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Leaching study of PNL 76-68 glass beads using the LLNL continuous-flow method and the PNL-modified IAEA method. Final report

Description: Lawrence Livermore National Laboratory (LLNL) has conducted a long-term single-pass continuous-flow (SPCF) leaching test of the glass waste form PNL 76-68. Leaching rates of Np, Pu, and various stable elements were measured at 25/sup 0/ and 75/sup 0/C with three different solutions and three different flow rates. The purposes of the study were: (1) to compare SPCF leaching results with the results of a modified IAEA leach test performed by Pacific Northwest Laboratories (PNL); (2) to establish … more
Date: August 20, 1982
Creator: Buddemeier, R. W.; Coles, D. G.; Mensing, R. W.; Rego, J. & Weed, H. C.
Partner: UNT Libraries Government Documents Department
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CsAlSi/sub 5/O/sub 12/: a possible host for /sup 137/Cs immobilization

Description: CsAlSi/sub 5/O/sub 12/ exhibits more acid resistance than pollucite (CsAlSi/sub 2/O/sub 6/). At pH values of 1.02 and 1.40, the extraction of Cs from CsAlSi/sub 5/O/sub 12/ at 25/sup 0/C was approximately proportional to the square root of leach time. The Cs extraction at 25/sup 0/C varied as (H/sup +/)/sup 0/ /sup 36/ over the pH range of 1 to 6. Also, the Cs extraction in various brines at 300/sup 0/C/30 MPa was comparable with that for pollucite. CsAlSi/sub 5/O/sub 12/ can be crystallized at… more
Date: March 31, 1982
Creator: Adl, T. & Vance, E.R.
Partner: UNT Libraries Government Documents Department
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Development and testing of matrices for the encapsulation of glass and ceramic nuclear waste forms.

Description: This report details the results of research on the matrix encapsulation of high level wastes at PML over the past few years. The demonstrations and tests described were designed to illustrate how the waste materials are effected when encapsulated in an inert matrix. Candidate materials evaluated for potential use as matrices for encapslation of pelletized ceramics or glass marbles were categorized into four groups: metals, glasses, ceramics, and graphite. Two processing techniques, casting and … more
Date: February 1, 1982
Creator: Wald, J. W.; Brite, D. W.; Gurwell, W. E.; Buckwalter, C. Q.; Bunnell, L. R.; Gray, W. J. et al.
Partner: UNT Libraries Government Documents Department
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Comparative leach testing of high-level waste forms

Description: Four candidate waste forms (borosilicate glass, high-silica glass, tailored ceramic, and Synroc) for Savannah River Plant high-level nuclear waste were compared in MCC-1 standard static leach tests. Relative leaching behavior differed for each element, and none of the waste forms was clearly superior to the others.
Date: January 1, 1982
Creator: Stone, J A
Partner: UNT Libraries Government Documents Department
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Alternative-waste-form evaluation for Savannah River Plant high-level waste

Description: Results of the waste form evaluation are summarized as: risks of human exposure are comparable and extremely small for either borosilicate glass or Synroc ceramic. Waste form properties are more than adequate for either form. The waste form decision can therefore be made on the basis of practicality and cost effectiveness. Synroc offers lower costs for transportation and emplacement. The borosilicate glass form offers the lowest total disposal cost, much simpler and less costly production, an e… more
Date: January 1, 1982
Creator: Gould, Jr, T H & Crandall, J L
Partner: UNT Libraries Government Documents Department
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Consolidated waste forms: glass marbles and ceramic pellets

Description: Glass marbles and ceramic pellets have been developed at Pacific Northwest Laboratory as part of the multibarrier concept for immobilizing high-level radioactive waste. These consolidated waste forms served as substrates for the application of various inert coatings and as ideal-sized particles for encapsulation in protective matrices. Marble and pellet formulations were based on existing defense wastes at Savannah River Plant and proposed commercial wastes. To produce marbles, glass is poured … more
Date: May 1, 1982
Creator: Treat, R.L. & Rusin, J.M.
Partner: UNT Libraries Government Documents Department
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High-level waste-form-product performance evaluation. [Leaching; waste loading; mechanical stability]

Description: Seven candidate waste forms were evaluated for immobilization and geologic disposal of high-level radioactive wastes. The waste forms were compared on the basis of leach resistance, mechanical stability, and waste loading. All forms performed well at leaching temperatures of 40, 90, and 150/sup 0/C. Ceramic forms ranked highest, followed by glasses, a metal matrix form, and concrete. 11 tables.
Date: January 1, 1982
Creator: Bernadzikowski, T A; Allender, J S; Stone, J A; Gordon, D E; Gould, Jr, T H & Westberry, III, C F
Partner: UNT Libraries Government Documents Department
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Technological options for management of hazardous wastes from US Department of Energy facilities

Description: This report provides comprehensive information on the technological options for management of hazardous wastes generated at facilities owned or operated by the US Department of Energy (DOE). These facilities annually generate a large quantity of wastes that could be deemed hazardous under the Resource Conservation and Recovery Act (RCRA). Included in these wastes are liquids or solids containing polychlorinated biphenyls, pesticides, heavy metals, waste oils, spent solvents, acids, bases, carci… more
Date: August 1, 1982
Creator: Chiu, S.; Newsom, D.; Barisas, S.; Humphrey, J.; Fradkin, L. & Surles, T.
Partner: UNT Libraries Government Documents Department
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Workshop on the leaching mechanisms of nuclear-waste forms, October 27-28, 1981. Summary report

Description: The purpose of this informal workshop was to initiate the program and achieve the following goals: (1) acquaint laboratory investigators (data generators) with the needs of the mathematical modelers (data users). Session I was devoted to a tutorial by D.D. Jackson, mathematical modeler for the leaching mechanisms program, on PROTOCOL, a general case waste form leaching model; (2) define important testing parameters, based on the present state of knowledge. To achieve this, a number of important… more
Date: April 1, 1982
Creator: Mendel, J.E. (comp.)
Partner: UNT Libraries Government Documents Department
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Stability of ceramic waste forms in potential repository environments: a review

Description: Most scenarios for geologic disposal of high-level nuclear waste include the eventual intrusion of groundwater into the repository. Reactions in the system and eventual release of the radionuclides, if any, will be controlled by the chemistry of the groundwater, the surrounding rock, the waste form, and any engineered barrier materials that are present, as well as by the temperature and pressure of the system. This report is a compilation and evaluation of the work completed to date on interact… more
Date: March 31, 1982
Creator: Johnston, R. J. & Palmer, R. A.
Partner: UNT Libraries Government Documents Department
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Chemical durability of Savannah River Plant waste glass as a function of waste loading

Description: The leachability of Savannah River Plant (SRP) waste forms was assessed for glass containing up to 50 wt % simulated waste oxides. Leach tests included standard MCC-1 static tests and pH-buffered solution experiments. An integrated approach combining leachate solution analysis with both bulk and surface analyses was used to study waste glass corrosion as a function of waste loading. Leachate solutions were analyzed by inductively coupled plasma spectroscopy and atomic absorption. Bulk and surfa… more
Date: January 1, 1982
Creator: Rankin, W D & Wicks, G G
Partner: UNT Libraries Government Documents Department
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Chemical durability of Savannah River Plant waste glass as a function of groundwater pH

Description: The leachability of Savannah River Plant (SRP) waste glass was assessed for leachants in the pH range of 3 to 11. A parabolic relationship was observed between leachability and solution pH in this range. At 40/sup 0/C, leachability was lowest within a pH range of approximately 5 to 9. Most of the groundwaters in potential repository locations have pH values in this range. Below pH 5 and above pH 9, leachability of the waste glass increases. Leachability as a function of solution pH was studied … more
Date: January 1, 1982
Creator: Wicks, G. G.; O'Rourke, P. E. & Whitkop, P. G.
Partner: UNT Libraries Government Documents Department
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Some chemical and mineralogical considerations important for understanding leachate chemistry

Description: Both the raw shale material and the retorting process parameters are influential in determining the subsequent behavior of the spent shale solids with respect to leaching and/or environmental weathering. The process parameters define the mineral reactions that occur to form the mineral assemblage in the spent shale, while the major and trace element residences and mobilities from the raw shale determine the extent of incorporation of these elements in the spent shale matrix and ultimately the c… more
Date: January 1, 1982
Creator: Peterson, E. J. & Wagner, P.
Partner: UNT Libraries Government Documents Department
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High-level-waste immobilization

Description: Analysis of risks, environmental effects, process feasibility, and costs for disposal of immobilized high-level wastes in geologic repositories indicates that the disposal system safety has a low sensitivity to the choice of the waste disposal form.
Date: January 1, 1982
Creator: Crandall, J L
Partner: UNT Libraries Government Documents Department
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Preliminary investigation of a technique to separate fission noble metals from fission product mixtures

Description: A variation of the gold-ore fire assay technique was examined as a method for recovering Pd, Rh and Ru from fission products. The mixture of fission product oxides is combined with glass-forming chemicals, a metal oxide such as PbO (scavenging agent), and a reducing agent such as charcoal. When this mixture is melted, a metal button is formed which extracts the noble metals. The remainder cools to form a glass for nuclear waste storage. Recovery depended only on reduction of the scavenger oxide… more
Date: August 1, 1982
Creator: Mellinger, G. B. & Jensen, G. A.
Partner: UNT Libraries Government Documents Department
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Properties of SYNROC-D nuclear waste form: a state-of-the-art reivew

Description: SYNROC is a titanate-based ceramic waste form being developed to immobilize high-level nuclear reactor wastes. SYNROC-D is a unique variation of SYNROC designed to contain high-level defense wastes, particularly those in storage at the Savannah River Plant (SRP). In this report, we review results from physical property and performance tests on SYNROC-D containing simulated SRP wastes. These results provide a data base for comparing SYNROC-D with other defense waste forms. The test data are grou… more
Date: January 1, 1982
Creator: Campbell, J.; Hoenig, C.; Bazan, F.; Ryerson, F.; Guinan, M.; Van Konynenburg, R. et al.
Partner: UNT Libraries Government Documents Department
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Chemical durability of glass containing SRP waste: leachability characteristics, protective layer formation, and repository system interactions

Description: The Repository Systems Program at Savannah River consists of the following elements: (a) static repository tests, (b) slow flow groundwater tests, (c) dynamic leaching experiments, (d) long term leaching tests, and (e) in situ experiments. The scouting tests performed in the static repository program are summarized and a new dynamic leaching concept is introduced in this paper. Abbreviated MCC-1 static leaching tests were used in this static repository program. The tests were conducted at 90/su… more
Date: January 1, 1982
Creator: Wicks, G G; Robnett, B M & Rankin, W D
Partner: UNT Libraries Government Documents Department
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Roasting and dissolution studies on nonirradiated thorium dioxide/uranium dioxide pellets

Description: Bench scale roasting and dissolution of ThO/sub 2/ and ThO/sub 2//UO/sub 2/ ractor-grade ceramic pellets were studied at the Savannah River Laboratory to define the key parameters affecting dissolution. Pellet breakup, and subsequent dissolution rates, were determined for ThO/sub 2/ and ThO/sub 2//UO/sub 2/ pellets roasted in air or in oxygen. Roasting ThO/sub 2//UO/sub 2/ pellets in air at temperatures from 400 to 900/sup 0/C caused the pellets to crack but not fragment. Roasting whole pellets… more
Date: January 1, 1982
Creator: Pickett, J. B.; Fowler, J. R. & Mosley, W. C. Jr.
Partner: UNT Libraries Government Documents Department
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SRP radioactive glass studies: small-scale process development and product performance

Description: A small-scale joule-heated ceramic melter contained in the Shielded Cells Facility has demonstrated the vitrification process for actual Savannah River Plant radioactive waste. Losses of radionuclides due to volatility are low and easily treated, and the glass produced is of comparable quality to laboratory-prepared simulated glass. Future work will include studies with wastes from other tanks, using new frit compositions. Leaching tests will continue, with emphasis being placed on long-term te… more
Date: January 1, 1982
Creator: Plodinec, M J; Soper, P D; Bibler, N E & Kessler, J L
Partner: UNT Libraries Government Documents Department
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Optimization of glass composition for the vitrification of nuclear waste at the Savannah River Plant

Description: Waste glasses of different compositions were compared in terms of leachability, viscosity, liquidus temperature, and coefficient of expansion. The compositions of the glasses were determined by statistical optimization. Waste glass of the optimized composition is more durable than the current reference composition but can still be processed at low temperature.
Date: January 1, 1982
Creator: Soper, P. D.; Roberts, G. J.; Lightner, L. F.; Walker, D. D. & Plodinec, M. J.
Partner: UNT Libraries Government Documents Department
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Summary report for the interlaboratory round robin on the MCC-1 static leach test method

Description: The MCC-1 Static Leach Test Method Round Robbin (RR) was conducted by the Materials Characterization Center (MCC) over a period of 15 months, 1980-82. A total of 25 laboratories provided data in connection with the RR. All together these laboratories tested 769 waste form specimens using the 1980 draft of MCC-1. The specimens tested were approximately one gram wafers cut by the laboratory from samples provided by MCC: NBS borosilicate glass; core dillings of basalt from the Hanford Reservation;… more
Date: March 1, 1982
Creator: Johnston, J. W. & Daniel, J. L.
Partner: UNT Libraries Government Documents Department
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Role of temperature, solvent and agitation in coal dissolution and liquefaction. Quarterly report, December 1981-February 1982

Description: A Plexiglas reactor was constructed and experiments carried out with three mixer configurations in a sand-water system to determine the best mixer configuration and the minimum rpm to produce uniform conditions during coal dissolution. Coal dissolution experiments on Kentucky No. 9 coal were made with combinations of tetralin and 2-methylnaphthalene to obtain the optimum ratio in the solvent. The effect of ..beta..-naphthol addition to the solvent on the dissolution of Kentucky No. 9 coal was s… more
Date: March 1, 1982
Creator: Briggs, D.E. & Ebnesajjad, S.
Partner: UNT Libraries Government Documents Department
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Soil-water impacts from using vegetation and rock covers for surface stabilization of uranium-mill tailings

Description: This paper presents the results from an analysis of vegetated and rock covers and their effect on the moisture content in a covered uranium mill tailings system. Based on a one-dimensional analysis of moisture movement, the results indicate that care must be taken when selecting a surface stabilization system for a tailings pile. The moisture-content response of the tailings pile and cover system can be radically altered by different surface treatments. The two cases considered in this study in… more
Date: January 1, 1982
Creator: Mayer, D. W.; Beedlow, P. A. & Cadwell, L. L.
Partner: UNT Libraries Government Documents Department
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Near-surface leaching studies of Pb-implanted Savannah River waste glass

Description: The present experiments with Savannah River Plant simulated nuclear waste glass implanted with Pb ions, used Rutherford backscattering spectrometry and elastic recoil detection to follow in detail the changes in composition which occur in the near-surface region upon leaching in deionized water at 90/sup 0/C. Analyses of the leach solutions were made in an attempt to correlate the actual leach rates with the observed near-surface compositional changes. These experiments show that radiation dama… more
Date: January 1, 1982
Creator: Arnold, G. W.; Northrup, C. J. M. & Bibler, N. E.
Partner: UNT Libraries Government Documents Department
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