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Demonstration of In-Situ Stabilization of Buried Waste at Pit G-11 at the Brookhaven National laboratory Glass Pits Disposal Site

Description: In 1989 BNL was added to the EPAs National Priorities List. The site is divided into seven operable units (OU). OU-I includes the former landfill area. The field task site is noted as the AOC 2C Glass Holes location. Beginning in the 1960s and continuing into the 1980s, BNL disposed of laboratory waste (glassware, chemicals and animal carcasses) in numerous shallow pits. The drivers for remediating the pits are; historical records that indicate hazardous materials may have been disposed of in the pits; ground water contamination down gradient of the pits; a test excavation of one of the glass holes that unearthed laboratory glass bottles with unidentified liquids still contained; and the fact that BNL rests atop an EPA designated sole-source aquifer. The specific site chosen for this demonstration was pit G-11. The requirements that lead to choosing this pit were; a well characterized pit and a relatively isolated pit where our construction operations would not impact on adjacent pits. The glass holes area, including pit G-11, was comprehensively surveyed using a suite of geophysical techniques (e.g., EM-31, EM-61, GPR). Prior to stabilizing the waste form a subsurface barrier was constructed to contain the entire waste pit. The pit contents were then stabilized using a cement grout applied via jet grouting. The stabilization was performed to make removal of the waste from the pit easier and safer in terms of worker exposure. The grouting process would mix and masticate the waste and grout and form a single monolithic waste form. This large monolith would then be subdivided into smaller 4 foot by 4 foot by 10-12 foot block using a demolition grout. The smaller blocks would then be easily removed from the site and disposed of in a CERCLA waste site.
Date: January 1, 1999
Creator: Dwyer, B.P.; Gilbert, J. & Heiser, J.
Partner: UNT Libraries Government Documents Department

Characterization Plan for the Old Hydrofracture Facility

Description: US Department of Energy (DOE) facilities are required to comply fully with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established the remedial action program, to provide comprehensive management of areas where past research, development, and waste management activities have been conducted and have resulted in residual contamination of facilities or the environment. One of the objectives of this program is to define the extent of contamination at these sites. The intent is to document the known environmental characteristics of the sites and identify the additional actions, such as sampling, analytical measurements, and modeling, necessary to confirm contamination and the possible migration of contaminants from the sites. One of these sites is the Old Hydrofracture Facility (OHF). The OHF was used for the permanent disposal of liquid radioactive waste in impermeable shale formations at depths ranging from about 230 to 300 m (750 to 1000 ft), from 1964 to 1979. The liquid waste was blended into a pumpable grout by mixing it with cement and special clays used to immobilize radionuclides against groundwater transport. This report summarizes the results of several studies at ORNL that have measured the concentration of radionuclides and, to some extent, concentrations of hazardous chemicals in the sediment of the impoundment, as well as the concentrations in soils and groundwater near the facility. The report addresses only the contamination of and the potential releases to the environment that might result from the facility per se and makes not attempt to address potential releases that might result from permanent disposal of wastes (i.e., the grout sheets) during its operation. Outlined in the report are the additional actions needed to obtain the information required to confirm the extent of contamination within the facility. The major efforts include the measurement ...
Date: January 1, 1999
Creator: Francis, C.W.
Partner: UNT Libraries Government Documents Department

Biodenitrification in Sequencing Batch Reactors. Final report

Description: One plan for stabilization of the Solar Pond waters and sludges at Rocky Flats Plant (RFP), is evaporation and cement solidification of the salts to stabilize heavy metals and radionuclides for land disposal as low-level mixed waste. It has been reported that nitrate (NO{sub 3}{sub {minus}}) salts may interfere with cement stabilization of heavy metals and radionuclides. Therefore, biological nitrate removal (denitrification) may be an important pretreatment for the Solar Pond wastewaters at RFP, improving the stability of the cement final waste form, reducing the requirement for cement (or pozzolan) additives and reducing the volume of cemented low-level mixed waste requiring ultimate disposal. A laboratory investigation of the performance of the Sequencing Batch Reactor (SBR) activated sludge process developed for nitrate removal from a synthetic brine typical of the high-nitrate and high-salinity wastewaters in the Solar Ponds at Rocky Flats Plant was carried out at the Environmental Engineering labs at the University of Colorado, Boulder, between May 1, 1994 and October 1, 1995.
Date: January 23, 1996
Creator: Silverstein, J.
Partner: UNT Libraries Government Documents Department

Physical barriers formed from gelling liquids: 1. numerical design of laboratory and field experiments

Description: The emplacement of liquids under controlled viscosity conditions is investigated by means of numerical simulations. Design calculations are performed for a laboratory experiment on a decimeter scale, and a field experiment on a meter scale. The purpose of the laboratory experiment is to study the behavior of multiple gout plumes when injected in a porous medium. The calculations for the field trial aim at designing a grout injection test from a vertical well in order to create a grout plume of a significant extent in the subsurface.
Date: January 1, 1994
Creator: Finsterle, S.; Moridis, G.J.; Pruess, K. & Persoff, P.
Partner: UNT Libraries Government Documents Department

Integrated nonthermal treatment system study

Description: This report presents the results of a study of nonthermal treatment technologies. The study consisted of a systematic assessment of five nonthermal treatment alternatives. The treatment alternatives consist of widely varying technologies for safely destroying the hazardous organic components, reducing the volume, and preparing for final disposal of the contact-handled mixed low-level waste (MLLW) currently stored in the US Department of Energy complex. The alternatives considered were innovative nonthermal treatments for organic liquids and sludges, process residue, soil and debris. Vacuum desorption or various washing approaches are considered for treatment of soil, residue and debris. Organic destruction methods include mediated electrochemical oxidation, catalytic wet oxidation, and acid digestion. Other methods studied included stabilization technologies and mercury separation of treatment residues. This study is a companion to the integrated thermal treatment study which examined 19 alternatives for thermal treatment of MLLW waste. The quantities and physical and chemical compositions of the input waste are based on the inventory database developed by the US Department of Energy. The Integrated Nonthermal Treatment Systems (INTS) systems were evaluated using the same waste input (2,927 pounds per hour) as the Integrated Thermal Treatment Systems (ITTS). 48 refs., 68 figs., 37 tabs.
Date: January 1, 1997
Creator: Biagi, C.; Bahar, D.; Teheranian, B.; Vetromile, J.; Quapp, W.J.; Bechtold, T. et al.
Partner: UNT Libraries Government Documents Department

Innovative grout/retrieval demonstration final report

Description: This report presents the results of an evaluation of an innovative retrieval technique for buried transuranic waste. Application of this retrieval technique was originally designed for full pit retrieval; however, it applies equally to a hot spot retrieval technology. The technique involves grouting the buried soil waste matrix with a jet grouting procedure, applying an expansive demolition grout to the matrix, and retrieving the debris. The grouted matrix provides an agglomeration of fine soil particles and contaminants resulting in an inherent contamination control during the dusty retrieval process. A full-scale field demonstration of this retrieval technique was performed on a simulated waste pit at the Idaho National Engineering Laboratory. Details are reported on all phases of this proof-of-concept demonstration including pit construction, jet grouting activities, application of the demolition grout, and actual retrieval of the grouted pit. A quantitative evaluation of aerosolized soils and rare earth tracer spread is given for all phases of the demonstration, and these results are compared to a baseline retrieval activity using conventional retrieval means. 8 refs., 47 figs., 10 tabs.
Date: January 1, 1995
Creator: Loomis, G.G. & Thompson, D.N.
Partner: UNT Libraries Government Documents Department

Utilization of the MPI Process for in-tank solidification of heel material in large-diameter cylindrical tanks

Description: A major problem faced by the US Department of Energy is remediation of sludge and supernatant waste in underground storage tanks. Exhumation of the waste is currently the preferred remediation method. However, exhumation cannot completely remove all of the contaminated materials from the tanks. For large-diameter tanks, amounts of highly contaminated ``heel'' material approaching 20,000 gal can remain. Often sludge containing zeolite particles leaves ``sand bars'' of locally contaminated material across the floor of the tank. The best management practices for in-tank treatment (stabilization and immobilization) of wastes require an integrated approach to develop appropriate treatment agents that can be safely delivered and mixed uniformly with sludge. Ground Environmental Services has developed and demonstrated a remotely controlled, high-velocity jet delivery system termed, Multi-Point-Injection (MPI). This robust jet delivery system has been field-deployed to create homogeneous monoliths containing shallow buried miscellaneous waste in trenches [fiscal year (FY) 1995] and surrogate sludge in cylindrical (FY 1998) and long, horizontal tanks (FY 1999). During the FY 1998 demonstration, the MPI process successfully formed a 32-ton uniform monolith of grout and waste surrogates in about 8 min. Analytical data indicated that 10 tons of zeolite-type physical surrogate were uniformly mixed within a 40-in.-thick monolith without lifting the MPI jetting tools off the tank floor. Over 1,000 lb of cohesive surrogates, with consistencies similar to Gunite and Associated Tank (GAAT) TH-4 and Hanford tank sludges, were easily intermixed into the monolith without exceeding a core temperature of 100 F during curing.
Date: January 1, 2000
Creator: Kauschinger, J.L. & Lewis, B.E.
Partner: UNT Libraries Government Documents Department

Acid Pit Stabilization Project (Volume 1 - Cold Testing) and (Volume 2 - Hot Testing)

Description: During the summer and fall of Fiscal Year 1997, a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Treatability Study was performed at the Idaho National Engineering and Environmental Laboratory. The study involved subsurface stabilization of a mixed waste contaminated soil site called the Acid Pit. This study represents the culmination of a successful technology development effort that spanned Fiscal Years 1994-1996. Research and development of the in situ grout stabilization technique was conducted. Hardware and implementation techniques are currently documented in a patent pending with the United States Patent and Trademark Office. The stabilization technique involved using jet grouting of an innovative grouting material to form a monolith out of the contamination zone. The monolith simultaneously provides a barrier to further contaminant migration and closes voids in the soil structure against further subsidence. This is accomplished by chemical incorporation of contaminants into less soluble species and achieving a general reduction in hydraulic conductivity within the monolith. The grout used for this study was TECT-HG, a relatively dense iron oxide-based cementitious grout. The treatability study involved cold testing followed by in situ stabilization of the Acid Pit. Volume 1 of this report discusses cold testing, performed as part of a ''Management Readiness Assessment'' in preparation for going hot. Volume 2 discusses the results of the hot Acid Pit Stabilization phase of this project. Drilling equipment was specifically rigged to reduce the spread of contamination, and all grouting was performed under a concrete block containing void space to absorb any grout returns. Data evaluation included examination of implementability of the grouting process and an evaluation of the contaminant spread during grouting. Following curing of the stabilized pit, cores were obtained and evaluated for toxicity characteristic leach ing procedure protocol for the main contaminant of concern, which was mercury. In addition, the ...
Date: January 1, 1998
Creator: Loomis, Guy G.; Zdinak, Andrew P.; Ewanic, Mark A. & Jessmore, James J.
Partner: UNT Libraries Government Documents Department

Laboratory Evaluation of Underwater Grouting of CPP-603 Basins

Description: A project is underway to deactivate a Fuel Storage Basin. The project specifies the requirements and identifies the tasks that will be performed for deactivation of the CPP- 603 building at the Idaho Nuclear Technology and Engineering Center of the Idaho National Engineering and Environmental Laboratory. The Fuel Receiving and Storage Building (CPP- 603) was originally used to receive and store spent nuclear fuel from various facilities. The area to undergo deactivation includes the three spent nuclear fuel storage basins and a transfer canal (1.5 million gallons of water storage). Deactivation operations at the task site include management of the hot storage boxes and generic fuel objects, removal of the fuel storage racks, basin sludge, water evaporation and basin grouting, and interior equipment, tanks, and associated components. This includes a study to develop a grout formulation and placement process for this deactivation project. Water will be allowed to passively evaporate to r educe the spread of contamination from the walls of the basin. The basins will be filled with grout, underwater, as the water evaporates to maintain the basin water at a safe level. The objective of the deactivation project is to eliminate potential exposure to hazardous and radioactive materials and eliminate potential safety hazards associated with the CPP-603 building.
Date: January 17, 2002
Creator: Johnson, V.J.; Pao, J.H.; Demmer, R.L. & Tripp, J.L.
Partner: UNT Libraries Government Documents Department

1987 Oak Ridge model conference: Proceedings: Volume I, Part 2, Waste Management

Description: A conference sponsored by the United States Department of Energy (DOE) was held on Waste Mangement. Topics discussed were waste stabilization technologies regulations and standards, innovative treatment technology, waste stabilization projects. Individual projects are processed separately for the data bases. (CBS)
Date: January 1, 1987
Partner: UNT Libraries Government Documents Department

Development of potential uses for the residue from fluidized bed combustion processes. Quarterly technical progress report, June-August 1980

Description: The following conclusions are recorded: The road base mixes in which quartz silica was substituted for the pulverized coal fly ash gave compressive strengths similar to those using the pulverized coal fly ash. The compressive strengths of road base mixes using recently produced AFB residue were of the same order of magnitude as those obtained in 1977, although the data covers a broad range of test results. Briquettes, produced from a number of trial mixes, show promise as a synthetic aggregate. Expansive grout mixes of slurry consistency achieve satisfactory compressive strengths in seven days. Sections of the test strips in Canton, Ohio show minimal expansion.
Date: January 1, 1980
Creator: Minnick, L.J.
Partner: UNT Libraries Government Documents Department

Closure of the Oak Ridge National Laboratory Hydrofracture Facility: An opportunity to study the fate of radioactive wastes disposed of by subsurface injection

Description: At Oak Ridge National Laboratory, subsurface injection has been used to dispose of liquid low-level nuclear waste for the past two decades. The process consists of mixing the liquid waste with cement and other additives to form a slurry that is injected under pressure through a cased well into a low-permeability shale at a depth of approximately 300 m (1000 ft). The slurry spreads from the well along hydraulic fractures and sets to form irregularly shaped grout sheets of up to 200 m (650 ft) in radius. Closure-related site characterization provides a unique opportunity to study the fate of the injected wastes. A series of monitoring wells are in place to measure groundwater chemistries within the injection strata and within overlying and underlying confining units. Initial results indicate that contaminated groundwater surrounds the grout sheets in the injection zone, extending at least as far as 300 m (1000 ft) from the injection well; contaminated groundwater is largely and perhaps exclusively confined to the host formation; and of the /sup 90/Sr and /sup 137/Cs radionuclides disposed of, only /sup 90/Sr is present in the contaminated groundwater. The illite-rich mineralogy of the injection formation strongly absorbs /sup 137/Cs and greatly retards its migration. Movement of /sup 90/Sr is not as greatly retarded by the injection formation. Geochemical modeling is being used to identify and to evaluate hydrogeological controls on /sup 90/Sr behavior. Preliminary results suggest that the groundwaters within the injection formation are saturated with Sr from natural sources, and that /sup 90/Sr mobility may be lessened by precipitation/dissolution reactions associated with such a saturated condition. 27 refs., 4 figs., 2 tabs.
Date: January 1, 1987
Creator: Haase, C.S.; Von Damm, K.L. & Stow, S.H.
Partner: UNT Libraries Government Documents Department

In situ grouting of buried transuranic waste with polyacrylamide

Description: This project is a demonstration and evaluation of the in situ hydrologic stabilization of buried transuranic waste at a humid site via grout injection. Two small trenches, containing buried transuranic waste, were filled with 34.000 L of polyacrylamide grout. Initial field results have indicated that voids within the trenches were totally filled by the grout and that the intratrench hydraulic conductivity was reduced to below field-measurable values. No evidence of grout constituents were observed in twelve perimeter groundwater monitoring wells indicating that grout was contained completely within the two trenches. Polyacrylamide grout was selected for field demonstration over the polyacrylate grout due to its superior performance in laboratory degradation studies. Also supporting the selection of polyacrylamide was the difficulty in controlling the set time of the acrylate polymerization. Based on preliminary degradation monitoring, the polyacrylamide was estimated to have a microbiological half-life of 362 years in the test soil. 15 refs., 9 figs., 12 tabs.
Date: January 1, 1987
Creator: Spalding, B.P.; Lee, S.Y.; Farmer, C.D.; Hyder, L.K. & Supaokit, P.
Partner: UNT Libraries Government Documents Department

Underground stress engineering: the lifting and stabilization of underground voids

Description: The theoretical basis of how grout, i.e., concrete, pumped into rock fractures prevents the caving of underground tunnel and cavity roofs is presented, and the calculation of how much grout material must be injected to lift a dome and create a useful rubble stope in an underground cavity is described. (LCL)
Date: January 1, 1977
Creator: Colgate, S.A.; Petschek, A.G.; Browning, R.V. & Bowers, N.K.
Partner: UNT Libraries Government Documents Department

Disposal of liquid radioactive wastes through wells or shafts

Description: This report describes disposal of liquids and, in some cases, suitable solids and/or entrapped gases, through: (1) well injection into deep permeable strata, bounded by impermeable layers; (2) grout injection into an impermeable host rock, forming fractures in which the waste solidifies; and (3) slurrying into excavated subsurface cavities. Radioactive materials are presently being disposed of worldwide using all three techniques. However, it would appear that if the techniques were verified as posing minimum hazards to the environment and suitable site-specific host rock were identified, these disposal techniques could be more widely used.
Date: January 1, 1982
Creator: Perkins, B.L.
Partner: UNT Libraries Government Documents Department

Subsurface stabilization by grouting of a simulated underground tank

Description: A moisture barrier using water, sodium silicate, formamide, calcium chloride and penechem with a gel time of one-half hour was constructed around a simulated tank 10 feet deep by 10 feet diameter in the subsurface of the 200 West Area. As a test of the moisture barrier integrity, the volume which would normally be occupied by a tank was excavated and filled with water. The barrier was unable to contain the water. The failure to achieve a water-tight barrier was attributed to a leak in the floor grout.
Date: January 27, 1977
Creator: Wiater, P.J. & Higley, B.A.
Partner: UNT Libraries Government Documents Department

Waste disposal by hydrofracture and application of the technology to the management of hazardous wastes

Description: A unique disposal method, involving hydrofracturing, has been used for management of liquid low-level radioactive wastes at Oak Ridge National Laboratory (ORNL). Wastes are mixed with cement and other solids and injected along bedding plane fractures into highly impermeable shale at a depth of 300 m forming a grout sheet. The process has operated successfully for 20 years and may be applicable to disposal of hazardous wastes. The cement grout represents the primary barrier for immobilization of the wastes; the hydrologically isolated injection horizon represents a secondary barrier. At ORNL work has been conducted to characterize the geology of the disposal site and to determine its relationship to the injection process. The site is structurally quite complex. Research has also been conducted on the development of methods for monitoring the extent and orientation of the grout sheets; these methods include gamma-ray logging of cased observation wells, leveling surveys of benchmarks, tiltmeter surveys, and microseismic arrays. These methods, some of which need further development, offer promise for real-time and post-injection monitoring. Initial suggestions are offered for possible application of the technology to hazardous waste management and technical and regulatory areas needing attention are addressed. 11 refs., 1 fig.
Date: January 1, 1985
Creator: Stow, S.H.; Haase, C.S. & Weeren, H.O.
Partner: UNT Libraries Government Documents Department

Grout pump selection process for the Transportable Grout Facility

Description: Selected low-level radioactive liquid wastes at Hanford will be disposed by grouting. Grout is formed by mixing the liquid wastes with solid materials, including Portland cement, fly ash, and clay. The mixed grouts will be pumped to disposal sites (e.g., trenches and buried structures) where the grout will be allowed to harden and, thereby, immobilize the wastes. A Transportable Grout Facility (TGF) will be constructed and operated by Rockwell Hanford Operations to perform the grouting function. A critical component of the TGF is the grout pump. A preliminary review of pumping requirements identified reciprocating pumps and progressive cavity pumps as the two classes of pumps best suited for the application. The advantages and disadvantages of specific types of pumps within these two classes were subsequently investigated. As a result of this study, the single-screw, rotary positive displacement pump was identified as the best choice for the TGF application. This pump has a simple design, is easy to operate, is rugged, and is suitable for a radioactive environment. It produces a steady, uniform flow that simplifies suction and discharge piping requirements. This pump will likely require less maintenance than reciprocating pumps and can be disassembled rapidly and decontaminated easily. If the TGF should eventually require discharge pressures in excess of 500 psi, a double-acting duplex piston pump is recommended because it can operate at low speed, with only moderate flow rate fluctuations. However, the check valves, stuffing box, piston, suction, and discharge piping must be designed carefully to allow trouble-free operations.
Date: January 1, 1985
Creator: McCarthy, D. & Treat, R.L.
Partner: UNT Libraries Government Documents Department

Corrective measures technology for humid sites

Description: The corrective measures technology task for humid sites consists of three subtasks. The first subtask has the objective of demonstrating that grout injection into closed burial trenches can achieve the hydrologic isolation of buried wastes. From laboratory testing of seven grout formulations, two promising grouts, 7.6% sodium silicate and 11.7% acrylamide, were selected for field demonstration by injection into 1:10-scale burial trenches. Both grouts effected a several orders of magnitude reduction in the mean hydraulic conductivity of the trench. The trench chemical treatment subtask has the objective of demonstrating the caustic soda injection into a closed trench's backfill and surrounding soil can achieve a fixation of radiostrontium from further ground water contamination. Monitoring of ground waters in and around the treated trench indicate a continued fixation of radiostrontium from further leaching. Soil samples were taken from the trench and found to contain /sup 90/Sr coprecipitated with calcium carbonate. The final subtask has the objective of demonstrating that the detection and treatment of ground water seeps can achieve a significant reduction in radiostrontium contamination of surface water. The utility of measuring /sup 90/Sr in ground water samples by Cerenkov radiation detection was found to be analytically equivalent to but considerably less expensive and time consuming than the standard radiochemical method.
Date: January 1, 1983
Creator: Spalding, B.P.
Partner: UNT Libraries Government Documents Department

Flow of cavity gas along fractures, cable bundles, and grouted cables

Description: Analytical and numerical solutions are presented for gas flow along isolated fractures in permeable media. Two different cases are considered: preexisting fractures with a uniform aperture, as well as hydraulically-driven fractures with a variable aperture which is proportional to the local overpressure (local fluid pressure less confining stress). Results for these two geometries are compared with one another and with results for wedge-shaped and penny-shaped fracture geometries. Application to underground nuclear testing is illustrated by a number of examples including: flow along shock-induced and hydraulically-induced fractures, seepage along single electrical cables surrounded by grout, and flow along a bundle of electrical cables surrounded by granular stemming material. 15 refs., 13 figs.
Date: January 1, 1985
Creator: Nilson, R.H. & Morrison, F.A. Jr.
Partner: UNT Libraries Government Documents Department

Shallow land burial technology: humid

Description: Applying engineered modifications to present shallow land burial (SLB) practices is one method of ensuring safe operation and improving overall disposal-site performance. Two such engineered modifications, trench lining and grouting, are being demonstrated and evaluated at the Oak Ridge National Laboratory (ORNL) Engineered Test Facility (ETF), using nine 28-m/sup 3/ experimental trenches containing compacted low-level waste (LLW). Concurrent to this field demonstration experiment, two finite-element hydrologic models have been developed to model water movement and solute transport at a waste disposal site. This paper covers progress made in these two areas during FY 1984. Though the economic analysis of the two trench treatments favored Hypalon lining (lining costs were 33% lower at this demonstration scale), results of field experiments examining waste hydrologic isolation favored the cement-bentonite grout treatment. Data from water pump-out and water pump-in tests, combined with observed intratrench water-level fluctuations, suggest that the original goal of constructing watertight liners in three experimental trenches was not achieved. In addition, trench-cover subsidence of approx. 2% of the total trench depth has been measured over two of the three lined trenches but has not occurred over any of the three grouted or three control (untreated) trenches. The evaluation of the two trench treatments is continuing. However, results indicate that the cement-bentonite treatment, implemented at a cost of $160/m/sup 3/ of grout, provides a degree of waste isolation not afforded by the lined and control trenches and should be considered for use at SLB sites with water-related problems. 11 references, 6 figures, 2 tables.
Date: January 1, 1984
Creator: Davis, E.C. & Yeh, G.T.
Partner: UNT Libraries Government Documents Department

Shallow Land Burial Technology - Humid

Description: The Shallow Land Burial Technology - Humid Project is being conducted for the Department of Energy Low-Level Waste Management Program with the objective of identifying and demonstrating improved technology for disposing of low-level solid waste in humid environments. Two improved disposal techniques are currently being evaluated using nine demonstration trenches at the Engineered Test Facility (ETF). The first is use of a cement-bentonite grout applied as a waste backfill material prior to trench closure and covering. The second is complete hydrologic isolation of waste by emplacement in a trench that is lined on all four sides, top and bottom using synthetic impermeable lining material. An economic analysis of the trench grouting and lining demonstration favored the trench lining operation ($1055/demonstration trench) over trench grouting ($1585/demonstration trench), with the cost differential becoming even greater (as much as a factor of 6 in favor of lining for typical ORNL trenches) as trench dimensions increase and trench volumes exceed those of the demonstration trenches. In addition to the evaluation of trench grouting and lining, major effort has centered on characterization of the ETF site. Though only a part of the overall study, characterization is an extremely important component of the site selection process; it is during these activities that potential problems, which may obviate the site from further consideration, are found. Characterization of the ETF has included studies of regional and site-specific geology, the physical and chemical properties of the soils in which the demonstration trenches are located, and hydrology of the small watershed of which the ETF is a part. 12 references, 6 figures, 2 tables.
Date: January 1, 1983
Creator: Davis, E.C.; Spalding, B.P. & Lee, S.Y.
Partner: UNT Libraries Government Documents Department

Test Area for Remedial Actions (TARA) site characterization and dynamic compaction of low-level radioactive waste trenches

Description: As part of a low-level radioactive waste burial ground stabilization and closure technology demonstration project, a group of five burial trenches in Oak Ridge National Laboratory (ORNL) Solid Waste Storage Area (SWSA) 6 was selected as a demonstration site for testing trench compaction, trench grouting, and trench cap installation and performance. This report focuses on site characterization, trench compaction, and grout-trench leachate compatibility. Trench grouting and cap design and construction will be the subject of future reports. The five trenches, known as the Test Area for Remedial Actions (TARA) site, are contained within a hydrologically isolated area of SWSA 6; for that reason, any effects of stabilization activities on site performance and groundwater quality will be separable from the influence of other waste disposal units in SWSA 6. To obviate the chronic problem of burial trench subsidence and to provide support for an infiltration barrier cap, these five trenches were dynamically compacted by repeated dropping of a 4-ton weight onto each trench from heights of approximately 7 m.
Date: January 1, 1989
Creator: Davis, E.C.; Spalding, B.P.; Lee, S.Y. & Hyder, L.K.
Partner: UNT Libraries Government Documents Department

G-tunnel welded tuff mining experiment preparations

Description: Designers and analysts of radioactive waste repositories must be able to predict the mechanical behavior of the host rock. Sandia National Laboratories elected to conduct a mine-by in welded tuff so that predictive-type information could be obtained regarding the response of the rock to a drill and blast excavation process, where smooth blasting techniques were used. Included in the study were evaluations of and recommendations for various measurement systems that might be used in future mine-by efforts. This report summarizes the preparations leading to the recording of data. 17 refs., 27 figs., 5 tabs.
Date: January 1, 1991
Creator: Zimmerman, R.M.; Bellman, R.A. Jr.; Mann, K.L. & Zerga, D.P.
Partner: UNT Libraries Government Documents Department