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Experience base for Radioactive Waste Thermal Processing Systems: A preliminary survey

Description: In the process of considering thermal technologies for potential treatment of the Idaho National Engineering Laboratory mixed transuranic contaminated wastes, a preliminary survey of the experience base available from Radioactive Waste Thermal Processing Systems is reported. A list of known commercial radioactive waste facilities in the United States and some international thermal treatment facilities are provided. Survey focus is upon the US Department of Energy thermal treatment facilities. A… more
Date: April 1, 1992
Creator: Mayberry, J.; Geimer, R.; Gillins, R.; Steverson, E.M.; Dalton, D. (Science Applications International Corp., Idaho Falls, ID (United States)) & Anderson, G.L. (EG and G Idaho, Inc., Idaho Falls, ID (United States))
Partner: UNT Libraries Government Documents Department
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DWPF waste glass Product Composition Control System

Description: The Defense Waste Processing Facility (DWPF) will be used to blend aqueous radwaste (PHA) with solid radwaste (Sludge) in a waste receipt vessel (the SRAT). The resulting SRAT material is transferred to the SME an there blended with ground glass (Frit) to produce a batch of melter feed slurry. The SME material is passed to a hold tank (the MFT) which is used to continuously feed the DWPF melter. The melter. The melter produces a molten glass wasteform which is poured into stainless steel canist… more
Date: January 1, 1992
Creator: Brown, K.G. & Postles, R.L.
Partner: UNT Libraries Government Documents Department
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Nuclear facility decommissioning and site remedial actions. Volume 6. A selected bibliography

Description: This bibliography of 683 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the sixth in a series of annual reports prepared for the US Department of Energy's Remedial Action Programs. Foreign as well as domestic literature of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - … more
Date: September 1, 1985
Creator: Owen, P. T.; Michelson, D. C. & Knox, N. P.
Partner: UNT Libraries Government Documents Department
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Decommissioning of a grout- and waste-filled storage tank in the 200 East Area of the Hanford Site

Description: A self-concentrating waste tank located at the Strontium Semiworks Facility in the 200 East Area of the Hanford Site will be decommissioned following waste removal. During a previous decommissioning phase, the tank, thought to be empty, was filled with grout to prevent it from collapsing over time. Several years later, an agitator rod was pulled from within the tank and found to contain significant amounts of radiation, indicating there was still radioactive waste in the tank. Several alternati… more
Date: January 1, 1991
Creator: Marske, S.G.
Partner: UNT Libraries Government Documents Department
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Interactions of tailings leachate with local liner materials found at Canonsburg, Pennsylvania.

Description: The mill tailings site at Canonsburg, Pennsylvania is the first mill site to receive remedial action under the Department of Energy's Uranium Mill Tailings Remedial Action Program. Part of this remedial action will require excavating the 53,500 m/sup 3/ (70,000 yd/sup 3/) of tailings on the site having a specific activity exceeding 100 pCi/g, and encapsulating these contaminated tailings in a clay-lined cell. As part of the remedial action effort, Pacific Northwest Laboratory has been studying … more
Date: April 1, 1984
Creator: Dodson, M.E.; Gee, G.W. & Serne, R.J.
Partner: UNT Libraries Government Documents Department
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Office of Waste Isolation progress report, December 1977

Description: This document reports progress on the OWI's portion of the National Waste Terminal Storage (NWTS) program. It comprises project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. They are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs. (DLC)
Date: January 31, 1976
Creator: Zerby, C.D.
Partner: UNT Libraries Government Documents Department
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Development of a mathematical model of a packed column for benzene removal from salt solutions

Description: A mathematical model of a packed column was developed to describe the removal of benzene from radioactive salt solutions at the Savannah River Site. The model was developed from existing, generalized mass transfer correlations for randomly dumped packing, and the correlations were adapted for structured packing. Thermophysical data specific to the solutions of interest were incorporated into the model. Verification of the code was completed using operating data from stripping columns at other l… more
Date: January 1, 1989
Creator: Georgeton, G.K.
Partner: UNT Libraries Government Documents Department
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Organic components of nuclear wastes and their potential for altering radionuclide distribution when released to soil

Description: Normal waste processing at the Hanford operations requires the use of many organic materials, chiefly in the form of complexing agents and diluents. These organic materials and their chemical and radiolytic degradation products, have potential for complexing fission products and transuranium elements, both in the waste streams and upon infiltration into soil, perhaps influencing future sorption or migration of the nuclides. Particular complexation characteristics of various nuclides which const… more
Date: August 1, 1980
Creator: McFadden, K.M.
Partner: UNT Libraries Government Documents Department
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Compatibility testing of vitrified waste forms

Description: An experimental program to evaluate candidate metals for use in the fabrication of canisters for long-term storage of vitrified radioactive wastes is described. The long-term compatibility of the candidate metal both with the contained vitrified radioactive waste and with the external environments expected in possible final storage locations will be determined. These tests involve heating combinations of waste forms and canister metals in intimate contact for up to 50,000 hr to accelerate any r… more
Date: March 6, 1978
Creator: Rankin, W.N.
Partner: UNT Libraries Government Documents Department
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Scoping Report on Various Salt Mines in the United States

Description: One of the most important factors in isolating the demonstration waste storage site is an adequate number of shafts to insure proper ventilation. Proper ventilation will require that the air exhausted from the storage area pass directly to the upcast air shaft. Those mines reported by this scoping contract generally conform with the two shafts per mine requirement of MESA. Three of the mines reported on have more than two shafts. Several of the mines can have additional shafts drilled in time t… more
Date: July 1977
Creator: Jacoby, C. H.
Partner: UNT Libraries Government Documents Department
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Evaluation of environmental dosimetry models for applicability to possible radioactive waste repository discharges

Description: This report presents the results of a review of the available codes, for application to the National Waste Terminal Storage (NWTS) Program. Consideration was given to the types of radionuclides which may be of concern, the possible modes of release of these radionuclides and the various pathways by which members of the general public in the vicinity of a terminal storage facility may be exposed to the releases. Results reveal that the types and quantities of radioactive material requiring dispo… more
Date: September 1, 1977
Creator: Mauro, J. J.; Michlewicz, D. & Letizia, A.
Partner: UNT Libraries Government Documents Department
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Recovery of plutonium and americium from chloride salt wastes by solvent extraction

Description: Plutonium and americium can be recovered from aqueous waste solutions containing a mixture of HCl and chloride salt wastes by the coupling of two solvent extraction systems: tributyl phosphate (TBP) in tetrachloroethylene (TCE) and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in TCE. In the flowsheet developed, the salt wastes are dissolved in HCl, the Pu(III) is oxidized to the IV state with NaClO/sub 2/ and recovered in the TBP-TCE cycle, and the Am is then removed from t… more
Date: January 1, 1987
Creator: Reichley-Yinger, L. & Vandegrift, G.F.
Partner: UNT Libraries Government Documents Department
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Relevance of biotic pathways to the long-term regulation of nuclear waste disposal. A report on Tasks 1 and 2 of Phase I. [Shallow land burial]

Description: The purpose of the work reported here was to evaluate the relevance of biotic transport to the assessment of impacts and licensing of low-level waste disposal sites. Available computer models and their recent applications at low-level waste disposal sites are considered. Biotic transport mechanisms and processes for both terrestrial and aquatic systems are presented with examples from existing waste disposal sites. Following a proposed system for ranking radionuclides by their potential for bio… more
Date: July 1, 1982
Creator: McKenzie, D. H.; Cadwell, L. L.; Cushing, C. E. Jr.; Harty, R.; Kennedy, W. E. Jr.; Simmons, M. A. et al.
Partner: UNT Libraries Government Documents Department
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Energy Program annual report

Description: The national economy is particularly dependent on efficient electrical generation and transportation. Electrical demand continues to grow and will increasingly rely on coal and nuclear fuels. The nuclear power industry still has not found a solution to the problem of disposing of the waste produced by nuclear reactors. Although coal is in ample supply and the infrastructure is in place for its utilization, environmental problems and improved conversion processes remain technical challenges. In … more
Date: February 1, 1988
Creator: Borg, I.Y. (ed.)
Partner: UNT Libraries Government Documents Department
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Plutonium scrap recovery at Savannah River: Past, present, and vision of the future

Description: As a result of the changing requirement, plus environmental and regulatory commitments, SRP now has essentially completed its paradigm shift. SRP has been transformed from primarily a reprocessor of irradiated uranium targets to primarily a reprocessor of non-specification plutonium. This is the mission which will carry SRP into the 21st Century. Accomplishment of the defined goals for the three-pronged RandD program will achieve several objectives: exploit new processes for recovering low-grad… more
Date: January 1, 1988
Creator: Gray, Leonard W.; Gray, John H.; Blancett, Allen L.; Lower, William M. & Rudisill, Tracy S.
Partner: UNT Libraries Government Documents Department
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State-of-the-art for evaluating the potential impact of flooding on a radioactive waste repository

Description: This report is a review of the state-of-the-art for evaluating the potential impact of flooding on a deep radioactive-waste repository, namely, for predicting the future occurrence of catastrophic flooding and for estimating the effect of such flooding on waste containment characteristics. Several detrimental effects are identified: flooding can increase groundwater seepage velocities through a repository within the framework of the existing hydrologic system and thus increase the rate of radio… more
Date: July 16, 1980
Partner: UNT Libraries Government Documents Department
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Management of radioactive waste gases from the nuclear fuel cycle. Volume I. Comparison of alternatives

Description: Alternatives were compared for collection and fixation of radioactive waste gases released during normal operation of the nuclear fuel cycle, and for transportation and storage/disposal of the resulting waste forms. The study used a numerical rating scheme to evaluate and compare the alternatives for krypton-85, iodine-129, and carbon-14; whereas a subjective evaluation, based on published reports and engineering judgement, was made for transportation and storage/disposal options. Based on thes… more
Date: December 1, 1980
Creator: Evans, A. G.; Prout, W. E.; Buckner, J. T. & Buckner, M. R.
Partner: UNT Libraries Government Documents Department
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Response of a glass melter to steam explosion

Description: As part of the safety assessment in the design of the glass melter for large-scale immobilization of high-level radioactive wastes, structural considerations of the containment shell include its dynamic responses to abnormal loading conditions such as that caused by a steam explosion. The postulated steam explosion, conservatively given an energy content equivalent to 13 pounds of TNT, is capable of exerting sudden pressures greater than 300 psi but less than 410 psi on the melter wall. By use … more
Date: January 1, 1984
Creator: Yau, W. F. & Durant, W. S.
Partner: UNT Libraries Government Documents Department
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Environmental monitoring at major U. S. Energy Research and Development Administration contractor sites: calendar year 1976. Volume 2

Description: The purpose of this compilation is to present, in a central reference document, all of the individual annual reports summarizing the results of the environmental monitoring programs conducted at each of the Energy Research and Development Administration (ERDA) sites having a potential for environmental impact or which release a significant quantity of radioactivity or nonradioactive pollutants. Data on the levels of radioactivity and nonradioactive pollutants in effluents and the environs at ea… more
Date: August 1, 1977
Partner: UNT Libraries Government Documents Department
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Energy and protein production from pulp mill wastes. Progress report, June 15, 1977--September 15, 1977

Description: Experiments conducted during this past quarter demonstrated the decided difference both in amount and composition of the gas produced from the fermentation of ozonated versus unozonated yeast-plant SSL. Gas from ozonated SSL averaged over 80% methane content while unozonated effluent was mostly carbon dioxide. Gas production rates and retention time studies indicated that the fermentation was substrate-limited. Preliminary tests using supplemental carbon sources have verified this. The success … more
Date: September 15, 1977
Creator: Jurgensen, M. F. & Patton, J. T.
Partner: UNT Libraries Government Documents Department
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Facilities evaluation report

Description: The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes th… more
Date: April 1, 1992
Creator: Sloan, P.A. & Edinborough, C.R.
Partner: UNT Libraries Government Documents Department
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Preliminary assessment of tree mortality near F- and H-area seepage basins

Description: A preliminary assessment was conducted to evaluate factors that may have been responsible for the vegetation damage that has occurred in groundwater seeps downslope from the F- and H-area seepage basins. The factors that were considered included altered hydrology, toxicity from hazardous chemical constituents associated with seepage basin operation, and toxicity from non-hazardous constituents associated with basin operation. It was concluded that the observed damage was not likely to have resu… more
Date: January 28, 1988
Creator: Loehle, C & Gladden, J
Partner: UNT Libraries Government Documents Department
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Organic iodine removal from simulated dissolver off-gas streams using silver-exchanged mordenite

Description: The removal of methyl iodide by absorption onto silver mordenite was studied using a simulated off-gas from the fuel dissolution step of a nuclear fuel reprocessing plant. The methyl iodide absorption of silver mordenite was examined for the effects of NO/sub x/, humidity, iodine concentration, filter temperature, and filter pretreatment. The highest iodine loading achieved in these tests has been 34 mg CH/sub 3/I per g of substrate, approximately five times less than the elemental iodine loadi… more
Date: January 1, 1980
Creator: Jubin, R. T.
Partner: UNT Libraries Government Documents Department
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Studies of nuclear-waste migration in geologic media. Annual report, November 1976--October 1977

Description: The confinement of nuclear wastes in geologic formations is being considered as a method of permanently disposing of the waste. Laboratory experiments (column infiltration, static absorption, and batch partitioning experiments) were performed with nuclides of Cs, Pu, Np, and Am to examine the migratory characteristics of long-lived radionuclides that could be mobilized by groundwaters infiltrating a nuclear waste repository and the surrounding geologic body. In column infiltration experiments, … more
Date: March 1, 1978
Creator: Seitz, M.G.; Rickert, P.G.; Fried, S.M.; Friedman, A.M. & Steindler, M.J.
Partner: UNT Libraries Government Documents Department
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