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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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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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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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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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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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Waste Treatment and Disposal Progress Report for June and July 1961

Description: 7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scaven… more
Date: October 24, 1961
Creator: Blanco, R. E. & Struxness, E. G.
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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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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Geothermal waste treatment biotechnology: Progress and advantages to the utilities

Description: Development of biotechnology for treatment of geothermal residual waste is aimed at the application of low-cost biochemical processes for the surface treatment and disposal of residual geothermal sludges. These processes, in addition to the lowering of disposal cost, are designed to be environmentally acceptable. Recent studies at Brookhaven National Laboratory (BNL) have shown that optimization of several process variables results in fast rates (<24h) of metal removal from residual sludges at … more
Date: March 1, 1992
Creator: Premuzic, E.T.; Lin, M.S. & Jin, 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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LFCM vitrification technology. Quarterly progress report, January-March 1986

Description: This report is compiled by the Nuclear Waste Treatment Progrqam and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to document progress on liquid-fed ceramic melter (LFCM) vitrification technology. Progress in the following technical subject areas during the second quarter of FY 1986 is discussed: melting process chemistry and glass development, feed preparation and transfer systems, melter systems, canister filling and handling systems, off-gas systems, and process/pro… more
Date: September 1, 1986
Creator: Burkholder, H. C. & Minor, J. E.
Partner: UNT Libraries Government Documents Department
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Sodium Fluozirconate Precipitation Process for Zirconium Fuels. Part 1. Laboratory Development

Description: Precipitation, evaporation, and extraction feed preparation conditions are established for the removal of zirconium and fluoride from fuel dissolver product solutions by the addition of sodium formate. A sparingly soluble complex fluozirconate is formed. Ninety-five to 99% of the zirconium and fluoride is separated from the uranium losses of 0.1% or less. Chemical material balances, based on experimental data, were developed for two flowsheets. In one flowsheet, sufficient nitric acid is added … more
Date: May 15, 1962
Creator: Newby, B. J.
Partner: UNT Libraries Government Documents Department
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Westinghouse Hanford Company waste minimization and pollution prevention awareness program plan

Description: The purpose of this plan is to establish the Westinghouse Hanford Company's Waste Minimization Program. The plan specifies activities and methods that will be employed to reduce the quantity and toxicity of waste generated at Westinghouse Hanford Company (Westinghouse Hanford). It is designed to satisfy the US Department of Energy (DOE) and other legal requirements that are discussed in Subsection C of the section. The Pollution Prevention Awareness Program is included with the Waste Minimizati… more
Date: August 1, 1991
Creator: Craig, P.A.; Nichols, D.H. & Lindsey, D.W.
Partner: UNT Libraries Government Documents Department
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Characterization of radioactive ion exchange media waste generated at Three Mile Island

Description: The March 1979 accident at General Public Utilities Nuclear Corporation (GPUNC) Three Mile Island Nuclear Power Station Unit 2 (TMI-2), resulted in the transfer of more than 1100 m/sup 3/ of contaminated water to the auxiliary and fuel handling building. The principal sources of the water were the makeup and letdown purification system and the containment building sump. The contaminated water was processed through an ion exchange system designated as EPICOR II. The EPICOR-II System is a three-s… more
Date: October 1, 1981
Creator: Runion, T. C.; Holzworth, R. E.; Ogle, R. E.; Burton, H. M. & Bixby, W. W.
Partner: UNT Libraries Government Documents Department
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Tilt-pour melt-caster for encapsulation of radioactive cesium

Description: Use of the tilt-pour melt-caster makes distinct improvements in the cesium encapsulation process. Compared to the vacuum castings system now in use, the tilt-pour equipment requires no reliance on heat-traced transfer lines, less sealing pressure for capsule filling, is less corrosive to capsules and is easier to repair. From the results of the extensive development program, it is concluded that the tilt-pour melt-caster can be operated to meet the cesium encapsulation production and maintenanc… more
Date: January 1, 1977
Partner: UNT Libraries Government Documents Department
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Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: January--March 1978

Description: The exposure of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a beta dose of 10 ..mu..Ci/cm/sup 3/ and a gamma dose of 10/sup -5/ ..mu..Ci/cm/sup 3/ did not show any conclusive evidence of membrane degradation. Viscosity measurements for control membranes and irradiated membranes indicate no changes in polymer molecular weight were caused by the radiation exposure. This, in turn, suggests no physical or mechanical degradation took… more
Date: April 27, 1978
Creator: Koenst, J. W.; Herald, W. R. & Roberts, R. C.
Partner: UNT Libraries Government Documents Department
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Hot gas desulfurization with oxides of zinc, iron, and vanadium

Description: The objective of this study is to develop an improved sorbent which can reduce H{sub 2}S levels up to 1 ppmv or less, which can stabilize zinc, and produce economically recoverable amounts of elemental sulfur during regeneration. For this purpose, the desulfurization performance of sorbents prepared by the addition of various amounts of V{sub 2}O{sub 5} to the zinc ferrite sorbent is investigated.
Date: January 1, 1992
Creator: Akyurtlu, J.F. & Akyurtlu, A.
Partner: UNT Libraries Government Documents Department
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Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program

Description: The meeting consisted of the following six sessions: (1) plenary session I; (2) disposal technology; (3) characteristics and treatment of low-level waste; (4) environmental aspects and performance prediction; (5) overall summary sessions; and (6) plenary session II. Fifty two papers of the papers presented were processed for inclusion in the Energy Data Base. (ATT)
Date: December 1, 1983
Partner: UNT Libraries Government Documents Department
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CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Description: Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from … more
Date: September 21, 1961
Partner: UNT Libraries Government Documents Department
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Fifth in situ vitrification engineering-scale test of simulated INEL buried waste sites

Description: In September 1990, an engineering-scale in situ vitrification (ISV) test was conducted on sealed canisters containing a combined mixture of buried waste materials expected to be present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). The test was part of a Pacific Northwest Laboratory (PNL) program to assist INEL in treatability studies of the potential application of ISV to mixed transuranic wastes at the INEL SDA. The purpose of this test was to determine t… more
Date: June 1, 1992
Creator: Bergsman, T.M.; Shade, J.W. (Pacific Northwest Lab., Richland, WA (United States)) & Farnsworth, R.K. (EG and G Idaho, Inc., Idaho Falls, ID (United States))
Partner: UNT Libraries Government Documents Department
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Support of International Waste Management Agreements in the field of TRU Waste Management

Description: The USDOE has implemented technical information exchange agreements in the field of TRU waste management with the United Kingdom, Federal Republic of Germany, Japan, and France. This has been done in an effort to minimize research and development costs, and ensured maximum safety to man and the environment during waste handling and disposal. In this report, the technical work plan for fiscal year 1986 is presented. (JDL)
Date: January 1, 1986
Partner: UNT Libraries Government Documents Department
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