simply a low-level radioactive waste that can be fed to a low-level waste evaporator.
Date: June 1993
Creator: Vandegrift, G. F.; Conner, C.; Hutter, Joseph C.; Leonard, R. A.; Nuñez, Luis; Sedlet, J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress in chemical processing of LEU targets for {sup 99}Mo production -- 1997

Description: Presented here are recent experimental results of the continuing development activities associated with converting current processes for producing fission-product {sup 99}Mo from targets using high-enriched uranium (HEU) to low-enriched uranium (LEU). Studies were focused in four areas: (1) measuring the chemical behavior of iodine, rhodium, and silver in the LEU-modified Cintichem process, (2) performing experiments and calculations to assess the suitability of zinc fission barriers for LEU me… more
Date: October 1, 1997
Creator: Vandegrift, G. F.; Conner, C.; Sedlet, J.; Wygmans, D. G.; Wu, D.; Iskander, F. et al.
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Partner: UNT Libraries Government Documents Department
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Letter report - parametric studies on the use of in situ formed magnetite for the removal of Sr and actinides from tank waste at the Savannah River site.

Description: This report discusses the experimental program conducted at ANL to study the performance of in-situ-formed magnetite for the removal of Sr, Pu, Np, U, Am, and Cs from the Savannah River Site (SRS) tank waste. The boundaries for the experimental work were defined based on the operational envelope developed earlier in collaboration with SRS. In situ formed ''magnetite'' is actually a mixture of Fe(II) and Fe(III) oxides and hydroxides, including magnetite. Decontamination factor (DF) values were … more
Date: April 14, 2003
Creator: Arafat, H. A.; Aase, S. B.; Bakel, A. J.; Bowers, D. L.; Gelis, A. V.; Regalbuto, M. C. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Electroplating fission-recoil barriers onto LEU-metal foils for {sup 99}Mo-production targets

Description: Electroplating experiments on uranium foil have been conducted in order to develop low-enriched uranium composite targets suitable for the production of {sup 99}Mo. Preparation of the foil surface prior to plating was found to play a key role in the quality of the resultant coating. A surface preparation procedure was developed that produces both zinc and nickel coatings with the desired level of coating adherence and coverage. Modifications of the existing plating processes now need investigat… more
Date: October 1, 1997
Creator: Smaga, J. A.; Sedlet, J.; Conner, C.; Liberatore, M. W.; Walker, D. E.; Wygmans, D. G. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Development and demonstration of the TRUEX solvent extraction process

Description: The Generic TRUEX Model (GTM) was developed for use in designing site and feed-specific TRUEX flowsheets and in estimating the space and cost requirements for installing a TRUEX process. This paper discusses data collected in support of the GTM and its use in (1) designing process flowsheets and (2) performing sensitivity analyses. Demonstration of the TRUEX process is underway at Argonne National Laboratory (ANL), where plutonium-containing analytical waste solutions generated at the DOE New B… more
Date: March 1, 1993
Creator: Vandegrift, G. F.; Chamberlain, D. B.; Conner, C.; Copple, J. M.; Dow, J. A.; Everson, L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Development and demonstration of the TRUEX solvent extraction process

Description: The Generic TRUEX Model (GTM) was developed for use in designing site and feed-specific TRUEX flowsheets and in estimating the space and cost requirements for installing a TRUEX process. This paper discusses data collected in support of the GTM and its use in (1) designing process flowsheets and (2) performing sensitivity analyses. Demonstration of the TRUEX process is underway at Argonne National Laboratory (ANL), where plutonium-containing analytical waste solutions generated at the DOE New B… more
Date: January 1, 1993
Creator: Vandegrift, G. F.; Chamberlain, D. B.; Conner, C.; Copple, J. M.; Dow, J. A.; Everson, L. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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