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Foundation Grouting Practices at Corps of Engineers Dams

Description: The purpose of the assessment is to provide background information on the Corps' practices, identify shortcomings in specifications, estimates, grout placement techniques, and, in general, to determine the effectiveness of the Corps' grouting programs. The report reviews past grouting projects and describes the planning, execution, and performance evaluation of the programs.
Date: October 1984
Creator: Albritton, John; Jackson, Lawson & Bangert, Robert
Partner: UNT Libraries Government Documents Department

Brief overview of the various families of grouts and their aplications

Description: It is difficult to maintain an up-to-date overview of all the grouts presently used on the international market. Better grouts are continuously developed and more formulators are making their appearance. Consequently, it is difficult to clearly define all of the products in the industry. This topic has been the subject of numerous papers and textbooks. Most authors, however, only focus on their fields of interest: applications in geotechnical, or rehabilitation, or seepage control in civil engineering, oil or mining industry. There has been a limited transfer of technology from one field to the other because of the enormous differences in magnitude, site conditions and consequently the application techniques. The tools an engineer has are: his expertise in grouting and engineering background, equipment available or to be designed or modified to carry out a particular job, relevant data available from other sciences, and products with a variety of characteristics. This paper concentrates on product selection. The most suitable product for a particular project requires a good understanding of the general chemical and mechanical characteristics of the grout. The grouts have been classified into four categories for the purpose of this paper. There may be other methods of classification; however, this is only an attempt to help the industry with the selection of the most suitable grout for a given application. The four categories are: suspension grouts, chemical grouts, hot melts, and precipitation grouts. 1 fig.
Date: April 1, 1989
Creator: Nandts, A.
Partner: UNT Libraries Government Documents Department

Grout performance in support of in situ grouting of the TH4 tank sludge

Description: The cold demonstration test proved that less water was required to pump the in situ grout formulation than had been previously tested in the laboratory. The previous in situ grout formulation was restandardized with the same relative amounts of dry blend ingredients, albeit adding a fluidized admixture, but specifying less water for the slurry mix that must by pumped through the nozzles at high pressure. Also, the target GAAT tank for demonstrating this is situ grouting technique has been shifted to Tank TH4. A chemical surrogate sludge for TH4 was developed and tested in the laboratory, meeting expectations for leach resistance and strenght at 35 wt % sludge loading. It addition, a sample of hot TH4 sludge was also tested at 35 wt % sludge loading and proved to have superior strength and leach resistance compared with the surrogate test.
Date: April 1999
Creator: Hunt, R. D.; Kauschinger, J. L. & Spence, R. D.
Partner: UNT Libraries Government Documents Department

Grout and Glass Performance in Support of Stabilization/Solidification of the MVST Tank Sludges

Description: Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) pending treatment for disposal. The waste separates into two phases: sludge and supematant. Some of the supematant from these tanks has been decanted, solidified into a grout, and stored for disposal as a solid low-level waste. The sludges in the tank bottoms have been accumulating ,for several years. Some of the sludges contain a high amount of gamma activity (e.g., `37CS concentration range of 0.01 3-11 MBq/g) and contain enough transuranic (TRU) radioisotopes to be classified as TRU wastes. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough in the available total constituent analysis for the MVST sludge to be classified as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste.
Date: November 1, 1998
Creator: Gilliam, T.M. & Spence, R.D.
Partner: UNT Libraries Government Documents Department

Radiolytic and Thermal Generation of Gases from Hanford Grout Samples : Interim Report

Description: Gamma irradiation of WHC-supplied samples of grouted Tank 102-AP simulated nonradioactive waste has been carried out at three dose rates, 0.25, 0.63, and 130 krad/hr. The low dose rate corresponds to that in the actual grout vaults; with the high dose rate, doses equivalent to more than 40 years in the grout vault were achieved. An average G(H2) = 0.047 molecules/100 eV was found, independent of dose rate. The rate of H2 production decreases above 80 Mrad. For other gases, G(N2) = 0.12, G(O2) = 0.026, G(N2O) = 0.011 and G(CO) = 0.0042 at 130 krad/hr were determined. At lower dose rates, N2 and O2 could not be measured because of interference by trapped air. The value of G(H2) is higher than expected, suggesting segregation of water from nitrate and nitrite salts in the grout. The total pressure generated by the radiolysis at 130 krad/h has been independently measured, and total amounts of gases generated were calculated from this measurement. Good agreement between this measurement and the sum of all the gases that were independently determined was obtained. Therefore, the individual gas measurements account for most of the major components that are generated by the radiolysis. At 90 C, H2, N2, and N2O were generated at a rate that could be described by exponential formation of each of the gases. Gases measured at the lower temperatures were probably residual trapped gases. An as yet unknown product interfered with oxygen determinations at temperatures above ambient. The thermal results do not affect the radiolytic findings.
Date: October 1993
Creator: Meisel, Dan; Jonah, Charles D.; Kapoor, S.; Matheson, Max S. & Mulac, W. A.
Partner: UNT Libraries Government Documents Department

A New Parameter to Assess Hydromechanical Effect in Single-hole Hydraulic Testing and Grouting

Description: Grouting or filling of the open voids in fractured rock is done by introducing a fluid, a grout, through boreholes under pressure. The grout may be either a Newtonian fluid or a Bingham fluid. The penetration of the grout and the resulting pressure profile may give rise to hydromechanical effects, which depends on factors such as the fracture aperture, pressure at the borehole and the rheological properties of the grout. In this paper, we postulate that a new parameter, {angstrom}, which is the integral of the fluid pressure change in the fracture plane, is an appropriate measure to describe the change in fracture aperture volume due to a change in effective stress. In many cases, analytic expressions are available to calculate pressure profiles for relevant input data and the {angstrom} parameter. The approach is verified against a fully coupled hydromechanical simulator for the case of a Newtonian fluid. Results of the verification exercise show that the new approach is reasonable and that the {angstrom}-parameter is a good measure for the fracture volume change: i.e., the larger the {angstrom}-parameter, the larger the fracture volume change, in an almost linear fashion. To demonstrate the application of the approach, short duration hydraulic tests and constant pressure grouting are studied. Concluded is that using analytic expressions for penetration lengths and pressure profiles to calculate the {angstrom} parameter provides a possibility to describe a complex situation and compare, discuss and weigh the impact of hydromechanical couplings for different alternatives. Further, the analyses identify an effect of high-pressure grouting, where uncontrolled grouting of larger fractures and insufficient (or less-than-expected) sealing of finer fractures is a potential result.
Date: September 1, 2007
Creator: Rutqvist, Jonny; Fransson, A.; Tsang, C.-F.; Rutqvist, J. & Gustafson, G.
Partner: UNT Libraries Government Documents Department

Uranium Metal Reaction Behavior in Water, Sludge, and Grout Matrices

Description: This report summarizes information and data on the reaction behavior of uranium metal in water, in water-saturated simulated and genuine K Basin sludge, and in grout matrices. This information and data are used to establish the technical basis for metallic uranium reaction behavior for the K Basin Sludge Treatment Project (STP). The specific objective of this report is to consolidate the various sources of information into a concise document to serve as a high-level reference and road map for customers, regulators, and interested parties outside the STP (e.g., external reviewers, other DOE sites) to clearly understand the current basis for the corrosion of uranium metal in water, sludge, and grout.
Date: May 27, 2009
Creator: Delegard, Calvin H. & Schmidt, Andrew J.
Partner: UNT Libraries Government Documents Department

Grout and Glass Performance Maximizing the Loading of ORNL Tank Sludges

Description: Grouting and vitrification are currently two likely stabilization and solidification alternatives for radioactive and hazardous mixed wastes stored at Department of Energy (DOE) facilities. Grouting has been used to stabilize and solidify hazardous and low-level radioactive waste for decades. Vitrification has been developed as a high-level radioactive alternative for decades and has been under development recently as a mixed-waste alternative disposal technology.
Date: March 1, 1999
Creator: Burgess, M. W.; Mattus, A. J.; Spence, R. D. & Travis, J. R.
Partner: UNT Libraries Government Documents Department

Idaho Nuclear Technology and Engineering Center Newly Generated Liquid Waste Demonstration Project Feasibility Study

Description: A research, development, and demonstration project for the grouting of newly generated liquid waste (NGLW) at the Idaho Nuclear Technology and Engineering Center is considered feasible. NGLW is expected from process equipment waste, decontamination waste, analytical laboratory waste, fuel storage basin waste water, and high-level liquid waste evaporator condensate. The potential grouted waste would be classed as mixed low-level waste, stabilized and immobilized to meet RCRA LDR disposal in a grouting process in the CPP-604 facility, and then transported to the state.
Date: February 1, 2000
Creator: Herbst, A.K.
Partner: UNT Libraries Government Documents Department

Evaluation of In Situ Grouting as a Potential Remediation Method for the Hanford Central Plateau Deep Vadose Zone

Description: The Deep Vadose Zone Treatability Test Plan for the Hanford Central Plateau report identifies in situ grouting as a potential remediation technology for the deep vadose zone and includes a planned effort to evaluate in situ grouting to provide information for future feasibility studies. This report represents the first step in this evaluation effort.
Date: January 11, 2011
Creator: Truex, Michael J.; Pierce, Eric M.; Nimmons, Michael J. & Mattigod, Shas V.
Partner: UNT Libraries Government Documents Department

Direct Grout Stabilization of High Cesium Salt Waste: Salt Alternative Phase III Feasibility Study

Description: The direct grout alternative is a viable option for treatment/stabilization and disposal of salt waste containing Cs-137 concentrations of 1-3 Ci/gal. The composition of the direct grout salt solution is higher in sodium salts and contains up to a few hundred ppm Cs-137 more than the current reference salt solution. However it is still similar to the composition of the current reference salt solution. Consequently, the processing, setting, and leaching properties (including TCLP for Cr and Hg) of the direct grout and current saltstone waste forms are very similar. The significant difference between these waste solutions is that the high cesium salt solution will contain between 1 and 3 Curies of Cs-137 per gallon compared to a negligible amount in the current salt solution. This difference will require special engineering and shielding for a direct grout processing facility and disposal units to achieve acceptable radiation exposure conditions. The Cs-137 concentration in the direct grout salt solution will also affect the long-term curing temperature of the waste form since 4.84 Watts of energy are generated per 1000 Ci of Cs-137. The temperature rise of the direct grout during long-term curing has been calculated by A. Shaddy, SRTC.1 The effect of curing temperature on the strength, leaching and physical durability of the direct grout saltstone is described in this report. At the present time, long term curing at 90 degrees C appears to be unacceptable because of cracking which will affect the structural integrity as evaluated in the immersion test. (The experiments conducted in this feasibility study do not address the effect of cracking on leaching of contaminants other than Cr, Hg, and Cs.) No cracking of the direct grout or reference saltstone waste forms was observed for samples cured at 70 degrees C. At the present time the implications of waste ...
Date: December 7, 1998
Creator: Langton, C.A.
Partner: UNT Libraries Government Documents Department

Completion report for the isolation and remediation of inactive liquid low-level radioactive waste tanks 7562, H-209, and T-30 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: A human health risk analysis was conducted on inactive tanks 7562, H-209 and T-30 to determine the method for remediating the tanks. Risk analysis results indicated that the health risk associated with these tanks were within or below the EPA range of concern of 1 {times} 10{sup {minus}4} to 1 {times} 10{sup {minus}6}. On the basis of these results, and with regulator approval, it was determined that either no action or in-place stabilization of the tanks would satisfy risk-based remediation goals. Therefore, a decision was made and approved by DOE to remediate these tanks in-place as a maintenance action. Tanks H-209 and T-30 were isolated from associated piping, electrical systems, and instrumentation and grouted in-place. Due to regulatory concerns over the location of tank 7562 relative to an area of subsurface soil contamination, tank 7562 was isolated from associated piping and instrumentation and left in-place empty. Completion of these maintenance actions has met the intent of the Federal Facility Agreement (FFA) for remediation of inactive tanks H-209 and T-30. EPA and Tennessee Department of Environment and Conservation (TDEC) will be requested to approve a change to the FFA removing tanks H-209 and T-30 from the Appendix F list of inactive tanks. The request for removal of tank 7562 from Appendix F will be submitted pending final disposition of the tank. Since the associated tank piping systems remain in-place, it will further be requested that these systems be included as individual sites in Appendix C of the FFA for future remedial consideration.
Date: December 1, 1996
Partner: UNT Libraries Government Documents Department

A new and superior ultrafine cementitious grout

Description: Sealing fractures in nuclear waste repositories concerns all programs investigating deep burial as a means of disposal. Because the most likely mechanism for contaminant migration is by dissolution and movement through groundwater, sealing programs are seeking low-viscosity sealants that are chemically, mineralogically, and physically compatible with the host rock. This paper presents the results of collaborative work directed by Sandia National Laboratories (SNL) and supported by Whiteshell Laboratories, operated by Atomic Energy of Canada, Ltd. The work was undertaken in support of the Waste Isolation Pilot Plant (WIPP), an underground nuclear waste repository located in a salt formation east of Carlsbad, NM. This effort addresses the technology associated with long-term isolation of nuclear waste in a natural salt medium. The work presented is part of the WIPP plugging and sealing program, specifically the development and optimization of an ultrafine cementitious grout that can be injected to lower excessive, strain-induced hydraulic conductivity in the fractured rock termed the Disturbed Rock Zone (DRZ) surrounding underground excavations. Innovative equipment and procedures employed in the laboratory produced a usable cement-based grout; 90% of the particles were smaller than 8 microns and the average particle size was 4 microns. The process involved simultaneous wet pulverization and mixing. The grout was used for a successful in situ test underground at the WIPP. Injection of grout sealed microfractures as small as 6 microns (and in one rare instance, 3 microns) and lowered the gas transmissivity of the DRZ by up to three orders of magnitude. Following the WIPP test, additional work produced an improved version of the grout containing particles 90% smaller than 5 microns and averaging 2 microns. This grout will be produced in dry form, ready for the mixer.
Date: April 1, 1997
Creator: Ahrens, E.H.
Partner: UNT Libraries Government Documents Department

Completion report for the isolation and remediation of inactive liquid low-level radioactive waste tanks LA-104, WC-7, and 4501-P at Oak Ridge National Laboratory, Oak Ridge, Tennessee

Description: This report provides documentation of the maintenance action completion for remediation of tanks LA-104, WC-7, and 4501-P at Oak Ridge National Laboratory. This report will serve as the remediation completion documentation for the request to remove these tanks from the Federal Facility Agreement listing.
Date: December 1, 1996
Partner: UNT Libraries Government Documents Department

Thermal denitration and mineralization of waste constituents

Description: In order to produce a quality grout from LLW using hydraulic cements, proper conditioning of the waste is essential for complete cement curing. Several technologies were investigated as options for conditions. Since the LLW is dilute, removal of all, or most, of the water will significantly reduce the final waste volume. Neutralization of the LLW is also desirable since acidic liquids to not allow cement to cure properly. The nitrate compounds are very soluble and easily leached from solid waste forms; therefore, denitration is desirable. Thermal and chemical denitration technologies have the advantages of water removal, neutralization, and denitration. The inclusion of additives during thermal treatment were investigated as a method of forming insoluable waste conditions.
Date: August 1, 1997
Creator: Nenni, J.A. & Boardman, R.D.
Partner: UNT Libraries Government Documents Department

Quality assurance plan for placement of cold-cap grout, demonstration vault, Hanford Grout Vault Program. Final report

Description: During FY 91, the U.S. Army Engineer Waterways Experiment Station (WES) developed a grout to be used as a cold cap, a nonradioactive layer, between the solidified waste and the cover blocks of a demonstration waste disposal vault at the U.S. Department of Energy Hanford Facility. This document recommends requirements for a quality assurance (QA) plan for field mixing and placing of the cold-cap grout during final closure of the demonstration vault. Preplacement activities emphasize selection and testing of materials that will match the performance of materials used in the WES grout. Materials sources and applicable American Society of Testing and Materials, American Concrete Institute, and American Petroleum Institute specifications and requirements are provided. Archiving of physical samples of materials is essential, in addition to careful maintenance of test reports and laboratory data. Full-scale field trial mixing and a detailed preconstruction conference are recommended. Placement activities focus on production and placement of a grout that remains sufficiently constant throughout all batches and meets performance requirements. QA activities must be coordinated between the batch plant and delivery site. Recommended sampling during placement includes cylinders cast for subsequent tests of compressive strength and for nondestructive evaluation and prisms cast for monitoring volume stability. A minimum of two lifts is recommended. Postplacement activities include long-term monitoring of the properties of grout specimens cast during placement. Minimum testing of cylinders includes pulse velocity, fundamental frequency, and unconfined compressive strength. Monitoring characteristics of the microstructure also are recommended. The QA plan should designate an organization to have responsibility for maintaining complete records, reports, and archived samples, including details of deviations from plans written before field placement.
Date: August 1, 1992
Creator: Harrington, P.T.; Wakeley, L.D.; Ernzen, J.J. & Walley, D.M.
Partner: UNT Libraries Government Documents Department

Cascade Line Testing for Hanford Single-Shell HLW Tank Closure

Description: Two proof-of-principle large-scale tests were performed to simulate the flow of grout into Hanford single-shell HLW Tanks and into cascade lines which interconnect the HLW tanks. The goal of the testing was to determine whether the HLW tank grout can enter the cascade line and solidify prior to flowing into an adjacent tank. Two tests were performed as part of this task. The tests were conducted using the Phase 2 Structural Grout, SRG2, the structural grout mix that was used during scale-up testing last year.
Date: December 2, 2004
Creator: JOHN, HARBOUR
Partner: UNT Libraries Government Documents Department

Hanford tank initiative cone penetrometer stand alone grouting module

Description: The HTI subsurface characterization task will use the Hanford Cone Penetrometer platform (CPP) to deploy contaminant sensor and soil sampling probes into the vadose zone surrounding SST 241-AX-104. Closure of the resulting penetration holes may be stipulated by WAC requirements. A stand alone grouting capability deployable by the CPP has been developed. This qualification test plan defines testing of this capability to be performed at the Immobilized Low Activity Waste Disposal Complex.
Date: October 15, 1998
Creator: CALLAWAY, W.S.
Partner: UNT Libraries Government Documents Department

Gas Generation from Hanford Grout Samples : Final Report

Description: The radiolytic yields of hydrogen nitrogen, oxygen, nitrous oxide, and carbon monoxide from two batches of WHC-supplied samples of grouted simulated waste have been (gamma) irradiated at several dose rates (0.025, 0.63 and 130 krad/h for hydrogen and 130 krad/h for all other gases). In one batch, the liquid waste simulant that was added to the grout included the original components that were added to Tank 102-AP (labeled "virgin" waste.) The second batch included a similar liquid waste simulant that was preirradiated to 35 Mrad prior to incorporation into the grout. It is believed that the preirradiated samples more closely represent radioactive waste that was stored in the tank for several years. The lowest dose rate corresponds approximately to that expected in the grout; with the high dose rate, doses equivalent to about 85 years storage in grout vaults were achieved. Most of the results on the batch of virgin samples have been reported recently (Report ANL 93/42). Here we report the results from the batch of preirradiated grout samples and compare the results from the two batches. The radiolytic yields of hydrogen and nitrogen are lower in the preirradiated than in the virgin grout. On the other hand G(oxygen) is higher in the preirradiated samples: 0.078 vs. 0.026. The yield of nitrous oxide is essentially the same, G(nitrous oxide) = 0.010, in both. The yields measured from both batches are significantly higher than previously reported values. At 90 C similar amounts of hydrogen were generated thermally from both batches of grout, whereas the total amounts of nitrogen and nitrous oxide were larger for the preirradiated than for the virgin grout samples. At lower temperatures the rate of generation was hardly measurable. Mass spectrometric analysis suggests that NO is thermally (but not radiolytically) released from the grout samples.
Date: March 1994
Creator: Jonah, Charles D.; Kapoor, S.; Matheson, Max S.; Mulac, W. A. & Meisel, Dan
Partner: UNT Libraries Government Documents Department

Grout Analysis for EC and CC Calorimeters

Description: The EC and CC calorimeters roll on Two parallel hardened steel ways which reside on the top of the D0 platform's center beam. The ways will be grouted to the center beam once their correct elevation has been established. The purpose of this report is to evaluate and compare three different epoxy grouts and their properties for this application.
Date: January 6, 1987
Creator: Engstrom, L.L.
Partner: UNT Libraries Government Documents Department

Unreviewed Disposal Question Evaluation: Disposal of 0.2 Curie/gallon MAVRC Project Equipment in Vault 1

Description: The Saltstone Facility 0.2 Curie/gallon MAVRC (Mixer At Vault Roof Concept) Project will utilize various pieces of process equipment that have not been analyzed from a Performance Assessment perspective for future disposal. The proposed activity will involve the disposal of Saltstone process equipment in an empty Vault 1 cell and encasing the equipment in clean (nonradioactive) grout. An examination of this activity indicates that the disposal of up to 20 pieces of each specified component should not affect the assumptions, results, and conclusions of the approved Performance Assessment (PA) and Special Analyses (SA) for Saltstone, and that the activity is within the bounds of the Disposal Authorization Statement (DAS).
Date: July 7, 2005
Creator: Millings, Margaret R.
Partner: UNT Libraries Government Documents Department