National Library of Energy BETA

Sample records for replace brine disposal

  1. Environmental assessment of the brine pipeline replacement for the Strategic Petroleum Reserve Bryan Mound Facility in Brazoria County, Texas

    SciTech Connect (OSTI)

    Not Available

    1993-09-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA-0804, for the proposed replacement of a deteriorated brine disposal pipeline from the Strategic Petroleum Reserve (SPR) Bryan Mound storage facility in Brazoria County, Texas, into the Gulf of Mexico. In addition, the ocean discharge outfall would be moved shoreward by locating the brine diffuser at the end of the pipeline 3.5 miles offshore at a minimum depth of 30 feet. The action would occur in a floodplain and wetlands; therefore, a floodplain/wetlands assessment has been prepared in conjunction with this EA. Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969 (42 USC. 4321, et seg.). Therefore, the preparation of an Environmental Impact Statement (EIS) is not required, and the Department is issuing this Finding of No Significant Impact (FONSI). This FONSI also includes a Floodplain Statement of Findings in accordance with 10 CFR Part 1022.

  2. Evaluation of brine disposal from the Bryan Mound site of the strategic petroleum reserve program. Final report

    SciTech Connect (OSTI)

    Case, Robert J.; Chittenden, Jr, Mark E.; Harper, Jr, Donald E.; Kelly, Jr, Francis J.; Loeblich, Laurel A.; McKinney, Larry D.; Minello, Thomas J.; Park, E. Taisoo; Randall, Robert E.; Slowey, J. Frank

    1981-01-01

    On March 10, 1980, the Department of Energy's Strategic Petroleum Reserve Program began leaching the Bryan Mound salt dome and discharging the resulting brine into the coastal waters off Freeport, Texas. During the months of March and April, a team of scientists and engineers from Texas A and M University conducted an intensive environmental study of the area surrounding the diffuser site. A pipeline has been laid from the Bryan Mound site to a location 12.5 statute miles (20 km) offshore. The last 3060 ft (933 m) of this pipeline is a 52-port diffuser through which brine can be discharged at a maximum rate of 680,000 barrels per day. Initially, 16 ports were open which permitted a maximum discharge rate of 350,000 barrels per day and a continuous brine discharge was achieved on March 13, 1980. The purpose of this report is to describe the findings of the project team during the intensive postdisposal study period of March and April, 1980. The major areas of investigation are physical oceanography, analysis of the discharge plume, water and sediment quality, nekton, benthos, phytoplankton, zooplankton, and data management.

  3. Evaluation of brine disposal from the Bryan Mound site of the Strategic Petroleum Reserve Program. Final report

    SciTech Connect (OSTI)

    Hann, R.W. Jr.; Randall, R.E.

    1980-12-01

    The purpose of this report is to describe the environmental conditions found by the principal investigators during the predisposal study conducted from September 1977 through February 1980 prior to the start of brine discharge in March 1980. The major areas of investigation are physical oceanography, analysis of the discharge plume, water and sediment quality, nekton, benthos, phytoplankton, zooplankton, and data management. Volume 1 describes the results of the predisposal study, and it is divided into eight chapters entitled: Physical Oceanography, Analysis of the Discharge Plume, Water and Sediment Quality, Nekton, Benthos, Zooplankton, Phytoplankton, and Data Management. Volume 2 consists of appendices which contain additional supporting data in the form of figures and tables.

  4. Fate of Magnesium Chloride Brine Applied to Suppress Dust from...

    Office of Scientific and Technical Information (OSTI)

    Title: Fate of Magnesium Chloride Brine Applied to Suppress Dust from Unpaved Roads at the INEEL Subsurface Disposal Area Between 1984 and 1993, MgCl2 brine was used to suppress ...

  5. EA-1793: Replacement Capability for Disposal of Remote-handled Low-level Waste Generated at the Department of Energy's Idaho Site

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of replacement capability for disposal of remote-handled low-level radioactive waste (LLW) generated at the Idaho National Laboratory (INL) site beginning in October 2017.

  6. Viscous heavy brines

    SciTech Connect (OSTI)

    House, R.F.; Hoover, L.D.

    1984-07-10

    Hydroxyethyl cellulose and a sequestrant are added to a heavy brine containing one or more salts selected from calcium chloride, calcium bromide, and zinc bromide to increase the viscosity of the brine. Preferably the brine contains zinc bromide, has a density in the range from about 14.2-19.2 pounds per gallon, and the sequestrant is a polyphosphonic acid or water soluble salt thereof.

  7. Brine flow in heated geologic salt.

    SciTech Connect (OSTI)

    Kuhlman, Kristopher L.; Malama, Bwalya

    2013-03-01

    This report is a summary of the physical processes, primary governing equations, solution approaches, and historic testing related to brine migration in geologic salt. Although most information presented in this report is not new, we synthesize a large amount of material scattered across dozens of laboratory reports, journal papers, conference proceedings, and textbooks. We present a mathematical description of the governing brine flow mechanisms in geologic salt. We outline the general coupled thermal, multi-phase hydrologic, and mechanical processes. We derive these processes' governing equations, which can be used to predict brine flow. These equations are valid under a wide variety of conditions applicable to radioactive waste disposal in rooms and boreholes excavated into geologic salt.

  8. Fate of Magnesium Chloride Brine Applied to Suppress Dust from Unpaved

    Office of Scientific and Technical Information (OSTI)

    Roads at the INEEL Subsurface Disposal Area (Journal Article) | SciTech Connect Fate of Magnesium Chloride Brine Applied to Suppress Dust from Unpaved Roads at the INEEL Subsurface Disposal Area Citation Details In-Document Search Title: Fate of Magnesium Chloride Brine Applied to Suppress Dust from Unpaved Roads at the INEEL Subsurface Disposal Area Between 1984 and 1993, MgCl2 brine was used to suppress dust on unpaved roads at a radioactive waste subsurface disposal area. Because Cl-

  9. Thickened heavy brines

    SciTech Connect (OSTI)

    House, R.F.; Hoover, L.D.

    1983-12-13

    A thickened brine solution useful as a well servicing fluid is prepared, said solution consisting essentially of water, at least 20% by weight zinc bromide, calcium bromide, and a viscosifying amount of hydroxyethyl cellulose.

  10. Public Invited to Comment on Draft Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low Level Radioactive Waste Generated at the U.S. Department of Energy’s Idaho Site

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy invites the public to read and comment on a draft environmental assessment it has prepared, for a proposal to provide a replacement capability for continued disposal of remote-handled low-level radioactive waste that is generated at the Idaho National Laboratory site.

  11. West Hackberry Strategic Petroleum Reserve site brine disposal monitoring, Year I report. Volume V. Supporting data for estuarine hydrology, discharge plume analysis, chemical oceanography, biological oceanography, and data management. Final report

    SciTech Connect (OSTI)

    DeRouen, L.R.; Hann, R.W.; Casserly, D.M.; Giammona, C.; Lascara, V.J.

    1983-02-01

    This project centers around the Strategic Petroleum Site (SPR) known as the West Hackberry salt dome which located in southwestern Louisiana, and which is designed to store 241 million barrels of crude oil. Oil storage caverns are formed by injecting water into salt deposits, and pumping out the resulting brine. Studies described in this report were designed as follow-on studies to three months of pre-discharge characterization work, and include data collected during the first year of brine leaching operations. The objectives were to: (1) characterize the environment in terms of physical, chemical and biological attributes; (2) determine if significant adverse changes in ecosystem productivity and stability of the biological community are occurring as a result of brine discharge; and (3) determine the magnitude of any change observed. Volume V contains appendices for the following: supporting data for estuarine hydrology and hydrography; supporting data analysis of discharge plume; supporting data for water and sediment chemistry; CTD/DO and pH profiles during biological monitoring; supporting data for nekton; and supporting data for data management.

  12. Brine stability study

    SciTech Connect (OSTI)

    Gary Garland

    2015-04-15

    This is a study of the brine formulations that we were using in our testing were stable over time. The data includes charts, as well as, all of the original data from the ICP-MS runs to complete this study.

  13. DOE Media Advisory- DOE extends public comment period on Draft Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the U.S. Department of Energy’s Idaho Site

    Broader source: Energy.gov [DOE]

    In response to requests from people interested in National Environmental Policy Act activities occurring at the U.S. Department of Energy’s Idaho Operations Office, the department has extended the public comment period that began September 1 on the Draft Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low-Level Radioactive Waste Generated at the U.S. Department of Energy’s Idaho Site.

  14. DOE issues Finding of No Significant Impact on Environmental Assessment for Replacement Capability for Disposal of Remote-Handled Low Level Radioactive Waste Generated at Idaho Site

    Broader source: Energy.gov [DOE]

    Idaho Falls, ID After completing a careful assessment, the U.S. Department of Energy has determined that building a new facility at its Idaho National Laboratory site for continued disposal of remote-handled low level radioactive waste generated by operations at the site will not have a significant impact on the environment.

  15. Gas evolution from geopressured brines

    SciTech Connect (OSTI)

    Matthews, C.S.

    1980-06-01

    The process of gas evolution from geopressured brine is examined using as a basis the many past studies of gas evolution from liquids in porous media. A discussion of a number of speculations that have been made concerning gas evolution from geopressured brines is provided. According to one, rapid pressure reduction will cause methane gas to evolve as when one opens a champagne bottle. It has been further speculated that evolved methane gas would migrate up to form an easily producible cap. As a result of detailed analyses, it can be concluded that methane gas evolution from geopressured brines is far too small to ever form a connected gas saturation except very near to the producing well. Thus, no significant gas cap could ever form. Because of the very low solubility of methaned in brine, the process of methane gas evolution is not at all analogous to evolution of carbon dioxide from champagne. A number of other speculations and questions on gas evolution are analyzed, and procedures for completing wells and testing geopressured brine reservoirs are discussed, with the conclusion that presently used procedures will provide adequate data to enable a good evaluation of this resource.

  16. Brine Sampling and Evaluation Program, 1991 report

    SciTech Connect (OSTI)

    Deal, D.E.; Abitz, R.J.; Myers, J.; Martin, M.L.; Milligan, D.J.; Sobocinski, R.W.; Lipponer, P.P.J.; Belski, D.S.

    1993-09-01

    The data presented in this report are the result of Brine Sampling and Evaluation Program (BSEP) activities at the Waste Isolation Pilot Plan (WIPP) during 1991. These BSEP activities document and investigate the origins, hydraulic characteristics, extent, and composition of brine occurrences in the Permian Salado Formation and seepage of that brine into the excavations at the WIPP. When excavations began at the WIPP in 1982, small brine seepages (weeps) were observed on the walls. Brine studies began as part of the Site Validation Program and were formalized as a program in its own right in 1985. During nine years of observations (1982--1991), evidence has mounted that the amount of brine seeping into the WIPP excavations is limited, local, and only a small fraction of that required to produce hydrogen gas by corroding the metal in the waste drums and waste inventory. The data through 1990 is discussed in detail and summarized by Deal and others (1991). The data presented in this report describes progress made during the calendar year 1991 and focuses on four major areas: (1) quantification of the amount of brine seeping across vertical surfaces in the WIPP excavations (brine ``weeps); (2) monitoring of brine inflow, e.g., measuring brines recovered from holes drilled downward from the underground drifts (downholes), upward from the underground drifts (upholes), and from subhorizontal holes; (3) further characterization of brine geochemistry; and (4) preliminary quantification of the amount of brine that might be released by squeezing the underconsolidated clays present in the Salado Formation.

  17. Viscous heavy brine completion fluids. [Oil wells

    SciTech Connect (OSTI)

    Darlington, R.K.; Hunter, D.V.

    1982-01-01

    An activated hydroxyethyl cellulose (HEC) has been developed which will viscosify brines of any density up to 19.2 lb/gal containing calcium chloride, calcium bromide and/or zinc bromide. The use of activated hydroxyethyl cellulose allows preparation of viscosified brines at ambient emperature and without undissolved polymer solids. The time required to prepare a viscosified brine is greatly reduced. In addition, the rheology of brines viscosified with activated HEC can be accurately predicted allowing brines with equivalent solution rheology properties to be prepared batch after batch. 29 refs.

  18. Improved Water Flooding through Injection Brine Modification

    SciTech Connect (OSTI)

    Robertson, Eric Partridge; Thomas, Charles Phillip; Morrow, Norman

    2003-01-01

    Crude oil/brine/rock interactions can lead to large variations in the displacement efficiency of waterflooding, by far the most widely applied method of improved oil recovery. Laboratory waterflood tests show that injection of dilute brine can increase oil recovery. Numerous fields in the Powder River basin have been waterflooded using low salinity brine (about 500 ppm) from the Madison limestone or Fox Hills sandstone. Although many uncertainties arise in the interpretation and comparison of field production data, injection of low salinity brine appears to give higher recovery compared to brine of moderate salinity (about 7,000 ppm). Laboratory studies of the effect of brine composition on oil recovery cover a wide range of rock types and crude oils. Oil recovery increases using low salinity brine as the injection water ranged from a low of no notable increase to as much as 37.0% depending on the system being studied. Recovery increases using low salinity brine after establishing residual oil saturation (tertiary mode) ranged from no significant increase to 6.0%. Tests with two sets of reservoir cores and crude oil indicated slight improvement in recovery for low salinity brine. Crude oil type and rock type (particularly the presence and distribution of kaolinite) both play a dominant role in the effect that brine composition has on waterflood oil recovery.

  19. Study of thermal-gradient-induced migration of brine inclusions in salt. Final report

    SciTech Connect (OSTI)

    Olander, D.R.

    1984-08-01

    Natural salt deposits, which are being considered for high-level waste disposal, contain a small volume fraction of water in the form of brine inclusions distributed throughout the salt. Radioactive decay heating of the nuclear wastes will impose a temperature gradient on the surrounding salt which mobilizes the brine inclusions. Inclusions filled completely with brine (the all-liquid inclusions) migrate up the temperature gradient and eventually accumulate brine near the buried waste forms. The brine may slowly corrode or degrade the waste forms, which is undesirable. Therefore it is important to consider the migration of brine inclusions in salt under imposed temperature gradients to properly evaluate the performance of a future salt repository for nuclear wastes. The migration velocities of the inclusions were found to be dependent on temperature, temperature gradient, and inclusion shape and size. The velocities were also dictated by the interfacial mass transfer resistance at brine/solid interface. This interfacial resistance depends on the dislocation density in the crystal, which in turn, depends on the axial compressive loading of the crystal. At low axial loads, the dependence between the velocity and temperature gradient is nonlinear. At high axial loads, the interfacial resistance is reduced and the migration velocity depends linearly on the temperature gradient. All-liquid inclusions filled with mixed brines were also studied. For gas-liquid inclusions, helium, air and argon were compared. Migration studies were also conducted on single crystallites of natural salt as well as in polycrystalline natural salt samples. The behavior of the inclusions at large-ange grain boundaries was observed.

  20. Modeling acid-gas generation from boiling chloride brines

    SciTech Connect (OSTI)

    Zhang, Guoxiang; Spycher, Nicolas; Sonnenthal, Eric; Steefel, Carl

    2009-11-16

    This study investigates the generation of HCl and other acid gases from boiling calcium chloride dominated waters at atmospheric pressure, primarily using numerical modeling. The main focus of this investigation relates to the long-term geologic disposal of nuclear waste at Yucca Mountain, Nevada, where pore waters around waste-emplacement tunnels are expected to undergo boiling and evaporative concentration as a result of the heat released by spent nuclear fuel. Processes that are modeled include boiling of highly concentrated solutions, gas transport, and gas condensation accompanied by the dissociation of acid gases, causing low-pH condensate. Simple calculations are first carried out to evaluate condensate pH as a function of HCl gas fugacity and condensed water fraction for a vapor equilibrated with saturated calcium chloride brine at 50-150 C and 1 bar. The distillation of a calcium-chloride-dominated brine is then simulated with a reactive transport model using a brine composition representative of partially evaporated calcium-rich pore waters at Yucca Mountain. Results show a significant increase in boiling temperature from evaporative concentration, as well as low pH in condensates, particularly for dynamic systems where partial condensation takes place, which result in enrichment of HCl in condensates. These results are in qualitative agreement with experimental data from other studies. The combination of reactive transport with multicomponent brine chemistry to study evaporation, boiling, and the potential for acid gas generation at the proposed Yucca Mountain repository is seen as an improvement relative to previously applied simpler batch evaporation models. This approach allows the evaluation of thermal, hydrological, and chemical (THC) processes in a coupled manner, and modeling of settings much more relevant to actual field conditions than the distillation experiment considered. The actual and modeled distillation experiments do not represent expected conditions in an emplacement drift, but nevertheless illustrate the potential for acid-gas generation at moderate temperatures (<150 C).

  1. Batteries from Brine | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    In fact, minerals like lithium, manganese, and zinc supply the raw materials for cathodes, ... demonstration facility there and mine lithium, manganese, and zinc from geothermal brines. ...

  2. Brine Migration Experimental Studies for Salt Repositories

    Broader source: Energy.gov [DOE]

    Experiments were used to examine water content in Permian salt samples including impact of variation in thermal regime on water content of evaporites and other mineral species, behavior of brine inclusions in salt, and evolution of the gas/liquid brine/salt system.

  3. Raft River Geothermal Field Well Head Brine Sample

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Tim Lanyk

    2015-12-18

    Raw data and data workup of assay for real-world brine sample. Brine sample was taken at the well head.

  4. Property:BrineConstituents | Open Energy Information

    Open Energy Info (EERE)

    Chloride type brine, "The content of potassium and calcium are high, while that of lithium, boron and sulfate is very low", See table 1 of Izquierdo et al. (2006). + Chena...

  5. How temperature and pressure affect clear brines

    SciTech Connect (OSTI)

    Hubbard, J.T.

    1984-04-01

    The correct application of the expansivity and compressibility of brine fluids under the influence of temperature and pressure is needed to calculate the actual hydrostatic pressure in a well. Well operations can benefit by reducing unintentional overbalance, lessening fluid losses, and lowering recommended fluid densities, hence reducing fluid costs. Since the early 1970s, the effects of temperature and pressure on the density of clear brine fluids have been questioned. As early as 1973, studies were started to define density loss with increased temperature in zinc bromide brines. This article describes a continuing study, begun in 1978, which has characterized the expansivity and compressibility of single salt brine solutions, such as are used in workover and completion fluids.

  6. Advanced biochemical processes for geothermal brines FY 1998 annual operating plan

    SciTech Connect (OSTI)

    1997-10-01

    As part of the overall Geothermal Energy Research which is aimed at the development of economical geothermal resources production systems, the aim of the Advanced Biochemical Processes for Geothermal Brines (ABPGB) effort is the development of economic and environmentally acceptable methods for disposal of geothermal wastes and conversion of by-products to useful forms. Methods are being developed for dissolution, separation and immobilization of geothermal wastes suitable for disposal, usable in inert construction materials, suitable for reinjection into the reservoir formation, or used for recovery of valuable metals.

  7. Disposable remote zero headspace extractor

    DOE Patents [OSTI]

    Hand, Julie J. (Idaho Falls, ID); Roberts, Mark P. (Arco, ID)

    2006-03-21

    The remote zero headspace extractor uses a sampling container inside a stainless steel vessel to perform toxicity characteristics leaching procedure to analyze volatile organic compounds. The system uses an in line filter for ease of replacement. This eliminates cleaning and disassembly of the extractor. All connections are made with quick connect fittings which can be easily replaced. After use, the bag can be removed and disposed of, and a new sampling container is inserted for the next extraction.

  8. Portable brine evaporator unit, process, and system

    DOE Patents [OSTI]

    Hart, Paul John (Indiana, PA); Miller, Bruce G. (State College, PA); Wincek, Ronald T. (State College, PA); Decker, Glenn E. (Bellefonte, PA); Johnson, David K. (Port Matilda, PA)

    2009-04-07

    The present invention discloses a comprehensive, efficient, and cost effective portable evaporator unit, method, and system for the treatment of brine. The evaporator unit, method, and system require a pretreatment process that removes heavy metals, crude oil, and other contaminates in preparation for the evaporator unit. The pretreatment and the evaporator unit, method, and system process metals and brine at the site where they are generated (the well site). Thus, saving significant money to producers who can avoid present and future increases in transportation costs.

  9. Summary Results for Brine Migration Modeling Performed by LANL...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Results for Brine Migration Modeling Performed by LANL, LBNL and SNL for the Used Fuel Disposition Program Summary Results for Brine Migration Modeling Performed by LANL, LBNL and SNL ...

  10. Expected brine movement at potential nuclear waste repository salt sites

    SciTech Connect (OSTI)

    McCauley, V.S.; Raines, G.E.

    1987-08-01

    The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m/sup 3/ brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs.

  11. Disposable rabbit

    DOE Patents [OSTI]

    Lewis, Leroy C. (Idaho Falls, ID); Trammell, David R. (Rigby, ID)

    1986-01-01

    A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

  12. Disposal rabbit

    DOE Patents [OSTI]

    Lewis, L.C.; Trammell, D.R.

    1983-10-12

    A disposable rabbit for transferring radioactive samples in a pneumatic transfer system comprises aerated plastic shaped in such a manner as to hold a radioactive sample and aerated such that dissolution of the rabbit in a solvent followed by evaporation of the solid yields solid waste material having a volume significantly smaller than the original volume of the rabbit.

  13. Targeted Pressure Management During CO2 Sequestration: Optimization of Well Placement and Brine Extraction

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Cihan, Abdullah; Birkholzer, Jens; Bianchi, Marco

    2014-12-31

    Large-scale pressure increases resulting from carbon dioxide (CO2) injection in the subsurface can potentially impact caprock integrity, induce reactivation of critically stressed faults, and drive CO2 or brine through conductive features into shallow groundwater. Pressure management involving the extraction of native fluids from storage formations can be used to minimize pressure increases while maximizing CO2 storage. However, brine extraction requires pumping, transportation, possibly treatment, and disposal of substantial volumes of extracted brackish or saline water, all of which can be technically challenging and expensive. This paper describes a constrained differential evolution (CDE) algorithm for optimal well placement and injection/ extractionmore » control with the goal of minimizing brine extraction while achieving predefined pressure contraints. The CDE methodology was tested for a simple optimization problem whose solution can be partially obtained with a gradient-based optimization methodology. The CDE successfully estimated the true global optimum for both extraction well location and extraction rate, needed for the test problem. A more complex example application of the developed strategy was also presented for a hypothetical CO2 storage scenario in a heterogeneous reservoir consisting of a critically stressed fault nearby an injection zone. Through the CDE optimization algorithm coupled to a numerical vertically-averaged reservoir model, we successfully estimated optimal rates and locations for CO2 injection and brine extraction wells while simultaneously satisfying multiple pressure buildup constraints to avoid fault activation and caprock fracturing. The study shows that the CDE methodology is a very promising tool to solve also other optimization problems related to GCS, such as reducing ‘Area of Review’, monitoring design, reducing risk of leakage and increasing storage capacity and trapping.« less

  14. Molecular Simulation of Carbon Dioxide Brine and Clay Mineral...

    Office of Scientific and Technical Information (OSTI)

    Title: Molecular Simulation of Carbon Dioxide Brine and Clay Mineral Interactions and Determination of Contact Angles. Abstract not provided. Authors: Tenney, Craig M ; Cygan, ...

  15. Reduce completion fluid costs with on-site brine tests

    SciTech Connect (OSTI)

    Thomas, D.C.; Darlington, R.K.; Kinney, W.R.; Lowell, J.L.

    1982-09-01

    A newly developed field kit makes on-site brine completion fluid testing practical. Simple titration procedures are used to analyze brine for calcium, zinc, chloride and bromide with an accuracy and repeatability that compares favorably with expensive laboratory techniques. This article describes the field testing theory and details analytical procedures used.

  16. Disposal Authorization Statement

    Broader source: Energy.gov [DOE]

    The Saltstone Disposal Facility (SDF) is authorized to operate under this Disposal Authorization Statement (DAS) (Revision 1). The revised DAS requirements ensure the facility does not pose a...

  17. Radionuclide transport in sandstones with WIPP brine

    SciTech Connect (OSTI)

    Weed, H.C.; Bazan, F.; Fontanilla, J.; Garrison, J.; Rego, J.; Winslow, A.M.

    1981-02-01

    Retardation factors (R) have been measured for the transport of /sup 3/H, /sup 95m/Tc, and /sup 85/Sr in WIPP brine using St. Peter, Berea, Kayenta, and San Felipe sandstone cores. If tritium is assumed to have R=1, /sup 95m/Tc has R=1.0 to 1.3 and therefore is essentially not retarded. Strontium-85 has R = 1.0 to 1.3 on St. Peter, Berea, and Kayenta, but R=3 on San Felipe. This is attributed to sorption on the matrix material of San Felipe, which has 45 volume % matrix compared with 1 to 10 volume % for the others. Retardation factors (R/sub s/) for /sup 85/Sr calculated from static sorption measurements are unity for all the sandstones. Therefore, the static and transport results for /sup 85/Sr disagree in the case of San Felipe, but agree for St. Peter, Berea, and Kayenta.

  18. Technique for thermodynamic crystallization temperature of brine fluids

    SciTech Connect (OSTI)

    Clark, D.E.; Hubbard, J.T.

    1983-03-01

    The application of high density solids free brine fluids has proven to be technically and economically successful in hydrocarbon completion and workover operations. The use of inorganic salts such as calcium chloride, calcium bromide, zinc bromide, and sodium bromide has contributed to the development of complex salt systems. As the density and complexity of these systems becomes more detailed, the requirement for proper fluid design becomes increasingly important. When a brine solution is cooled sufficiently, a temperature is reached where the solution will be saturated. A further decrease in temperature will result in the precipitation of salt from the solution. The temperature at which this transpires, provided no super-cooling occurs, is the crystallization point of the solution. A correctly formulated solids free brine should have the optimum crystallization point for the temperature conditions it will encounter. A recently developed semiautomatic procedure constructs a cooling curve plot of each brine tested. This cooling curve plot allows the determination of the super-cooling potential, the Thermodynamic Crystallization Temperature, and the Last Crystal To Dissolve Temperature. The device provides a permanent record of the cooling curve with repeatable accuracy, which assists in the development of error free brine formulation tables, brine density, and/or crystallization point adjustments, and brine analysis.

  19. Formate brines -- New fluids for drilling and completions

    SciTech Connect (OSTI)

    Ramsey, M.S.; Shipp, J.A.

    1996-01-01

    The term ``formate brines`` refers broadly to three primary compounds dissolved in water -- sodium formate (NaCOOH), potassium formate (KCOOH) and cesium formate (CsCOOH). Each is chemically classified as an alkali-metal salt of formic acid. They offer properties that in many respects are superior to their predecessors, halide brines such as zinc bromide and calcium bromide, without the undesirable side effects of those more common halide brine systems. This article introduces the technology and provides an overview of published work to date regarding formates.

  20. Summary Results for Brine Migration Modeling Performed by LANL LBNL and SNL for the UFD Program.

    SciTech Connect (OSTI)

    Kuhlman, Kristopher L

    2014-09-01

    This report summarizes laboratory and field observations and numerical modeling related to coupled processes involving brine and vapor migration in geologic salt, focusing on recent developments and studies conducted at Sandia, Los Alamos, and Berkeley National Laboratories. Interest into the disposal of heat-generating waste in salt has led to interest into water distribution and migration in both run-of-mine crushed and intact geologic salt. Ideally a fully coupled thermal-hydraulic-mechanical-chemical simulation is performed using numerical models with validated constitutive models and parameters. When mechanical coupling is not available, mechanical effects are prescribed in hydraulic models as source, boundary, or initial conditions. This report presents material associated with developing appropriate initial conditions for a non-mechanical hydrologic simulation of brine migration in salt. Due to the strong coupling between the mechanical and hydrologic problems, the initial saturation will be low for the excavation disturbed zone surrounding the excavation. Although most of the material in this report is not new, the author hopes it is presented in a format making it useful to other salt researchers.

  1. Molecular Simulation of Carbon Dioxide Brine and Clay Mineral Interactions

    Office of Scientific and Technical Information (OSTI)

    and Determination of Contact Angles. (Journal Article) | SciTech Connect Journal Article: Molecular Simulation of Carbon Dioxide Brine and Clay Mineral Interactions and Determination of Contact Angles. Citation Details In-Document Search Title: Molecular Simulation of Carbon Dioxide Brine and Clay Mineral Interactions and Determination of Contact Angles. Abstract not provided. Authors: Tenney, Craig M ; Cygan, Randall T. Publication Date: 2013-08-01 OSTI Identifier: 1106710 Report Number(s):

  2. Geochemical Impacts of Carbon Dioxide, Brine, Trace Metal and Organic

    Office of Scientific and Technical Information (OSTI)

    Leakage into an Unconfined, Oxidizing Limestone Aquifer (Journal Article) | SciTech Connect Journal Article: Geochemical Impacts of Carbon Dioxide, Brine, Trace Metal and Organic Leakage into an Unconfined, Oxidizing Limestone Aquifer Citation Details In-Document Search Title: Geochemical Impacts of Carbon Dioxide, Brine, Trace Metal and Organic Leakage into an Unconfined, Oxidizing Limestone Aquifer An important risk at CO2 storage sites is the potential for groundwater quality impacts. As

  3. Energy Replacement Generation Tax Exemption

    Broader source: Energy.gov [DOE]

    Under the Energy Replacement Generation Tax Exemption, the following facilities are exempt from the replacement tax:

  4. Filter Replacement Activities Complete

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    4, 2014 Filter Replacement Activities Complete This week, filter replacements were safely and successfully completed. The high efficiency filters on the second filter unit were replaced on June 20, and employees replaced the moderate filters on June 23. Decontamination and cleanup of the work areas in the filter building will complete all activities currently scheduled for WIPP's ventilation system. Employees are also restoring higher airflow levels now that both filter units are operational.

  5. Appendix K Disposal Cell Groundwater Monitoring Plan

    Office of Legacy Management (LM)

    Disposal Cell Groundwater Monitoring Plan

  6. Targeted Pressure Management During CO2 Sequestration: Optimization of Well Placement and Brine Extraction

    SciTech Connect (OSTI)

    Cihan, Abdullah; Birkholzer, Jens; Bianchi, Marco

    2014-12-31

    Large-scale pressure increases resulting from carbon dioxide (CO2) injection in the subsurface can potentially impact caprock integrity, induce reactivation of critically stressed faults, and drive CO2 or brine through conductive features into shallow groundwater. Pressure management involving the extraction of native fluids from storage formations can be used to minimize pressure increases while maximizing CO2 storage. However, brine extraction requires pumping, transportation, possibly treatment, and disposal of substantial volumes of extracted brackish or saline water, all of which can be technically challenging and expensive. This paper describes a constrained differential evolution (CDE) algorithm for optimal well placement and injection/ extraction control with the goal of minimizing brine extraction while achieving predefined pressure contraints. The CDE methodology was tested for a simple optimization problem whose solution can be partially obtained with a gradient-based optimization methodology. The CDE successfully estimated the true global optimum for both extraction well location and extraction rate, needed for the test problem. A more complex example application of the developed strategy was also presented for a hypothetical CO2 storage scenario in a heterogeneous reservoir consisting of a critically stressed fault nearby an injection zone. Through the CDE optimization algorithm coupled to a numerical vertically-averaged reservoir model, we successfully estimated optimal rates and locations for CO2 injection and brine extraction wells while simultaneously satisfying multiple pressure buildup constraints to avoid fault activation and caprock fracturing. The study shows that the CDE methodology is a very promising tool to solve also other optimization problems related to GCS, such as reducing Area of Review, monitoring design, reducing risk of leakage and increasing storage capacity and trapping.

  7. Disposal Information - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    About Us Hanford Site Wide Programs Hanford Site Solid Waste Acceptance Program Tools Disposal Information About Us Hanford Site Solid Waste Acceptance Program What's New Acceptance Criteria Acceptance Process Tools Approved High Integrity Containers Approved Sorbents, Stabilizers, and Void Fillers Disposal Information Points of Contact Disposal Information Email Email Page | Print Print Page |Text Increase Font Size Decrease Font Size Disposal of Radioactive Waste at Hanford The Hanford Site

  8. Material Disposal Areas

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Material Disposal Areas Material Disposal Areas Material Disposal Areas, also known as MDAs, are sites where material was disposed of below the ground surface in excavated pits, trenches, or shafts. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Material Disposal Areas at LANL The following are descriptions and status updates of each MDA at LANL. To view a current fact sheet on the MDAs, click on LA-UR-13-25837 (pdf).

  9. Actinide (III) solubility in WIPP Brine: data summary and recommendations

    SciTech Connect (OSTI)

    Borkowski, Marian; Lucchini, Jean-Francois; Richmann, Michael K.; Reed, Donald T.

    2009-09-01

    The solubility of actinides in the +3 oxidation state is an important input into the Waste Isolation Pilot Plant (WIPP) performance assessment (PA) models that calculate potential actinide release from the WIPP repository. In this context, the solubility of neodymium(III) was determined as a function of pH, carbonate concentration, and WIPP brine composition. Additionally, we conducted a literature review on the solubility of +3 actinides under WIPP-related conditions. Neodymium(III) was used as a redox-invariant analog for the +3 oxidation state of americium and plutonium, which is the oxidation state that accounts for over 90% of the potential release from the WIPP through the dissolved brine release (DBR) mechanism, based on current WIPP performance assessment assumptions. These solubility data extend past studies to brine compositions that are more WIPP-relevant and cover a broader range of experimental conditions than past studies.

  10. Nevada: Geothermal Brine Brings Low-Cost Power with Big Potential...

    Office of Environmental Management (EM)

    Nevada: Geothermal Brine Brings Low-Cost Power with Big Potential Nevada: Geothermal Brine Brings Low-Cost Power with Big Potential August 21, 2013 - 12:00am Addthis Utilizing a 1...

  11. Brine pH Modification Scale Control Technology. 2. A Review.pdf...

    Open Energy Info (EERE)

    Brine pH Modification Scale Control Technology. 2. A Review.pdf Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article: Brine pH Modification Scale...

  12. Radiation Source Replacement Workshop

    SciTech Connect (OSTI)

    Griffin, Jeffrey W.; Moran, Traci L.; Bond, Leonard J.

    2010-12-01

    This report summarizes a Radiation Source Replacement Workshop in Houston Texas on October 27-28, 2010, which provided a forum for industry and researchers to exchange information and to discuss the issues relating to replacement of AmBe, and potentially other isotope sources used in well logging.

  13. Uranium (VI) solubility in carbonate-free ERDA-6 brine

    SciTech Connect (OSTI)

    Lucchini, Jean-francois; Khaing, Hnin; Reed, Donald T

    2010-01-01

    When present, uranium is usually an element of importance in a nuclear waste repository. In the Waste Isolation Pilot Plant (WIPP), uranium is the most prevalent actinide component by mass, with about 647 metric tons to be placed in the repository. Therefore, the chemistry of uranium, and especially its solubility in the WIPP conditions, needs to be well determined. Long-term experiments were performed to measure the solubility of uranium (VI) in carbonate-free ERDA-6 brine, a simulated WIPP brine, at pC{sub H+} values between 8 and 12.5. These data, obtained from the over-saturation approach, were the first repository-relevant data for the VI actinide oxidation state. The solubility trends observed pointed towards low uranium solubility in WIPP brines and a lack of amphotericity. At the expected pC{sub H+} in the WIPP ({approx} 9.5), measured uranium solubility approached 10{sup -7} M. The objective of these experiments was to establish a baseline solubility to further investigate the effects of carbonate complexation on uranium solubility in WIPP brines.

  14. CX-010404: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Replace Brine Disposal System Header to West Hackberry Brine Tanks, Government Furnished Equipment CX(s) Applied: B1.3 Date: 04/22/2013 Location(s): Louisiana Offices(s): Strategic Petroleum Reserve Field Office

  15. CX-010401: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Replace Brine Disposal System Header to West Hackberry Brine Tanks CX(s) Applied: B1.3 Date: 04/22/2013 Location(s): Louisiana Offices(s): Strategic Petroleum Reserve Field Office

  16. CX-009718: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Replace Brine Disposal System Header to Bryan Mound Brine Tank, GFE CX(s) Applied: B1.3 Date: 12/11/2012 Location(s): Texas Offices(s): Strategic Petroleum Reserve Field Office

  17. Replacing 16 mm film cameras with high definition digital cameras

    SciTech Connect (OSTI)

    Balch, K.S.

    1995-12-31

    For many years 16 mm film cameras have been used in severe environments. These film cameras are used on Hy-G automotive sleds, airborne gun cameras, range tracking and other hazardous environments. The companies and government agencies using these cameras are in need of replacing them with a more cost effective solution. Film-based cameras still produce the best resolving capability, however, film development time, chemical disposal, recurring media cost, and faster digital analysis are factors influencing the desire for a 16 mm film camera replacement. This paper will describe a new camera from Kodak that has been designed to replace 16 mm high speed film cameras.

  18. disposal_cell.cdr

    Office of Legacy Management (LM)

    With the April 24, 1997, ceremonial ground-breaking for disposal facility construction, the Weldon Spring Site Remedial Action Project (WSSRAP) moved into the final stage of cleanup, treatment, and disposal of uranium- processing wastes. The cleanup of the former uranium- refining plant consisted of three primary operations: Demolition and removal of remaining concrete pads and foundations that supported the 44 structures and buildings on site Treatment of selected wastes Permanent encapsulation

  19. Pre-injection brine production for managing pressure in compartmentalized CO₂ storage reservoirs

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Buscheck, Thomas A.; White, Joshua A.; Chen, Mingjie; Sun, Yunwei; Hao, Yue; Aines, Roger D.; Bourcier, William L.; Bielicki, Jeffrey M.

    2014-12-31

    We present a reservoir management approach for geologic CO₂ storage that combines CO₂ injection with brine extraction. In our approach,dual-mode wells are initially used to extract formation brine and subsequently used to inject CO₂. These wells can also be used to monitor the subsurface during pre-injection brine extraction so that key data is acquired and analyzed prior to CO₂ injection. The relationship between pressure drawdown during pre-injection brine extraction and pressure buildup during CO₂ injection directly informs reservoir managers about CO₂ storage capacity. These data facilitate proactive reservoir management, and thus reduce costs and risks. The brine may be usedmore » directly as make-up brine for nearby reservoir operations; it can also be desalinated and/or treated for a variety of beneficial uses.« less

  20. Pre-injection brine production for managing pressure in compartmentalized CO? storage reservoirs

    SciTech Connect (OSTI)

    Buscheck, Thomas A.; White, Joshua A.; Chen, Mingjie; Sun, Yunwei; Hao, Yue; Aines, Roger D.; Bourcier, William L.; Bielicki, Jeffrey M.

    2014-12-31

    We present a reservoir management approach for geologic CO? storage that combines CO? injection with brine extraction. In our approach,dual-mode wells are initially used to extract formation brine and subsequently used to inject CO?. These wells can also be used to monitor the subsurface during pre-injection brine extraction so that key data is acquired and analyzed prior to CO? injection. The relationship between pressure drawdown during pre-injection brine extraction and pressure buildup during CO? injection directly informs reservoir managers about CO? storage capacity. These data facilitate proactive reservoir management, and thus reduce costs and risks. The brine may be used directly as make-up brine for nearby reservoir operations; it can also be desalinated and/or treated for a variety of beneficial uses.

  1. Summary Results for Brine Migration Modeling Performed by LANL, LBNL and

    Energy Savers [EERE]

    SNL for the Used Fuel Disposition Program | Department of Energy Results for Brine Migration Modeling Performed by LANL, LBNL and SNL for the Used Fuel Disposition Program Summary Results for Brine Migration Modeling Performed by LANL, LBNL and SNL for the Used Fuel Disposition Program The report summarizes laboratory and field observations and numerical modeling related to coupled processes involving brine and vapor migration in geologic salt, focusing on recent developments and studies

  2. Waste Disposal | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Disposal Waste Disposal Trucks transport debris from Oak Ridge’s cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. Trucks transport debris from Oak Ridge's cleanup sites to the onsite CERCLA disposal area, the Environmental Management Waste Management Facility. The low-level radiological and hazardous wastes generated from Oak Ridge's cleanup projects are disposed in the Environmental Management Waste Management Facility (EMWMF). The

  3. replace fossil fuels

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    replace fossil fuels - Sandia Energy Energy Search Icon Sandia Home Locations Contact Us Employee Locator Energy & Climate Secure & Sustainable Energy Future Stationary Power Energy Conversion Efficiency Solar Energy Wind Energy Water Power Supercritical CO2 Geothermal Natural Gas Safety, Security & Resilience of the Energy Infrastructure Energy Storage Nuclear Power & Engineering Grid Modernization Battery Testing Nuclear Fuel Cycle Defense Waste Management Programs Advanced

  4. HIGH-PRESSURE SOLVENT EXTRACTION OF METHANE FROM GEOPRESSURED BRINES:

    Office of Scientific and Technical Information (OSTI)

    PRESSURE SOLVENT EXTRACTION OF METHANE FROM GEOPRESSURED BRINES: TECHNICAL EVALUATION AND COST ANALYSIS R. Quong H. H. Otsuki F. E. Locke July 1981 This is an informal report intended primarily for internal or limited extcrual dirtribdk.. 1Lc opinions and condusions stated are tbose of the antbor and m y or may m o t be tbosc of tbe Laboratory. Work performed under the ampices of the U S . Department of Elnrgy by tbe Lawrence Livermore Laboratory under Cwbsct W-7405-Er498. 7 DISTRIBUTIUN OF THIS

  5. Community Geothermal Technology Program: Electrodeposition of minerals in geothermal brine

    SciTech Connect (OSTI)

    Not Available

    1990-12-31

    Objective was to study the materials electrodeposited from geothermal brine, from the HGP-A well in Puna, Hawaii. Due to limitations, only one good set of electrodeposited material was obtained; crystallography indicates that vaterite forms first, followed by calcite and then perhaps aragonite as current density is increased. While the cost to weight ratio is reasonable, the deposition rate is very slow. More research is needed, such as reducing the brittleness. The electrodeposited material possibly could be used as building blocks, tables, benches, etc. 49 figs, 4 tabs, 7 refs.

  6. Waste disposal package

    DOE Patents [OSTI]

    Smith, M.J.

    1985-06-19

    This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

  7. Radioactive waste disposal package

    DOE Patents [OSTI]

    Lampe, Robert F. (Bethel Park, PA)

    1986-01-01

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  8. COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS

    SciTech Connect (OSTI)

    THIELGES, J.R.; CHASTAIN, S.A.

    2007-06-21

    The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

  9. Oil field waste disposal costs at commercial disposal facilities

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-10-01

    The exploration and production segment of the U.S. oil and gas industry generates millions of barrels of nonhazardous oil field wastes annually. In most cases, operators can dispose of their oil fields wastes at a lower cost on-site than off site and, thus, will choose on-site disposal. However, a significant quantity of oil field wastes are still sent to off-site commercial facilities for disposal. This paper provides information on the availability of commercial disposal companies in different states, the treatment and disposal methods they employ, and how much they charge. There appear to be two major off-site disposal trends. Numerous commercial disposal companies that handle oil field wastes exclusively are located in nine oil-and gas-producing states. They use the same disposal methods as those used for on-site disposal. In addition, the Railroad Commission of Texas has issued permits to allow several salt caverns to be used for disposal of oil field wastes. Twenty-two other oil- and gas-producing states contain few or no disposal companies dedicated to oil and gas industry waste. The only off-site commercial disposal companies available handle general industrial wastes or are sanitary landfills. In those states, operators needing to dispose of oil field wastes off-site must send them to a local landfill or out of state. The cost of off-site commercial disposal varies substantially, depending on the disposal method used, the state in which the disposal company is located, and the degree of competition in the area.

  10. Power Plant Replacement Study

    SciTech Connect (OSTI)

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self-funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois Universitys aging and failing circa 1925 central steam production plant. Twenty-three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  11. Power Plant Replacement Study

    SciTech Connect (OSTI)

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self-funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois University's aging and failing circa 1925 central steam production plant. Twenty-three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  12. Power Plant Replacement Study

    SciTech Connect (OSTI)

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self-funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois University’s aging and failing circa 1925 central steam production plant. Twenty-three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  13. Power Plant Replacement Study

    SciTech Connect (OSTI)

    Reed, Gary

    2010-09-30

    This report represents the final report for the Eastern Illinois University power plant replacement study. It contains all related documentation from consideration of possible solutions to the final recommended option. Included are the economic justifications associated with the chosen solution along with application for environmental permitting for the selected project for construction. This final report will summarize the results of execution of an EPC (energy performance contract) investment grade audit (IGA) which lead to an energy services agreement (ESA). The project includes scope of work to design and install energy conservation measures which are guaranteed by the contractor to be self?funding over its twenty year contract duration. The cost recovery is derived from systems performance improvements leading to energy savings. The prime focus of this EPC effort is to provide a replacement solution for Eastern Illinois Universitys aging and failing circa 1925 central steam production plant. Twenty?three ECMs were considered viable whose net impact will provide sufficient savings to successfully support the overall project objectives.

  14. Chemical-equilibrium calculations for aqueous geothermal brines

    SciTech Connect (OSTI)

    Kerrisk, J.F.

    1981-05-01

    Results from four chemical-equilibrium computer programs, REDEQL.EPAK, GEOCHEM, WATEQF, and SENECA2, have been compared with experimental solubility data for some simple systems of interest with geothermal brines. Seven test cases involving solubilities of CaCO/sub 3/, amorphous SiO/sub 2/, CaSO/sub 4/, and BaSO/sub 4/ at various temperatures from 25 to 300/sup 0/C and in NaCl or HCl solutions of 0 to 4 molal have been examined. Significant differences between calculated results and experimental data occurred in some cases. These differences were traced to inaccuracies in free-energy or equilibrium-constant data and in activity coefficients used by the programs. Although currently available chemical-equilibrium programs can give reasonable results for these calculations, considerable care must be taken in the selection of free-energy data and methods of calculating activity coefficients.

  15. Recommendation 223: Recommendations on Additional Waste Disposal...

    Office of Environmental Management (EM)

    3: Recommendations on Additional Waste Disposal Capacity Recommendation 223: Recommendations on Additional Waste Disposal Capacity ORSSAB's recommendations encourage DOE to...

  16. Transportation, Aging and Disposal Canister System Performance...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 ...

  17. Pioneering Nuclear Waste Disposal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    PIONEERING NUCLEAR WASTE DISPOSAL U.S. Department of Energy Carlsbad Area Office February 2000 DOE/CAO-00-3124 T h e W a s t e I s o l a t i o n P i l o t P l a n t ii Table of Contents Closing the Circle on Transuranic Waste 1 The Long Road to the WIPP 3 The need for the WIPP The National Academy of Sciences Community leaders suggest Carlsbad as the site for the WIPP Construction of the WIPP The WIPP Land Withdrawal Act Certification by the EPA The National Environmental Policy Act The Resource

  18. Radioactive waste material disposal

    DOE Patents [OSTI]

    Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

    1995-10-24

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

  19. Radioactive waste material disposal

    DOE Patents [OSTI]

    Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

    1995-01-01

    The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

  20. WIPP Workers Perform Filter Replacement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    December 10, 2015 WIPP Workers Perform Filter Replacement As recovery operations at the Waste Isolation Pilot Plant continue, increased work activity in the underground results in higher levels of airborne salt dust, increasing the frequency with which filters are replaced. Last week, workers performed a filter replacement on WIPP's Underground Ventilation System. WIPP's ventilation system has two filter units. Each unit has 84 separate filters arranges in four layers- moderate efficiency

  1. Environmental waste disposal contracts awarded

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Environmental contracts awarded locally Environmental waste disposal contracts awarded locally Three small businesses with offices in Northern New Mexico awarded nuclear waste...

  2. Replacement Cost of Domestic Crude

    Energy Science and Technology Software Center (OSTI)

    1994-12-01

    The DEEPWATER model forecasts the replacement cost of domestic crude oil for 13 offshore regions in the lower 48 states. The replacement cost of domestic crude oil is the constant or levelized selling price that will recover the full expense of exploration, development, and productions with a reasonable return on capital.

  3. Window Replacement, Rehabilitation, & Repair Guides - Building...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Window Replacement, Rehabilitation, & Repair Guides - Building America Top Innovation Window Replacement, Rehabilitation, & Repair Guides - Building America Top Innovation Effec...

  4. Recovery of Fresh Water Resources from Desalination of Brine Produced During Oil and Gas Production Operations

    SciTech Connect (OSTI)

    David B. Burnett; Mustafa Siddiqui

    2006-12-29

    Management and disposal of produced water is one of the most important problems associated with oil and gas (O&G) production. O&G production operations generate large volumes of brine water along with the petroleum resource. Currently, produced water is treated as a waste and is not available for any beneficial purposes for the communities where oil and gas is produced. Produced water contains different contaminants that must be removed before it can be used for any beneficial surface applications. Arid areas like west Texas produce large amount of oil, but, at the same time, have a shortage of potable water. A multidisciplinary team headed by researchers from Texas A&M University has spent more than six years is developing advanced membrane filtration processes for treating oil field produced brines The government-industry cooperative joint venture has been managed by the Global Petroleum Research Institute (GPRI). The goal of the project has been to demonstrate that treatment of oil field waste water for re-use will reduce water handling costs by 50% or greater. Our work has included (1) integrating advanced materials into existing prototype units and (2) operating short and long-term field testing with full size process trains. Testing at A&M has allowed us to upgrade our existing units with improved pre-treatment oil removal techniques and new oil tolerant RO membranes. We have also been able to perform extended testing in 'field laboratories' to gather much needed extended run time data on filter salt rejection efficiency and plugging characteristics of the process train. The Program Report describes work to evaluate the technical and economical feasibility of treating produced water with a combination of different separation processes to obtain water of agricultural water quality standards. Experiments were done for the pretreatment of produced water using a new liquid-liquid centrifuge, organoclay and microfiltration and ultrafiltration membranes for the removal of hydrocarbons from produced water. The results of these experiments show that hydrocarbons from produced water can be reduced from 200 ppm to below 29 ppm level. Experiments were also done to remove the dissolved solids (salts) from the pretreated produced water using desalination membranes. Produced water with up to 45,000 ppm total dissolved solids (TDS) can be treated to agricultural water quality water standards having less than 500 ppm TDS. The Report also discusses the results of field testing of various process trains to measure performance of the desalination process. Economic analysis based on field testing, including capital and operational costs, was done to predict the water treatment costs. Cost of treating produced water containing 15,000 ppm total dissolved solids and 200 ppm hydrocarbons to obtain agricultural water quality with less than 200 ppm TDS and 2 ppm hydrocarbons range between $0.5-1.5 /bbl. The contribution of fresh water resource from produced water will contribute enormously to the sustainable development of the communities where oil and gas is produced and fresh water is a scarce resource. This water can be used for many beneficial purposes such as agriculture, horticulture, rangeland and ecological restorations, and other environmental and industrial application.

  5. Recovery of energy from geothermal brine and other hot water sources

    DOE Patents [OSTI]

    Wahl, III, Edward F.; Boucher, Frederic B.

    1981-01-01

    Process and system for recovery of energy from geothermal brines and other hot water sources, by direct contact heat exchange between the brine or hot water, and an immiscible working fluid, e.g. a hydrocarbon such as isobutane, in a heat exchange column, the brine or hot water therein flowing countercurrent to the flow of the working fluid. The column can be operated at subcritical, critical or above the critical pressure of the working fluid. Preferably, the column is provided with a plurality of sieve plates, and the heat exchange process and column, e.g. with respect to the design of such plates, number of plates employed, spacing between plates, area thereof, column diameter, and the like, are designed to achieve maximum throughput of brine or hot water and reduction in temperature differential at the respective stages or plates between the brine or hot water and the working fluid, and so minimize lost work and maximize efficiency, and minimize scale deposition from hot water containing fluid including salts, such as brine. Maximum throughput approximates minimum cost of electricity which can be produced by conversion of the recovered thermal energy to electrical energy.

  6. Preliminary performance assessment for the Waste Isolation Pilot Plant, December 1992. Volume 5, Uncertainty and sensitivity analyses of gas and brine migration for undisturbed performance

    SciTech Connect (OSTI)

    Not Available

    1993-08-01

    Before disposing of transuranic radioactive waste in the Waste Isolation Pilot Plant (WIPP), the United States Department of Energy (DOE) must evaluate compliance with applicable long-term regulations of the United States Environmental Protection Agency (EPA). Sandia National Laboratories is conducting iterative performance assessments (PAs) of the WIPP for the DOE to provide interim guidance while preparing for a final compliance evaluation. This volume of the 1992 PA contains results of uncertainty and sensitivity analyses with respect to migration of gas and brine from the undisturbed repository. Additional information about the 1992 PA is provided in other volumes. Volume 1 contains an overview of WIPP PA and results of a preliminary comparison with 40 CFR 191, Subpart B. Volume 2 describes the technical basis for the performance assessment, including descriptions of the linked computational models used in the Monte Carlo analyses. Volume 3 contains the reference data base and values for input parameters used in consequence and probability modeling. Volume 4 contains uncertainty and sensitivity analyses with respect to the EPA`s Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes (40 CFR 191, Subpart B). Finally, guidance derived from the entire 1992 PA is presented in Volume 6. Results of the 1992 uncertainty and sensitivity analyses indicate that, conditional on the modeling assumptions and the assigned parameter-value distributions, the most important parameters for which uncertainty has the potential to affect gas and brine migration from the undisturbed repository are: initial liquid saturation in the waste, anhydrite permeability, biodegradation-reaction stoichiometry, gas-generation rates for both corrosion and biodegradation under inundated conditions, and the permeability of the long-term shaft seal.

  7. Integrated Disposal Facility Risk Assessment

    SciTech Connect (OSTI)

    MANN, F. M.

    2003-06-03

    An environmental risk assessment associated with the disposal of projected Immobilized Low-Activity Waste, solid wastes and failed or decommissioned melters in an Integrated Disposal Facility was performed. Based on the analyses all performance objectives associated with the groundwater, air, and intruder pathways were met.

  8. Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

    SciTech Connect (OSTI)

    Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

    2013-07-29

    Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

  9. Behavior of natural uranium, thorium, and radium isotopes in the Wolfcamp brine aquifers, Palo Duro Basin, Texas

    SciTech Connect (OSTI)

    Laul, J.C.; Smith, M.R.; Hubbard, N.

    1984-10-01

    Previously reported results for Palo Duro deep brines show that Ra is highly soluble and not retarded. Relative to Ra, U and Th are highly sorbed. Uranium, like thorium, is in the +4 valence state, indicating a reducing environment. Additional data reported here support these results. However, one Wolfcamp brine sample gives somewhat different results. Radium appears to be somewhat sorbed. Uranium is largely in the +6 valence state, indicating a less reducing condition. In all brines, kinetics for sorption (/sup 228/Th) and desorption (/sup 224/Ra) are rapid. This Wolfcamp brine was tested for the effects of colloids for Ra, U, and Th concentrations. No effects were found.

  10. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    David Duncan

    2011-05-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  11. Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2011-03-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  12. Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

    2010-10-01

    This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

  13. Performance Assessment and Composit Analysis Material Disposal...

    Office of Environmental Management (EM)

    Performance Assessment and Composit Analysis Material Disposal Area G Revision 4 Performance Assessment and Composit Analysis Material Disposal Area G Revision 4 Los Alamos...

  14. WIPP - Pioneering Nuclear Waste Disposal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Pioneering Nuclear Waste Disposal Cover Page and Table of Contents Closing the Circle The Long Road to WIPP - Part 1 The Long Road to WIPP - Part 2 Looking to the Future Related Reading and The WIPP Team

  15. Optimization of Waste Disposal - 13338

    SciTech Connect (OSTI)

    Shephard, E.; Walter, N.; Downey, H.; Collopy, P.; Conant, J.

    2013-07-01

    From 2009 through 2011, remediation of areas of a former fuel cycle facility used for government contract work was conducted. Remediation efforts were focused on building demolition, underground pipeline removal, contaminated soil removal and removal of contaminated sediments from portions of an on-site stream. Prior to conducting the remediation field effort, planning and preparation for remediation (including strategic planning for waste characterization and disposal) was conducted during the design phase. During the remediation field effort, waste characterization and disposal practices were continuously reviewed and refined to optimize waste disposal practices. This paper discusses strategic planning for waste characterization and disposal that was employed in the design phase, and continuously reviewed and refined to optimize efficiency. (authors)

  16. Disposal phase experimental program plan

    SciTech Connect (OSTI)

    1997-01-31

    The Waste Isolation Pilot Plant (WIPP) facility comprises surface and subsurface facilities, including a repository mined in a bedded salt formation at a depth of 2,150 feet. It has been developed to safely and permanently isolate transuranic (TRU) radioactive wastes in a deep geological disposal site. On April 12, 1996, the DOE submitted a revised Resource Conservation and Recovery Act (RCRA) Part B permit application to the New Mexico Environment Department (NMED). The DOE anticipates receiving an operating permit from the NMED; this permit is required prior to the start of disposal operations. On October 29, 1996, the DOE submitted a Compliance Certification Application (CCA) to the US Environmental Protection Agency (EPA) in accordance with the WIPP land Withdrawal Act (LWA) of 1992 (Public Law 102-579) as amended, and the requirements of Title 40 of the Code of Federal Regulations (40 CFR) Parts 191 and 194. The DOE plans to begin disposal operations at the WIPP in November 1997 following receipt of certification by the EPA. The disposal phase is expected to last for 35 years, and will include recertification activities no less than once every five years. This Disposal Phase Experimental Program (DPEP) Plan outlines the experimental program to be conducted during the first 5-year recertification period. It also forms the basis for longer-term activities to be carried out throughout the 35-year disposal phase. Once the WIPP has been shown to be in compliance with regulatory requirements, the disposal phase gives an opportunity to affirm the compliance status of the WIPP, enhance the operations of the WIPP and the national TRU system, and contribute to the resolution of national and international nuclear waste management technical needs. The WIPP is the first facility of its kind in the world. As such, it provides a unique opportunity to advance the technical state of the art for permanent disposal of long-lived radioactive wastes.

  17. Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Danny Anderson

    2014-07-01

    As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE and commercial disposal options exist for contact-handled LLW; however, offsite disposal options are either not currently available (i.e., commercial disposal facilities), practical, or cost-effective for all remote-handled LLW streams generated at INL. Offsite disposal of all INL and tenant-generated remote-handled waste is further complicated by issues associated with transporting highly radioactive waste in commerce; and infrastructure and processing changes at the generating facilities, specifically NRF, that would be required to support offsite disposal. The INL Remote-Handled LLW Disposal Project will develop a new remote handled LLW disposal facility to meet mission-critical, remote-handled LLW disposal needs. A formal DOE decision to proceed with the project has been made in accordance with the requirements of National Environmental Policy Act (42 USC§ 4321 et seq.). Remote-handled LLW is generated from nuclear programs conducted at INL, including spent nuclear fuel handling and operations at NRF and operations at the Advanced Test Reactor. Remote-handled LLW also will be generated by new INL programs and from segregation and treatment (as necessary) of remote handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex.

  18. Silica separation from reinjection brines at Monte Amiata geothermal plants, Italy

    SciTech Connect (OSTI)

    Vitolo, S.; Cialdella, M.L. . Dipartimento di Ingegneria Chimica)

    1994-06-01

    A process for the separation of silica from geothermal reinjection brines is reported, in which the phases of coagulation, sedimentation and filtration of silica are involved. The effectiveness of lime and calcium chloride as coagulating agents has been investigated and the separating operations have been set out. Attention has been focused on Monte Amiata reinjection geothermal brines, whose scaling effect causes serious problems in the operation and maintenance of reinjection facilities. The study has been conducted using different amounts of added coagulants and at different temperatures, to determine optimal operating conditions. Though calcium chloride was revealed to be effective as a coagulant of the polymeric silica fraction, lime has also proved capable of removing monomeric dissolved silica at high dosages. Investigation on the behavior of coagulated brine has revealed the feasibility of separating the coagulated silica by sedimentation and filtration.

  19. Do You Have Windows That Need Replacing?

    Broader source: Energy.gov [DOE]

    Do you have windows that need replacing, too? Do you have any plans to replace them with newer, more efficient windows?

  20. Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures

    SciTech Connect (OSTI)

    Rutqvist, Jonny; Blanco-Martin, Laura; Molins, Sergi; Trebotich, David; Birkholzer, Jens

    2015-09-01

    In this report, we present FY2015 progress by Lawrence Berkeley National Laboratory (LBNL) related to modeling of coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. This is a combined milestone report related to milestone Salt R&D Milestone Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures (M3FT-15LB0818012) and the Salt Field Testing Milestone (M3FT-15LB0819022) to support the overall objectives of the salt field test planning.

  1. ASSESSMENT OF TECHNETIUM LEACHABILITY IN CEMENT STABILIZED BASIN 43 GROUNDWATER BRINE

    SciTech Connect (OSTI)

    COOKE GA; DUNCAN JB; LOCKREM LL

    2008-09-30

    This report is an initial report on the laboratory effort executed under RPP-PLAN-33338, Test Plan for the Assessment of Technetium Leachability in Cement-Stabilized Basin 43 Groundwater Brine. This report delineates preliminary data obtained under subcontract 21065, release 30, from the RJ Lee Group, Inc., Center for Laboratory Sciences. The report is predicated on CLS RPT-816, Draft Report: Assessment of Technetium Leachability in Cement Stabilized Basin 43 Groundwater Brine. This document will be revised on receipt of the final RJ Lee Group, Inc., Center for Laboratory Sciences report, which will contain data subjected to quality control and quality assurance criteria.

  2. Nevada: Geothermal Brine Brings Low-Cost Power with Big Potential |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Nevada: Geothermal Brine Brings Low-Cost Power with Big Potential Nevada: Geothermal Brine Brings Low-Cost Power with Big Potential August 21, 2013 - 12:00am Addthis Utilizing a $1 million EERE investment, heat from geothermal fluids-a byproduct of gold mining-will be generating electricity this year for less than $0.06 per kilowatt hour with ElectraTherm's new plug-and-play technology. Building on this first-of-its-kind success, this emission-free electricity is the

  3. Transportation, Aging and Disposal Canister System Performance

    Energy Savers [EERE]

    Specification: Revision 1 | Department of Energy Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. PDF icon Transportation, Aging and Disposal Canister System Performance Specification: Revision 1 More Documents &

  4. PROPERTY DISPOSAL RECORDS | Department of Energy

    Energy Savers [EERE]

    PROPERTY DISPOSAL RECORDS PROPERTY DISPOSAL RECORDS These records pertain to the sales by agencies of real and personal property surplus to the needs of the Government PDF icon PROPERTY DISPOSAL RECORDS More Documents & Publications ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) ADMINISTRATIVE RECORDS: PROCUREMENT, SUPPLY, AND GRANT RECORDS ADMINISTRATIVE RECORDS SCHEDULE 12: COMMUNICATIONS RECORDS

  5. International Collaboration Activities in Different Geologic Disposal

    Energy Savers [EERE]

    Environments | Department of Energy Collaboration Activities in Different Geologic Disposal Environments International Collaboration Activities in Different Geologic Disposal Environments This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. To date, UFD's International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several

  6. Tank Waste Disposal Program redefinition

    SciTech Connect (OSTI)

    Grygiel, M.L.; Augustine, C.A.; Cahill, M.A.; Garfield, J.S.; Johnson, M.E.; Kupfer, M.J.; Meyer, G.A.; Roecker, J.H.; Holton, L.K.; Hunter, V.L.; Triplett, M.B.

    1991-10-01

    The record of decision (ROD) (DOE 1988) on the Final Environmental Impact Statement, Hanford Defense High-Level, Transuranic and Tank Wastes, Hanford Site, Richland Washington identifies the method for disposal of double-shell tank waste and cesium and strontium capsules at the Hanford Site. The ROD also identifies the need for additional evaluations before a final decision is made on the disposal of single-shell tank waste. This document presents the results of systematic evaluation of the present technical circumstances, alternatives, and regulatory requirements in light of the values of the leaders and constitutents of the program. It recommends a three-phased approach for disposing of tank wastes. This approach allows mature technologies to be applied to the treatment of well-understood waste forms in the near term, while providing time for the development and deployment of successively more advanced pretreatment technologies. The advanced technologies will accelerate disposal by reducing the volume of waste to be vitrified. This document also recommends integration of the double-and single-shell tank waste disposal programs, provides a target schedule for implementation of the selected approach, and describes the essential elements of a program to be baselined in 1992.

  7. Portsmouth Waste Disposal | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Environmental Cleanup » Portsmouth Waste Disposal Portsmouth Waste Disposal Preliminary design cross section of Planned On-site Disposal Cell Preliminary design cross section of Planned On-site Disposal Cell The Portsmouth Site Waste Management Program directs the safe storage, treatment, and disposal of waste generated from the decontamination and decommissioning (D&D) of facilities that are no longer in use, past plant operations, ongoing plant maintenance, and ongoing environmental

  8. Depleted uranium disposal options evaluation

    SciTech Connect (OSTI)

    Hertzler, T.J.; Nishimoto, D.D.; Otis, M.D.

    1994-05-01

    The Department of Energy (DOE), Office of Environmental Restoration and Waste Management, has chartered a study to evaluate alternative management strategies for depleted uranium (DU) currently stored throughout the DOE complex. Historically, DU has been maintained as a strategic resource because of uses for DU metal and potential uses for further enrichment or for uranium oxide as breeder reactor blanket fuel. This study has focused on evaluating the disposal options for DU if it were considered a waste. This report is in no way declaring these DU reserves a ``waste,`` but is intended to provide baseline data for comparison with other management options for use of DU. To PICS considered in this report include: Retrievable disposal; permanent disposal; health hazards; radiation toxicity and chemical toxicity.

  9. Disposable telemetry cable deployment system

    DOE Patents [OSTI]

    Holcomb, David Joseph (Sandia Park, NM)

    2000-01-01

    A disposable telemetry cable deployment system for facilitating information retrieval while drilling a well includes a cable spool adapted for insertion into a drill string and an unarmored fiber optic cable spooled onto the spool cable and having a downhole end and a stinger end. Connected to the cable spool is a rigid stinger which extends through a kelly of the drilling apparatus. A data transmission device for transmitting data to a data acquisition system is disposed either within or on the upper end of the rigid stinger.

  10. Modifications to Replacement Costs System

    SciTech Connect (OSTI)

    Godec, M. [ICF Resources, Inc., Fairfax, VA (United States)

    1989-05-18

    The purpose of this memorandum is to document the improvements and modifications made to the Replacement Costs of Crude Oil (REPCO) Supply Analysis System. While some of this work was performed under our previous support contract to DOE/ASFE, we are presenting all modifications and improvements are presented here for completeness. The memo primarily documents revisions made to the Lower-48 Onshore Model. Revisions and modifications made to other components and models in the REPCO system which are documented elsewhere are only highlighted in this memo. Generally, the modifications made to the Lower-48 Onshore Model reflect changes that have occurred in domestic drilling, oil field costs, and reserves since 1982, the date of the most recent available data used for the original Replacement Costs report, published in 1985.

  11. Replacing Lightbulbs and Ballasts | Department of Energy

    Broader source: Energy.gov (indexed) [DOE]

    Replace frequently used bulbs with more energy efficient options to save money and energy. Replace frequently used bulbs with more energy efficient options to save money and energy. Matching replacement lightbulbs to existing fixtures and ballasts can be tricky, especially with older fixtures. Using new fixtures made for new lightbulbs gives you the greatest energy savings, reliability, and longevity compared with simply replacing bulbs. Before replacing a lightbulb and/or ballast in a light

  12. Replacement Capability for Disposal of Remote-Handled Low-Level...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... INTEC Idaho Nuclear Technology and Engineering Center LCF latent cancer fatality LLW ... received by specified tissues of the body and a tissue-specific weighting factor. ...

  13. RealGasBrine v1.0 option of TOUGH+ v1.5

    SciTech Connect (OSTI)

    2015-02-27

    RealGasBrine v1.0 is a numerical code that for the simulation of the behavior of gas-bearing porous and/fractured geologic media. It is an option of TOUGH+ v1.5 [Moridis, 2014], a successor to the TOUGH2 [Pruess et al., 1999; 2012] family of codes for multi-component, multiphase ?uid and heat ?ow developed at the Lawrence Berkeley National Laboratory. RealGasBrine v1.0 needs the TOUGH+ v1.5 core code in order to compile and execute. It is written in standard FORTRAN 95/2003, and can be run on any computational platform (workstation, PC, Macintosh) for which such compilers are available. RealGasBrine v1.0 describes the non-isothermal two- (for pure water) or three-phase (for brine) flow of an aqueous phase and a real gas mixture in a gas-bearing medium, with a particular focus in ultra-tight (such as tight-sand and shale gas) systems. Up to 12 individual real gases can be tracked, and salt can precipitate as solid halite. The capabilities of the code include coupled flow and thermal effects, real gas behavior, Darcy and non-Darcy flow, several isotherm options of gas sorption onto the grains of the porous media, complex fracture descriptions, gas solubility into water, and geomechanical effects on flow properties. RealGasBrine v1.0 allows the study of flow and transport of fluids and heat over a wide range of time frames and spatial scales not only in gas reservoirs, but also in any problem involving the flow of gases in geologic media, including the geologic storage of greenhouse gas mixtures, the behavior of geothermal reservoirs with multi-component condensable (H2O and CO2) and non-condensable gas mixtures, the transport of water and released H2 in nuclear waste storage applications, etc.

  14. RealGasBrine v1.0 option of TOUGH+ v1.5

    Energy Science and Technology Software Center (OSTI)

    2015-02-27

    RealGasBrine v1.0 is a numerical code that for the simulation of the behavior of gas-bearing porous and/fractured geologic media. It is an option of TOUGH+ v1.5 [Moridis, 2014], a successor to the TOUGH2 [Pruess et al., 1999; 2012] family of codes for multi-component, multiphase ?uid and heat ?ow developed at the Lawrence Berkeley National Laboratory. RealGasBrine v1.0 needs the TOUGH+ v1.5 core code in order to compile and execute. It is written in standard FORTRANmore95/2003, and can be run on any computational platform (workstation, PC, Macintosh) for which such compilers are available. RealGasBrine v1.0 describes the non-isothermal two- (for pure water) or three-phase (for brine) flow of an aqueous phase and a real gas mixture in a gas-bearing medium, with a particular focus in ultra-tight (such as tight-sand and shale gas) systems. Up to 12 individual real gases can be tracked, and salt can precipitate as solid halite. The capabilities of the code include coupled flow and thermal effects, real gas behavior, Darcy and non-Darcy flow, several isotherm options of gas sorption onto the grains of the porous media, complex fracture descriptions, gas solubility into water, and geomechanical effects on flow properties. RealGasBrine v1.0 allows the study of flow and transport of fluids and heat over a wide range of time frames and spatial scales not only in gas reservoirs, but also in any problem involving the flow of gases in geologic media, including the geologic storage of greenhouse gas mixtures, the behavior of geothermal reservoirs with multi-component condensable (H2O and CO2) and non-condensable gas mixtures, the transport of water and released H2 in nuclear waste storage applications, etc.less

  15. DISPOSAL OF EXCESS REAL PROPERTY

    Office of Legacy Management (LM)

    . . : '* FEB 1972. : . .. - .. ..' *. ,; --.. . *..,,, :. :-, -, ' :.: t:-,...: : ,. -.". .- v ;; -'.1.;, ; . , DISPOSAL OF EXCESS REAL PROPERTY PARCEL 228 " . ;: 'i: .-. ' ' . -- - , *: , ; b;- .;.= ' i .; ,s ' ; .: '- :. ,S,, - ; * ^. ',. *. ;;: : ' " . - .. ,'~', approval is requested to report as excess a 20-acre;tract of landand improvements. The tract is located within the Oak Ridge comnunity near the intersection of Melton Lake Drive and the Oak Ridge Turnpike and is

  16. Reduced-Order Model for the Geochemical Impacts of Carbon Dioxide, Brine and Trace Metal Leakage into an Unconfined, Oxidizing Carbonate Aquifer, Version 2.1

    SciTech Connect (OSTI)

    Bacon, Diana H.

    2013-03-31

    The National Risk Assessment Partnership (NRAP) consists of 5 U.S DOE national laboratories collaborating to develop a framework for predicting the risks associated with carbon sequestration. The approach taken by NRAP is to divide the system into components, including injection target reservoirs, wellbores, natural pathways including faults and fractures, groundwater and the atmosphere. Next, develop a detailed, physics and chemistry-based model of each component. Using the results of the detailed models, develop efficient, simplified models, termed reduced order models (ROM) for each component. Finally, integrate the component ROMs into a system model that calculates risk profiles for the site. This report details the development of the Groundwater Geochemistry ROM for the Edwards Aquifer at PNNL. The Groundwater Geochemistry ROM for the Edwards Aquifer uses a Wellbore Leakage ROM developed at LANL as input. The detailed model, using the STOMP simulator, covers a 5x8 km area of the Edwards Aquifer near San Antonio, Texas. The model includes heterogeneous hydraulic properties, and equilibrium, kinetic and sorption reactions between groundwater, leaked CO2 gas, brine, and the aquifer carbonate and clay minerals. Latin Hypercube sampling was used to generate 1024 samples of input parameters. For each of these input samples, the STOMP simulator was used to predict the flux of CO2 to the atmosphere, and the volume, length and width of the aquifer where pH was less than the MCL standard, and TDS, arsenic, cadmium and lead exceeded MCL standards. In order to decouple the Wellbore Leakage ROM from the Groundwater Geochemistry ROM, the response surface was transformed to replace Wellbore Leakage ROM input parameters with instantaneous and cumulative CO2 and brine leakage rates. The most sensitive parameters proved to be the CO2 and brine leakage rates from the well, with equilibrium coefficients for calcite and dolomite, as well as the number of illite and kaolinite sorption sites proving to be of secondary importance. The Groundwater Geochemistry ROM was developed using nonlinear regression to fit the response surface with a quadratic polynomial. The goodness of fit was excellent for the CO2 flux to the atmosphere, and very good for predicting the volumes of groundwater exceeding the pH, TDS, As, Cd and Pb threshold values.

  17. Disposal of NORM waste in salt caverns

    SciTech Connect (OSTI)

    Veil, J.A.; Smith, K.P.; Tomasko, D.; Elcock, D.; Blunt, D.; Williams, G.P.

    1998-07-01

    Some types of oil and gas production and processing wastes contain naturally occurring radioactive materials (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, there are no fatal flaws that would prevent a state regulatory agency from approving cavern disposal of NORM. On the basis of the costs charged by caverns currently used for disposal of nonhazardous oil field waste (NOW), NORM waste disposal caverns could be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

  18. Transmittal Memo for Disposal Authorization Statement

    Broader source: Energy.gov [DOE]

    The Low-Level Waste Disposal Facility Federal Review Group (LFRG) has conducted a review of the Savannah River Site (SRS) Saltstone Disposal Facility (SDF) 2009 performance assessment (PA) in...

  19. CX-011223: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Bryan Mound Brine Disposal Pump Replacement (Install) CX(s) Applied: B5.2 Date: 10/28/2013 Location(s): Texas Offices(s): Strategic Petroleum Reserve Field Office

  20. Electrochemical apparatus comprising modified disposable rectangular

    Office of Scientific and Technical Information (OSTI)

    cuvette (Patent) | SciTech Connect Electrochemical apparatus comprising modified disposable rectangular cuvette Citation Details In-Document Search Title: Electrochemical apparatus comprising modified disposable rectangular cuvette Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by

  1. Electrochemical Apparatus with Disposable and Modifiable Parts

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    research Benefits: Incorporates disposable, commercially available cuvettes Modifiable design Allows multiple experiments using a single solution Designed for interface with...

  2. Maybell, Colorado, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Maybell, Colorado, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site at Maybell, Colorado. This site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Maybell, Colorado, Disposal Site Site Description and History The Maybell disposal site is located in Moffat County in northwest Colorado. The small town of Maybell is about 5 miles southwest of the site. The site is also the

  3. Spook, Wyoming, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    I UMTRCA Title I Spook, Wyoming, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site located at Spook, Wyoming. The site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Spook, Wyoming, Disposal Site Site Description and History The Spook disposal site is a former uranium-ore upgrading facility in Converse County, Wyoming, about 32 miles north of Glenrock. The site is

  4. Sustainable Disposal Cell Covers: Legacy Management Practices,

    Energy Savers [EERE]

    Improvements, and Long-Term Performance | Department of Energy Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance PDF icon Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance More

  5. Falls City, Texas, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Falls City, Texas, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site located at Falls City, Texas. The site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Falls City Disposal Site Site Description and History The Falls City disposal site is the location of a former uranium-ore processing facility in Karnes County, Texas, approximately 40 miles southeast of San Antonio

  6. Lowman, Idaho, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Lowman, Idaho, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site located at Lowman, Idaho. The site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Lowman, Idaho, Disposal Site Site Description and History The Lowman disposal site is the location of a former mechanical concentrator for sands containing rare-earth elements, uranium, and thorium. The site is located in

  7. Maxey Flats, Kentucky, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    3 Fact Sheet Maxey Flats, Kentucky, Disposal Site This fact sheet provides information about the Maxey Flats, Kentucky, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under the Comprehensive Environmental Response, Compensation, and Liability Act. Location of the Maxey Flats, Kentucky, Disposal Site Site Description and History The Maxey Flats site is an inactive, low-level radioactive waste disposal site located in eastern Kentucky about 10

  8. Monticello, Utah, Disposal and Processing Sites

    Office of Legacy Management (LM)

    Monticello, Utah, Disposal and Processing Sites This fact sheet provides information about the Monticello, Utah, Disposal and Processing Sites. These sites are managed by the U.S. Department of Energy Office of Legacy Management under the Comprehensive Environmental Response, Compensation, and Liability Act. Location of the Monticello, Utah, Disposal and Processing Sites Site Description and History The Monticello, Utah, Disposal and Processing Sites are located in and near the city of

  9. Sherwood, Washington, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Sherwood, Washington, Disposal Site This fact sheet provides information about the Sherwood, Washington, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Sherwood, Washington, Disposal Site Site Description and History The Sherwood disposal site is a former uranium-ore processing site operated by Western Nuclear, Inc. The site is in Stevens County near the

  10. Bluewater, New Mexico, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Bluewater, New Mexico, Disposal Site This fact sheet provides information about the Bluewater, New Mexico, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Bluewater, New Mexico, Disposal Site Site Description and History The Bluewater disposal site is in Cibola County in west-central New Mexico. Anaconda Copper Company constructed the original

  11. Burrell, Pennsylvania, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Burrell, Pennsylvania, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site located at Burrell, Pennsylvania. The site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Burrell Disposal Site Site Description and History The Burrell disposal site is a former railroad landfll located about 1 mile east of the Borough of Blairsville, Indiana County, in southwestern Pennsylvania.

  12. Risk assessment of nonhazardous oil-field waste disposal in salt caverns.

    SciTech Connect (OSTI)

    Elcock, D.

    1998-03-10

    Salt caverns can be formed in underground salt formations incidentally as a result of mining or intentionally to create underground chambers for product storage or waste disposal. For more than 50 years, salt caverns have been used to store hydrocarbon products. Recently, concerns over the costs and environmental effects of land disposal and incineration have sparked interest in using salt caverns for waste disposal. Countries using or considering using salt caverns for waste disposal include Canada (oil-production wastes), Mexico (purged sulfates from salt evaporators), Germany (contaminated soils and ashes), the United Kingdom (organic residues), and the Netherlands (brine purification wastes). In the US, industry and the regulatory community are pursuing the use of salt caverns for disposal of oil-field wastes. In 1988, the US Environmental Protection Agency (EPA) issued a regulatory determination exempting wastes generated during oil and gas exploration and production (oil-field wastes) from federal hazardous waste regulations--even though such wastes may contain hazardous constituents. At the same time, EPA urged states to tighten their oil-field waste management regulations. The resulting restrictions have generated industry interest in the use of salt caverns for potentially economical and environmentally safe oil-field waste disposal. Before the practice can be implemented commercially, however, regulators need assurance that disposing of oil-field wastes in salt caverns is technically and legally feasible and that potential health effects associated with the practice are acceptable. In 1996, Argonne National Laboratory (ANL) conducted a preliminary technical and legal evaluation of disposing of nonhazardous oil-field wastes (NOW) into salt caverns. It investigated regulatory issues; the types of oil-field wastes suitable for cavern disposal; cavern design and location considerations; and disposal operations, closure and remediation issues. It determined that if caverns are sited and designed well, operated carefully, closed properly, and monitored routinely, they could, from technical and legal perspectives, be suitable for disposing of oil-field wastes. On the basis of these findings, ANL subsequently conducted a preliminary risk assessment on the possibility that adverse human health effects (carcinogenic and noncarcinogenic) could result from exposure to contaminants released from the NOW disposed of in salt caverns. The methodology for the risk assessment included the following steps: identifying potential contaminants of concern; determining how humans could be exposed to these contaminants; assessing contaminant toxicities; estimating contaminant intakes; and estimating human cancer and noncancer risks. To estimate exposure routes and pathways, four postclosure cavern release scenarios were assessed. These were inadvertent cavern intrusion, failure of the cavern seal, failure of the cavern through cracks, failure of the cavern through leaky interbeds, and partial collapse of the cavern roof. Assuming a single, generic, salt cavern and generic oil-field wastes, potential human health effects associated with constituent hazardous substances (arsenic, benzene, cadmium, and chromium) were assessed under each of these scenarios. Preliminary results provided excess cancer risk and hazard index (for noncancer health effects) estimates that were well within the EPA target range for acceptable exposure risk levels. These results lead to the preliminary conclusion that from a human health perspective, salt caverns can provide an acceptable disposal method for nonhazardous oil-field wastes.

  13. Recovery Act: Molecular Simulation of Dissolved Inorganic Carbons for Underground Brine CO2 Sequestration

    SciTech Connect (OSTI)

    Goddard, William

    2012-11-30

    To further our understanding and develop the method for measuring the DICs under geological sequestration conditions, we studied the infrared spectra of DICs under high pressure and temperature conditions. First principles simulations of DICs in brine conditions were performed using a highly optimized ReaxFF-DIC forcefield. The thermodynamics stability of each species were determined using the 2PT method, and shown to be consistent with the Reax simulations. More importantly, we have presented the IR spectra of DIC in real brine conditions as a function of temperature and pressure. At near earth conditions, we find a breaking of the O-C-O bending modes into asymmetric and symmetric modes, separated by 100cm{sup -1} at 400K and 5 GPa. These results can now be used to calibrate FTIR laser measurements.

  14. Biochemical solubilization of toxic salts from residual geothermal brines and waste waters

    DOE Patents [OSTI]

    Premuzic, E.T.; Lin, M.S.

    1994-11-22

    A method of solubilizing metal salts such as metal sulfides in a geothermal sludge using mutant Thiobacilli selected for their ability to metabolize metal salts at high temperature is disclosed. The method includes the introduction of mutated Thiobacillus ferrooxidans and Thiobacillus thiooxidans to a geothermal sludge or brine. The microorganisms catalyze the solubilization of metal salts. For instance, in the case of metal sulfides, the microorganisms catalyze the solubilization to form soluble metal sulfates. 54 figs.

  15. Biochemical solubilization of toxic salts from residual geothermal brines and waste waters

    DOE Patents [OSTI]

    Premuzic, Eugene T. (East Moriches, NY); Lin, Mow S. (Rocky Point, NY)

    1994-11-22

    A method of solubilizing metal salts such as metal sulfides in a geothermal sludge using mutant Thiobacilli selected for their ability to metabolize metal salts at high temperature is disclosed, The method includes the introduction of mutated Thiobacillus ferrooxidans and Thiobacillus thiooxidans to a geothermal sludge or brine. The microorganisms catalyze the solubilization of metal salts, For instance, in the case of metal sulfides, the microorganisms catalyze the solubilization to form soluble metal sulfates.

  16. Utilizing rare earth elements as tracers in high TDS reservoir brines in CCS applications

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    McLing, Travis; Smith, William; Smith, Robert

    2014-12-31

    In this paper we report the result of research associated with the testing of a procedures necessary for utilizing natural occurring trace elements, specifically the Rare Earth Elements (REE) as geochemical tracers in Carbon Capture and Storage (CCS) applications. Trace elements, particularly REE may be well suited to serve as in situ tracers for monitoring geochemical conditions and the migration of CO₂-charged waters within CCS storage systems. We have been conducting studies to determine the efficacy of using REE as a tracer and characterization tool in the laboratory, at a CCS analogue site in Soda Springs, Idaho, and at amore » proposed CCS reservoir at the Rock Springs Uplift, Wyoming. Results from field and laboratory studies have been encouraging and show that REE may be an effective tracer in CCS systems and overlying aquifers. In recent years, a series of studies using REE as a natural groundwater tracer have been conducted successfully at various locations around the globe. Additionally, REE and other trace elements have been successfully used as in situ tracers to describe the evolution of deep sedimentary Basins. Our goal has been to establish naturally occurring REE as a useful monitoring measuring and verification (MMV) tool in CCS research because formation brine chemistry will be particularly sensitive to changes in local equilibrium caused by the addition of large volumes of CO₂. Because brine within CCS target formations will have been in chemical equilibrium with the host rocks for millions of years, the addition of large volumes of CO₂ will cause reactions in the formation that will drive changes to the brine chemistry due to the pH change caused by the formation of carbonic acid. This CO₂ driven change in formation fluid chemistry will have a major impact on water rock reaction equilibrium in the formation, which will impart a change in the REE fingerprint of the brine that can measured and be used to monitor in situ reservoir conditions. Our research has shown that the REE signature imparted to the formation fluid by the introduction of CO₂ to the formation, can be measured and tracked as part of an MMV program. Additionally, this REE fingerprint may serve as an ideal tracer for fluid migration, both within the CCS target formation, and should formation fluids migrate into overlying aquifers. However application of REE and other trace elements to CCS system is complicated by the high salt content of the brines contained within the target formations. In the United States by regulation, in order for a geologic reservoir to be considered suitable for carbon storage, it must contain formation brine with total dissolved solids (TDS) > 10,000 ppm, and in most cases formation brines have TDS well in excess of that threshold. The high salinity of these brines creates analytical problems for elemental analysis, including element interference with trace metals in Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) (i.e. element mass overlap due to oxide or plasma phenomenon). Additionally, instruments like the ICP-MS that are sensitive enough to measure trace elements down to the parts per trillion level are quickly oversaturated when water TDS exceeds much more than 1,000 ppm. Normally this problem is dealt with through dilution of the sample, bringing the water chemistry into the instruments working range. However, dilution is not an option when analyzing these formation brines for trace metals, because trace elements, specifically the REE, which occur in aqueous solutions at the parts per trillion levels. Any dilution of the sample would make REE detection impossible. Therefore, the ability to use trace metals as in situ natural tracers in high TDS brines environments requires the development of methods for pre-concentrating trace elements, while reducing the salinity and associated elemental interference such that the brines can be routinely analyzed by standard ICP-MS methods. As part of the Big Sky Carbon Sequestration Project the INL-CAES has developed a rapid, easy to use process that pre-concentrates trace metals, including REE, up to 100x while eliminating interfering ions (e.g. Ba, Cl). The process is straightforward, inexpensive, and requires little infrastructure, using only a single chromatography column with inexpensive, reusable, commercially available resins and wash chemicals. The procedure has been tested with synthetic brines (215,000 ppm or less TDS) and field water samples (up to 5,000 ppm TDS). Testing has produced data of high quality with REE capture efficiency exceeding 95%, while reducing interfering elements by > 99%.« less

  17. RealGasBrine v1.0 option of TOUGH+ v1.5

    Energy Science and Technology Software Center (OSTI)

    2015-02-27

    RealGasBrine v1.0 is a numerical code that for the simulation of the behavior of gas-bearing porous and/fractured geologic media. It is an option of TOUGH+ v1.5 [Moridis, 2014], a successor to the TOUGH2 [Pruess et al., 1999; 2012] family of codes for multi-component, multiphase ?uid and heat ?ow developed at the Lawrence Berkeley National Laboratory. RealGasBrine v1.0 needs the TOUGH+ v1.5 core code in order to compile and execute. It is written in standard FORTRANmore » 95/2003, and can be run on any computational platform (workstation, PC, Macintosh) for which such compilers are available. RealGasBrine v1.0 describes the non-isothermal two- (for pure water) or three-phase (for brine) flow of an aqueous phase and a real gas mixture in a gas-bearing medium, with a particular focus in ultra-tight (such as tight-sand and shale gas) systems. Up to 12 individual real gases can be tracked, and salt can precipitate as solid halite. The capabilities of the code include coupled flow and thermal effects, real gas behavior, Darcy and non-Darcy flow, several isotherm options of gas sorption onto the grains of the porous media, complex fracture descriptions, gas solubility into water, and geomechanical effects on flow properties. RealGasBrine v1.0 allows the study of flow and transport of fluids and heat over a wide range of time frames and spatial scales not only in gas reservoirs, but also in any problem involving the flow of gases in geologic media, including the geologic storage of greenhouse gas mixtures, the behavior of geothermal reservoirs with multi-component condensable (H2O and CO2) and non-condensable gas mixtures, the transport of water and released H2 in nuclear waste storage applications, etc.« less

  18. Integrated Disposal Facility - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Projects & Facilities Integrated Disposal Facility About Us About Hanford Cleanup Hanford History Hanford Site Wide Programs Contact Us 100 Area 118-K-1 Burial Ground 200 Area 222-S Laboratory 242-A Evaporator 300 Area 324 Building 325 Building 400 Area/Fast Flux Test Facility 618-10 and 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and Interim Storage Area Canyon Facilities Cold Test Facility D and DR Reactors Effluent Treatment Facility Environmental

  19. DOE SPENT NUCLEAR FUEL DISPOSAL CONTAINER

    SciTech Connect (OSTI)

    F. Habashi

    1998-06-26

    The DOE Spent Nuclear Fuel Disposal Container (SNF DC) supports the confinement and isolation of waste within the Engineered Barrier System of the Mined Geologic Disposal System (MGDS). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the access mains, and emplaced in emplacement drifts. The DOE Spent Nuclear Fuel Disposal Container provides long term confinement of DOE SNF waste, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The DOE SNF Disposal Containers provide containment of waste for a designated period of time, and limit radionuclide release thereafter. The disposal containers maintain the waste in a designated configuration, withstand maximum handling and rockfall loads, limit the individual waste canister temperatures after emplacement. The disposal containers also limit the introduction of moderator into the disposal container during the criticality control period, resist corrosion in the expected repository environment, and provide complete or limited containment of waste in the event of an accident. Multiple disposal container designs may be needed to accommodate the expected range of DOE Spent Nuclear Fuel. The disposal container will include outer and inner barrier walls and outer and inner barrier lids. Exterior labels will identify the disposal container and contents. Differing metal barriers will support the design philosophy of defense in depth. The use of materials with different failure mechanisms prevents a single mode failure from breaching the waste package. The corrosion-resistant inner barrier and inner barrier lid will be constructed of a high-nickel alloy and the corrosion-allowance outer barrier and outer barrier lid will be made of carbon steel. The DOE Spent Nuclear Fuel Disposal Containers interface with the emplacement drift environment by transferring heat from the waste to the external environment and by protecting the DOE waste canisters and their contents from damage/degradation by the external environment. The disposal containers also interface with the SNF by limiting access of moderator and oxidizing agents to the waste. The disposal containers interface with the Ex-Container System's emplacement drift disposal container supports. The disposal containers interface with the Canister Transfer System, Waste Emplacement System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and remediation of the disposal container.

  20. Aerosol can waste disposal device

    DOE Patents [OSTI]

    O'Brien, Michael D.; Klapperick, Robert L.; Bell, Chris

    1993-01-01

    Disclosed is a device for removing gases and liquid from containers. The ice punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container.

  1. Aerosol can waste disposal device

    DOE Patents [OSTI]

    O'Brien, M.D.; Klapperick, R.L.; Bell, C.

    1993-12-21

    Disclosed is a device for removing gases and liquid from containers. The device punctures the bottom of a container for purposes of exhausting gases and liquid from the container without their escaping into the atmosphere. The device includes an inner cup or cylinder having a top portion with an open end for receiving a container and a bottom portion which may be fastened to a disposal or waste container in a substantially leak-proof manner. A piercing device is mounted in the lower portion of the inner cylinder for puncturing the can bottom placed in the inner cylinder. An outer cylinder having an open end and a closed end fits over the top portion of the inner cylinder in telescoping engagement. A force exerted on the closed end of the outer cylinder urges the bottom of a can in the inner cylinder into engagement with the piercing device in the bottom of the inner cylinder to form an opening in the can bottom, thereby permitting the contents of the can to enter the disposal container. 7 figures.

  2. Replacing an Oversized and Underloaded Electric Motor | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Replacing an Oversized and Underloaded Electric Motor Replacing an Oversized and Underloaded Electric Motor This fact sheet will assist in decisions regarding replacement of...

  3. Disposal of tritium-exposed metal hydrides

    SciTech Connect (OSTI)

    Nobile, A.; Motyka, T.

    1991-01-01

    A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed.

  4. Disposal of tritium-exposed metal hydrides

    SciTech Connect (OSTI)

    Nobile, A.; Motyka, T.

    1991-12-31

    A plan has been established for disposal of tritium-exposed metal hydrides used in Savannah River Site (SRS) tritium production or Materials Test Facility (MTF) R&D operations. The recommended plan assumes that the first tritium-exposed metal hydrides will be disposed of after startup of the Solid Waste Disposal Facility (SWDF) Expansion Project in 1992, and thus the plan is consistent with the new disposal requiremkents that will be in effect for the SWDF Expansion Project. Process beds containing tritium-exposed metal hydride powder will be disposed of without removal of the powder from the bed; however, disposal of tritium-exposed metal hydride powder that has been removed from its process vessel is also addressed.

  5. Retail Replacement Lamps | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    CALiPER Testing » Application Reports » Retail Replacement Lamps Retail Replacement Lamps Annual CALiPER testing of A19, G25, candelabra, night light, MR16/PAR16, PAR20, and PAR30 replacement lamps - purchased directly from store shelves - offers insights on performance trends from year to year. The report findings offer valuable insights for manufacturers and retailers alike. Retail Lamps Study 3 (48 pages, February 2014) Retail Lamps Study 3.1: Dimming, Flicker, and Power Quality

  6. CX-010712: Categorical Exclusion Determination

    Broader source: Energy.gov [DOE]

    Replace West Hackberry Brine Disposal System Header from MOV-51’s to WHT-14/15 Brine Tanks with HDPE Pipe CX(s) Applied: B5.2 Date: 07/03/2013 Location(s): Louisiana Offices(s): Strategic Petroleum Reserve Field Office

  7. Grand Coulee & Hungry Horse SCADA Replacement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    extensive maintenance and repairs. The turbine hubs on these units have experienced chronic oil leaks. The history of problems led to a decision to replace the turbine runners...

  8. Ni Clusterbank Replacement Project | Argonne Leadership Computing...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Ni Clusterbank Replacement Project Event Sponsor: Argonne Leadership Computing Facility Seminar Start Date: Oct 20 2015 - 12:00pm BuildingRoom: Building 241Room D173...

  9. Z-Bed Recovery Water Disposal

    Office of Environmental Management (EM)

    Z-Bed Recovery Water Disposal Tritium Programs Engineering Louis Boone Josh Segura Savannah River Nuclear Solutions, LLC M-TRT-H-00087 Rev 0 Date: 4/10/2014 Tritium Facilities Purpose * Provide detailed explanation of the plan to capture and dispose of Z-Bed Recovery (ZR) water. Agenda * New Technology * Background * Z-Bed Recovery Water Disposal * Cost Saving * Alternatives New Technology * Dry Disconnect Fittings * Double Door Transfer Container (DDTC) * Bucket (Stainless Steel ASME pressure

  10. Paducah Waste Disposal | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Remediation » Paducah Waste Disposal Paducah Waste Disposal The U.S. Department of Energy (DOE) is looking at options to dispose of waste that will be generated from further cleanup of the Paducah Gaseous Diffusion Plant. Cleanup of the Site is projected to create an estimated 3.6 million cubic yards of demolition debris, metals, soils, asbestos and other material. DOE is using the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA) process to make a decision

  11. Edgemont, South Dakota, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Edgemont, South Dakota, Disposal Site This fact sheet provides information about the Edgemont, South Dakota, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Edgemont, South Dakota, Disposal Site Site Description and History The former Edgemont uranium mill is located in Edgemont, South Dakota, in Fall River County near the southwest corner of South Dakota.

  12. River Protection Project (RPP) Immobilized Low Activity Waste (ILAW) Disposal Plan

    SciTech Connect (OSTI)

    BRIGGS, M.G.

    2000-09-22

    This document replaces HNF-1517, Rev 2 which is deleted. It incorporates updates to reflect changes in programmatic direction associated with the vitrification plant contract change and associated DOE/ORP guidance. In addition it incorporates the cancellation of Project W-465, Grout Facility, and the associated modifications to Project W-520, Immobilized High-Level Waste Disposal Facility. It also includes document format changes and section number modifications consistent with CH2M HILL Hanford Group, Inc. procedures.

  13. WPCF Underground Injection Control Disposal Permit Evaluation...

    Open Energy Info (EERE)

    WPCF Underground Injection Control Disposal Permit Evaluation and Fact Sheet Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: WPCF Underground Injection...

  14. DOE Applauds Opening of Historic Disposal Facility

    Broader source: Energy.gov [DOE]

    ANDREWS, Texas – DOE officials participated in an event today to celebrate the opening of the first commercial disposal facility of its kind.

  15. Tuba City, Arizona, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    UMTRCA Title I UMTRCA Title I Page 1 of 3 Fact Sheet Tuba City, Arizona, Disposal Site This fact sheet provides information about the Tuba City, Arizona, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title I of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Tuba City, Arizona, Disposal Site Site Description and History The Tuba City, Arizona, Disposal Site is within the Navajo Nation and close to the Hopi

  16. Green River, Utah, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Green River, Utah, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site near Green River, Utah. This site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Green River, Utah, Disposal Site Site Description and History The Green River disposal site is about 0.5 mile east of the Green River and 1.5 miles southeast of the city of Green River, Utah. The site consists of an

  17. PILOT TESTING: PRETREATMENT OPTIONS TO ALLOW RE-USE OF FRAC FLOWBACK AND PRODUCED BRINE FOR GAS SHALE RESOURCE DEVELOPMENT

    SciTech Connect (OSTI)

    Burnett, David

    2012-12-31

    The goal of the A&M DOE NETL Project No. DE-FE0000847 was to develop a mobile, multifunctional water treatment capability designed specifically for pre-treatment of field waste brine. The project consisted of constructing s mobile field laboratory incorporating new technology for treating high salinity produced water and using the lab to conduct a side-by-side comparison between this new technology and that already existing in field operations. A series of four field trials were performed utilizing the mobile unit to demonstrate the effectiveness of different technology suitable for use with high salinity flow back brines and produced water. The design of the mobile unit was based on previous and current work at the Texas A&M Separation Sciences Pilot Plant. The several treatment techniques which have been found to be successful in both pilot plant and field tests had been tested to incorporate into a single multifunctional process train. Eight different components were evaluated during the trials, two types of oil and grease removal, one BTEX removal step, three micro-filters, and two different nanofilters. The performance of each technique was measured by its separation efficiency, power consumption, and ability to withstand fouling. The field trials were a success. Four different field brines were evaluated in the first trial in New York. Over 16,000 gallons of brine were processed. Using a power cost of $.10 per kWh, media pretreatment power use averaged $0.004 per barrel, solids removal $.04 per barrel and brine softening $.84 per barrel. Total power cost was approximately $1.00 per barrel of fluid treated. In Pennsylvania, brines collected from frac ponds were tested in two additional trials. Each of the brines was converted to an oil-free, solids-free brine with no biological activity. Brines were stable over time and would be good candidates for use as a make-up fluid in a subsequent fracturing fluid design. Reports on all of the field trials and subcontractor research have been summarized in this Final Report. Individual field trial reports and research reports are contained in the companion volume titled Appendices

  18. Hanford Landfill Reaches 15 Million Tons Disposed- Waste Disposal Mark Shows Success Cleaning Up River Corridor

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. – The U.S. Department of Energy (DOE) and its contractors have disposed of 15 million tons of contaminated material at the Environmental Restoration Disposal Facility (ERDF) since the facility began operations in 1996.

  19. Application of Generic Disposal System Models | Department of Energy

    Energy Savers [EERE]

    Application of Generic Disposal System Models Application of Generic Disposal System Models Two of the high priorities for UFDC disposal R&D are design concept development and disposal system modeling; these are directly addressed in the Generic Disposal Systems Analysis (GDSA) work. This report describes specific GDSA activities during fiscal year 2015 toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA

  20. Generic Deep Geologic Disposal Safety Case | Department of Energy

    Office of Environmental Management (EM)

    Deep Geologic Disposal Safety Case Generic Deep Geologic Disposal Safety Case The Generic Deep Geologic Disposal Safety Case presents generic information that is of use in understanding potential deep geologic disposal options in the U.S. for used nuclear fuel (UNF) from reactors and high-level radioactive waste (HLW). Potential disposal options include mined disposal in a variety of geologic media (e.g., salt, shale, granite), and deep borehole disposal in basement rock. The Generic Safety Case

  1. The sup 36 Cl ages of the brines in the Magadi-Natron basin, east Africa

    SciTech Connect (OSTI)

    Kaufman, A.; Margaritz, M.A.; Hollos, G. ); Paul, M.; Boaretto, E. ); Hillaire-Marcel, C. ); Taieb, M. )

    1990-10-01

    The depression in the East African Rift which includes both Lake Magadi and Lake Natron forms a closed basin within which almost all the dissolved chloride originates in precipitation, since there is no important source of very ancient sedimentary chloride. This provides an ideal setting for the evaluation of the {sup 36}Cl methodology as a geochemical and hydrological tracer. The main source of recent water, as represented by the most dilute samples measured, is characterized by a {sup 36}Cl/Cl ratio of 2.5 {times} 10{sup {minus}14}, in agreement with the calculated value expected in precipitation. Surface evaporation increases the chlorinity of the local freshwater inflow by about a factor of 110 without changing the isotopic ratio, indicating that little chloride enters the system in the form of sediment leachate. A second type of brine found in the basin occurs in a hot deep groundwater reservoir and is characterized by lower {sup 36}Cl/Cl ratios (<1.2 {times} 10{sup {minus}14}). By comparing this value with the 2.5 {times} 10{sup {minus}14} in recent recharge, one obtains an approximate salt accumulation age of 760 Ka which is consistent with thee time of the first appearance of the lake. These older brines also have lower {sup 18}O and {sup 2}H values which indicate that they were recharged during a climatically different era. The {sup 36}Cl/Cl ratios in the inflowing waters and in the accumulated brine, together with the known age of the Lake Magadi basin, may be used to estimate the importance of the hypogene and epigene, as opposed to the meteoric, mode of {sup 36}Cl production. Such a calculation shows that the hypogene and epigene processes together contribute less than 6% of the total {sup 36}Cl present in the lake.

  2. Mission Need Statement for the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Project

    SciTech Connect (OSTI)

    Lisa Harvego

    2009-06-01

    The Idaho National Laboratory proposes to establish replacement remote-handled low-level waste disposal capability to meet Nuclear Energy and Naval Reactors mission-critical, remote-handled low-level waste disposal needs beyond planned cessation of existing disposal capability at the end of Fiscal Year 2015. Remote-handled low-level waste is generated from nuclear programs conducted at the Idaho National Laboratory, including spent nuclear fuel handling and operations at the Naval Reactors Facility and operations at the Advanced Test Reactor. Remote-handled low-level waste also will be generated by new programs and from segregation and treatment (as necessary) of remote-handled scrap and waste currently stored in the Radioactive Scrap and Waste Facility at the Materials and Fuels Complex. Replacement disposal capability must be in place by Fiscal Year 2016 to support uninterrupted Idaho operations. This mission need statement provides the basis for the laboratorys recommendation to the Department of Energy to proceed with establishing the replacement remote-handled low-level waste disposal capability, project assumptions and constraints, and preliminary cost and schedule information for developing the proposed capability. Without continued remote-handled low-level waste disposal capability, Department of Energy missions at the Idaho National Laboratory would be jeopardized, including operations at the Naval Reactors Facility that are critical to effective execution of the Naval Nuclear Propulsion Program and national security. Remote-handled low-level waste disposal capability is also critical to the Department of Energys ability to meet obligations with the State of Idaho.

  3. Brine migration test for Asse Mine, Federal Republic of Germany: final test plan

    SciTech Connect (OSTI)

    Not Available

    1983-07-01

    The United States and the Federal Republic of Germany (FRG) will conduct a brine migration test in the Asse Salt Mine in the FRG as part of the US/FRG Cooperative Radioactive Waste Management Agreement. Two sets of two tests each will be conducted to study both liquid inclusion migration and vapor migration in the two salt types chosen for the experiments: (1) pure salt, for its characteristics similar to the salt that might occur in potential US repositories, and (2) transitional salt, for its similarity to the salt that might occur in potential repositories in Germany.

  4. Gas Content of Gladys McCall Reservoir Brine A Topical Report

    Office of Scientific and Technical Information (OSTI)

    Gas Content of Gladys McCall Reservoir Brine A Topical Report C-G- Hayden P.L- Randolph Institute of Gas Technology 3424 South State Street Chicago, Illinois 606 16 Submitted t o Eaton Operating Company 1980 Post Oak Boulevard, Suite 2000 Houston, Texas 77056 Under Sub-contract No. EOC 85-4 ( E O U I G T ) Under Prime Contract No. DE-AC07-851D12578 ([IOElEOC 1 IGT Project No. 65071 May 1987 Prepared by DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United

  5. Crystalline and Crystalline International Disposal Activities

    SciTech Connect (OSTI)

    Viswanathan, Hari S.; Chu, Shaoping; Reimus, Paul William; Makedonska, Nataliia; Hyman, Jeffrey De'Haven; Karra, Satish; Dittrich, Timothy M.

    2015-12-21

    This report presents the results of work conducted between September 2014 and July 2015 at Los Alamos National Laboratory in the crystalline disposal and crystalline international disposal work packages of the Used Fuel Disposition Campaign (UFDC) for DOE-NEs Fuel Cycle Research and Development program.

  6. Geochemical Impacts of Carbon Dioxide, Brine, Trace Metal and Organic Leakage into an Unconfined, Oxidizing Limestone Aquifer

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Bacon, Diana H.; Dai, Zhenxue; Zheng, Liange

    2014-12-31

    An important risk at CO2 storage sites is the potential for groundwater quality impacts. As part of a system to assess the potential for these impacts a geochemical scaling function has been developed, based on a detailed reactive transport model of CO2 and brine leakage into an unconfined, oxidizing carbonate aquifer. Stochastic simulations varying a number of geochemical parameters were used to generate a response surface predicting the volume of aquifer that would be impacted with respect to regulated contaminants. The brine was assumed to contain several trace metals and organic contaminants. Aquifer pH and TDS were influenced by CO2more » leakage, while trace metal concentrations were most influenced by the brine concentrations rather than adsorption or desorption on calcite. Organic plume sizes were found to be strongly influenced by biodegradation.« less

  7. AIR PASSIVATION OF METAL HYDRIDE BEDS FOR WASTE DISPOSAL

    SciTech Connect (OSTI)

    Klein, J; R. H. Hsu, R

    2007-07-02

    Metal hydride beds offer compact, safe storage of tritium. After metal hydride beds have reached the end of their useful life, the beds will replaced with new beds and the old beds prepared for disposal. One acceptance criteria for hydride bed waste disposal is that the material inside the bed not be pyrophoric. To determine the pyrophoric nature of spent metal hydride beds, controlled air ingress tests were performed. A simple gas handling manifold fitted with pressure transducers and a calibrated volume were used to introduce controlled quantities of air into a metal hydride bed and the bed temperature rise monitored for reactivity with the air. A desorbed, 4.4 kg titanium prototype hydride storage vessel (HSV) produced a 4.4 C internal temperature rise upon the first air exposure cycle and a 0.1 C temperature rise upon a second air exposure. A total of 346 scc air was consumed by the bed (0.08 scc per gram Ti). A desorbed, 9.66 kg LaNi{sub 4.25}Al{sub 0.75} prototype storage bed experienced larger temperature rises over successive cycles of air ingress and evacuation. The cycles were performed over a period of days with the bed effectively passivated after the 12th cycle. Nine to ten STP-L of air reacted with the bed producing both oxidized metal and water.

  8. Brine migration test report: Asse Salt Mine, Federal Republic of Germany: Technical report

    SciTech Connect (OSTI)

    Coyle, A.J.; Eckert, J.; Kalia, H.

    1987-01-01

    This report presents a summary of Brine Migration Tests which were undertaken at the Asse mine of the Federal Republic of Germany (FRG) under a bilateral US/FRG agreement. This experiment simulates a nuclear waste repository at the 800-m (2624-ft) level of the Asse salt mine in the Federal Republic of Germany. This report describes the Asse salt mine, the test equipment, and the pretest properties of the salt in the mine and in the vicinity of the test area. Also included are selected test data (for the first 28 months of operation) on the following: brine migration rates, thermomechaical behavior of the salt (including room closure, stress reading, and thermal profiles), borehole gas pressures, and borehole gas analyses. In addition to field data, laboratory analyses of pretest salt properties are included in this report. The operational phase of these experiments was completed on October 4, 1985, with the commencement of cooldown and the start of posttest activities. 7 refs., 68 figs., 48 tabs.

  9. Modeling Coupled THMC Processes and Brine Migration in Salt at High Temperatures

    SciTech Connect (OSTI)

    Rutqvist, Jonny; Blanco Martin, Laura; Mukhopadhyay, Sumit; Houseworth, Jim; Birkholzer, Jens

    2014-08-14

    In this report, we present FY2014 progress by Lawrence Berkeley National Laboratory (LBNL) related to modeling of coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. LBNLs work on the modeling of coupled THMC processes in salt was initiated in FY2012, focusing on exploring and demonstrating the capabilities of an existing LBNL modeling tool (TOUGH-FLAC) for simulating temperature-driven coupled flow and geomechanical processes in salt. This work includes development related to, and implementation of, essential capabilities, as well as testing the model against relevant information and published experimental data related to the fate and transport of water. we provide more details on the FY2014 work, first presenting updated tools and improvements made to the TOUGH-FLAC simulator, and the use of this updated tool in a new model simulation of long-term THM behavior within a generic repository in a salt formation. This is followed by the description of current benchmarking and validations efforts, including the TSDE experiment. We then present the current status in the development of constitutive relationships and the dual-continuum model for brine migration. We conclude with an outlook for FY2015, which will be much focused on model validation against field experiments and on the use of the model for the design studies related to a proposed heater experiment.

  10. Sensitivity study of CO2 storage capacity in brine aquifers withclosed boundaries: Dependence on hydrogeologic properties

    SciTech Connect (OSTI)

    Zhou, Q.; Birkholzer, J.; Rutqvist, J.; Tsang, C-F.

    2007-02-07

    In large-scale geologic storage projects, the injected volumes of CO{sub 2} will displace huge volumes of native brine. If the designated storage formation is a closed system, e.g., a geologic unit that is compartmentalized by (almost) impermeable sealing units and/or sealing faults, the native brine cannot (easily) escape from the target reservoir. Thus the amount of supercritical CO{sub 2} that can be stored in such a system depends ultimately on how much pore space can be made available for the added fluid owing to the compressibility of the pore structure and the fluids. To evaluate storage capacity in such closed systems, we have conducted a modeling study simulating CO{sub 2} injection into idealized deep saline aquifers that have no (or limited) interaction with overlying, underlying, and/or adjacent units. Our focus is to evaluate the storage capacity of closed systems as a function of various reservoir parameters, hydraulic properties, compressibilities, depth, boundaries, etc. Accounting for multi-phase flow effects including dissolution of CO{sub 2} in numerical simulations, the goal is to develop simple analytical expressions that provide estimates for storage capacity and pressure buildup in such closed systems.

  11. Fluid sampling and chemical modeling of geopressured brines containing methane. Final report, March 1980-February 1981

    SciTech Connect (OSTI)

    Dudak, B.; Galbraith, R.; Hansen, L.; Sverjensky, D.; Weres, O.

    1982-07-01

    The development of a flowthrough sampler capable of obtaining fluid samples from geopressured wells at temperatures up to 400/sup 0/F and pressures up to 20,000 psi is described. The sampler has been designed, fabricated from MP35N alloy, laboratory tested, and used to obtain fluid samples from a geothermal well at The Geysers, California. However, it has not yet been used in a geopressured well. The design features, test results, and operation of this device are described. Alternative sampler designs are also discussed. Another activity was to review the chemistry and geochemistry of geopressured brines and reservoirs, and to evaluate the utility of available computer codes for modeling the chemistry of geopressured brines. The thermodynamic data bases for such codes are usually the limiting factor in their application to geopressured systems, but it was concluded that existing codes can be updated with reasonable effort and can usefully explain and predict the chemical characteristics of geopressured systems, given suitable input data.

  12. Conceptual Design Plan SM-43 Replacement Project

    SciTech Connect (OSTI)

    University of California, Los Alamos National Laboratory, SCC Project Office

    2000-11-01

    The Los Alamos National Laboratory Conceptual Design Plan for the SM-43 Replacement Project outlines plans for replacing the SM-43 Administration Building. Topics include the reasons that replacement is considered a necessity; the roles of the various project sponsors; and descriptions of the proposed site and facilities. Also covered in this proposal is preliminary information on the project schedule, cost estimates, acquisition strategy, risk assessment, NEPA strategy, safety strategy, and safeguards and security. Spreadsheets provide further detail on space requirements, project schedules, and cost estimates.

  13. Replacement solvents for use in chemical synthesis

    DOE Patents [OSTI]

    Molnar, Linda K. (Philadelphia, PA); Hatton, T. Alan (Sudbury, MA); Buchwald, Stephen L. (Newton, MA)

    2001-05-15

    Replacement solvents for use in chemical synthesis include polymer-immobilized solvents having a flexible polymer backbone and a plurality of pendant groups attached onto the polymer backbone, the pendant groups comprising a flexible linking unit bound to the polymer backbone and to a terminal solvating moiety. The polymer-immobilized solvent may be dissolved in a benign medium. Replacement solvents for chemical reactions for which tetrahydrofuran or diethyl may be a solvent include substituted tetrahydrofurfuryl ethers and substituted tetrahydro-3-furan ethers. The replacement solvents may be readily recovered from the reaction train using conventional methods.

  14. Large Component Removal/Disposal

    SciTech Connect (OSTI)

    Wheeler, D. M.

    2002-02-27

    This paper describes the removal and disposal of the large components from Maine Yankee Atomic Power Plant. The large components discussed include the three steam generators, pressurizer, and reactor pressure vessel. Two separate Exemption Requests, which included radiological characterizations, shielding evaluations, structural evaluations and transportation plans, were prepared and issued to the DOT for approval to ship these components; the first was for the three steam generators and one pressurizer, the second was for the reactor pressure vessel. Both Exemption Requests were submitted to the DOT in November 1999. The DOT approved the Exemption Requests in May and July of 2000, respectively. The steam generators and pressurizer have been removed from Maine Yankee and shipped to the processing facility. They were removed from Maine Yankee's Containment Building, loaded onto specially designed skid assemblies, transported onto two separate barges, tied down to the barges, th en shipped 2750 miles to Memphis, Tennessee for processing. The Reactor Pressure Vessel Removal Project is currently under way and scheduled to be completed by Fall of 2002. The planning, preparation and removal of these large components has required extensive efforts in planning and implementation on the part of all parties involved.

  15. FACT SHEET: The Path Forward on Nuclear Waste Disposal | Department...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    FACT SHEET: The Path Forward on Nuclear Waste Disposal FACT SHEET: The Path Forward on Nuclear Waste Disposal FACT SHEET: The Path Forward on Nuclear Waste Disposal More Documents...

  16. FACT SHEET: The Path Forward on Nuclear Waste Disposal | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    FACT SHEET: The Path Forward on Nuclear Waste Disposal FACT SHEET: The Path Forward on Nuclear Waste Disposal PDF icon FACT SHEET: The Path Forward on Nuclear Waste Disposal More...

  17. Grand Coulee & Hungry Horse SCADA Replacement

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Gates Replacement This project is part of the Third Powerplant overhaul at Grand Coulee Dam. The full overhaul effort involves a mechanical overhaul of units G19 - G24. The...

  18. Marin County- Wood Stove Replacement Rebate Program

    Broader source: Energy.gov [DOE]

    Homes in the San Geronimo Valley (Forest Knolls, Lagunitas, San Geronimo, and Woodacre) can receive a rebate of $1,500 for the removal and replacement of non-certified wood burning appliances with...

  19. Replaces DOE F 5120.2

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    700.2 (09-93) Replaces DOE F 5120.2 (02-90) edition may be used 1. INITIATOR: NAME & ... Printed with soy ink on recycled paper Non Fillable INSTRUCTIONS FOR DOE F 5700.2, "WORK ...

  20. DOE - Office of Legacy Management -- Commercial (Burial) Disposal Site

    Office of Legacy Management (LM)

    Maxey Flats Disposal Site - KY 02 Commercial (Burial) Disposal Site Maxey Flats Disposal Site - KY 02 FUSRAP Considered Sites Site: Commercial (Burial) Disposal Site, Maxey Flats Disposal Site (KY.02) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Maxey Flats, Kentucky, Site Documents Related to Commercial (Burial) Disposal Site,

  1. New Facility Will Test Disposal Cell Cover Renovation | Department of

    Office of Environmental Management (EM)

    Energy Services » New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation New Facility Will Test Disposal Cell Cover Renovation PDF icon New Facility Will Test Disposal Cell Cover Renovation More Documents & Publications Design and Installation of a Disposal Cell Cover Field Test Sustainable Disposal Cell Covers: Legacy Management Practices, Improvements, and Long-Term Performance Long-Term Surveillance Operations and Maintenance

  2. Mexican Hat, Utah, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Mexican Hat, Utah, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site at Mexican Hat, Utah. This site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Mexican Hat, Utah, Disposal Cell Site Location and History The Mexican Hat disposal site is located on the Navajo Reservation in southeast Utah, 1.5 miles southwest of the town of Mexican Hat and 1 mile south of the San

  3. Generic disposal concepts and thermal load management for larger...

    Office of Scientific and Technical Information (OSTI)

    Generic disposal concepts and thermal load management for larger waste packages. Citation Details In-Document Search Title: Generic disposal concepts and thermal load management...

  4. Nevada Industrial Solid Waste Disposal Site Permit Application...

    Open Energy Info (EERE)

    Nevada Industrial Solid Waste Disposal Site Permit Application Jump to: navigation, search OpenEI Reference LibraryAdd to library Form: Nevada Industrial Solid Waste Disposal Site...

  5. A new design for a disposable and modifiable electrochemical...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: A new design for a disposable and modifiable electrochemical cell Citation Details In-Document Search Title: A new design for a disposable and modifiable...

  6. Deep Borehole Disposal of Spent Fuel. (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Deep Borehole Disposal of Spent Fuel. Citation Details In-Document Search Title: Deep Borehole Disposal of Spent Fuel. Abstract not provided. Authors: Brady, Patrick V. Publication...

  7. Deep Borehole Disposal Research: Geological Data Evaluation Alternativ...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Deep Borehole Disposal Research: Geological Data Evaluation Alternative Waste Forms and Borehole Seals Citation Details In-Document Search Title: Deep Borehole Disposal Research:...

  8. Used Fuel Disposition Campaign Disposal Research and Development...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear...

  9. LOW-LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP EXECUTION...

    Office of Environmental Management (EM)

    LOW-LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP EXECUTION PLAN Los Alamos National ... Safety and Security LFRG Low-Level Waste Disposal Facility Federal Review Group LLW ...

  10. Deep Borehole Disposal of Nuclear Waste: Science Needs. (Conference...

    Office of Scientific and Technical Information (OSTI)

    Deep Borehole Disposal of Nuclear Waste: Science Needs. Citation Details In-Document Search Title: Deep Borehole Disposal of Nuclear Waste: Science Needs. Abstract not provided. ...

  11. A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu...

  12. Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell...

    Office of Environmental Management (EM)

    Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of Long-Term Performance Plant Encroachment on the Burrell, Pennsylvania, Disposal Cell: Evaluation of...

  13. Erosion Control and Revegetation at DOE's Lowman Disposal Site...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and Revegetation at DOE's Lowman Disposal Site, Lowman, Idaho Erosion Control and ...

  14. Low-Level Waste Disposal Facility Federal Review Group (LFRG...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Program Management Compliance Low-Level Waste Disposal Facility Federal Review Group (LFRG) Low-Level Waste Disposal Facility Federal Review Group (LFRG) The Low-Level Waste...

  15. NDAA Section 3116 Waste Determinations with Related Disposal...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments NDAA Section 3116 Waste Determinations with Related Disposal Performance Assessments Section...

  16. Title 40 CFR 268 Land Disposal Restrictions | Open Energy Information

    Open Energy Info (EERE)

    disposal and defines those limited circumstances under which an otherwise prohibited waste may continue to be land disposed. Except as specifically provided otherwise in this...

  17. Deep Borehole Disposal of Nuclear Waste. (Conference) | SciTech...

    Office of Scientific and Technical Information (OSTI)

    Deep Borehole Disposal of Nuclear Waste. Citation Details In-Document Search Title: Deep Borehole Disposal of Nuclear Waste. Abstract not provided. Authors: Arnold, Bill Walter ;...

  18. Treated Effluent Disposal Facility - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Treated Effluent Disposal Facility About Us About Hanford Cleanup Hanford History Hanford Site Wide Programs Contact Us 100 Area 118-K-1 Burial Ground 200 Area 222-S Laboratory...

  19. Deep Borehole Disposal Research: Demonstration Site Selection...

    Office of Environmental Management (EM)

    The deep borehole disposal concept consists of drilling a borehole on the order of 5,000 m deep, emplacing waste canisters in the lower part of the borehole, and sealing the upper ...

  20. Supplement Analysis for Disposal of Polychlorinated Biphenyl...

    Office of Environmental Management (EM)

    Disposal of Polychlorinated Biphenyl-Commingled Transuranic Waste at the Waste Isolation Pilot Plant (DOEEIS-0026-SA02) 1.0 Purpose and Need for Action Transuranic (TRU) waste is...

  1. Z-Bed Recovery Water Disposal

    Office of Environmental Management (EM)

    Z-Bed Recovery Water Disposal Tritium Programs Engineering Louis Boone Josh Segura Savannah River Nuclear Solutions, LLC M-TRT-H-00087 Rev 0 Date: 4102014 Tritium Facilities...

  2. Operational Issues at the Environmental Restoration Disposal...

    Office of Environmental Management (EM)

    Hanford Operations Evaluating Operational Issues at the Environmental Restoration Disposal Facility at Hanford By Craig H. Benson, PhD, PE; William H. Albright, PhD; and David P. ...

  3. Special Analysis: Naval Reactor Waste Disposal Pad

    SciTech Connect (OSTI)

    Cook, J.R.

    2003-03-31

    This report presents the results of a special study of the Naval Reactor Waste Disposal Pad located within the boundary of the E-Area Low-Level Waste Facility at the Savannah River Site.

  4. Assessment of Preferred Depleted Uranium Disposal Forms

    SciTech Connect (OSTI)

    Croff, A.G.; Hightower, J.R.; Lee, D.W.; Michaels, G.E.; Ranek, N.L.; Trabalka, J.R.

    2000-06-01

    The Department of Energy (DOE) is in the process of converting about 700,000 metric tons (MT) of depleted uranium hexafluoride (DUF6) containing 475,000 MT of depleted uranium (DU) to a stable form more suitable for long-term storage or disposal. Potential conversion forms include the tetrafluoride (DUF4), oxide (DUO2 or DU3O8), or metal. If worthwhile beneficial uses cannot be found for the DU product form, it will be sent to an appropriate site for disposal. The DU products are considered to be low-level waste (LLW) under both DOE orders and Nuclear Regulatory Commission (NRC) regulations. The objective of this study was to assess the acceptability of the potential DU conversion products at potential LLW disposal sites to provide a basis for DOE decisions on the preferred DU product form and a path forward that will ensure reliable and efficient disposal.

  5. Parkersburg, West Virginia, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Parkersburg, West Virginia, Disposal Site This fact sheet provides information about the Parkersburg, West Virginia, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under the Nuclear Waste Policy Act Section 151. Location of the Parkersburg, West Virginia, Site Site Description and History The 15-acre Parkersburg site is located 8 miles southwest of Parkersburg, West Virginia, in Wood County, near the east bank of the Ohio River. The surrounding

  6. Brine-in-crude-oil emulsions at the Strategic Petroleum Reserve.

    SciTech Connect (OSTI)

    Nemer, Martin B.; Lord, David L.; MacDonald, Terry L.

    2013-10-01

    Metastable water-in-crude-oil emulsion formation could occur in a Strategic Petroleum Reserve (SPR) cavern if water were to flow into the crude-oil layer at a sufficient rate. Such a situation could arise during a drawdown from a cavern with a broken-hanging brine string. A high asphaltene content (> 1.5 wt %) of the crude oil provides the strongest predictor of whether a metastable water-in-crude-oil emulsion will form. However there are many crude oils with an asphaltene content > 1.5 wt % that don't form stable emulsions, but few with a low asphaltene content that do form stable emulsions. Most of the oils that form stable emulsions are %E2%80%9Csour%E2%80%9D by SPR standards indicating they contain total sulfur > 0.50 wt %.

  7. Reduced order models for prediction of groundwater quality impacts from CO₂ and brine leakage

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Zheng, Liange; Carroll, Susan; Bianchi, Marco; Mansoor, Kayyum; Sun, Yunwei; Birkholzer, Jens

    2014-12-31

    A careful assessment of the risk associated with geologic CO₂ storage is critical to the deployment of large-scale storage projects. A potential risk is the deterioration of groundwater quality caused by the leakage of CO₂ and brine leakage from deep subsurface reservoirs. In probabilistic risk assessment studies, numerical modeling is the primary tool employed to assess risk. However, the application of traditional numerical models to fully evaluate the impact of CO₂ leakage on groundwater can be computationally complex, demanding large processing times and resources, and involving large uncertainties. As an alternative, reduced order models (ROMs) can be used as highlymore » efficient surrogates for the complex process-based numerical models. In this study, we represent the complex hydrogeological and geochemical conditions in a heterogeneous aquifer and subsequent risk by developing and using two separate ROMs. The first ROM is derived from a model that accounts for the heterogeneous flow and transport conditions in the presence of complex leakage functions for CO₂ and brine. The second ROM is obtained from models that feature similar, but simplified flow and transport conditions, and allow for a more complex representation of all relevant geochemical reactions. To quantify possible impacts to groundwater aquifers, the basic risk metric is taken as the aquifer volume in which the water quality of the aquifer may be affected by an underlying CO₂ storage project. The integration of the two ROMs provides an estimate of the impacted aquifer volume taking into account uncertainties in flow, transport and chemical conditions. These two ROMs can be linked in a comprehensive system level model for quantitative risk assessment of the deep storage reservoir, wellbore leakage, and shallow aquifer impacts to assess the collective risk of CO₂ storage projects.« less

  8. Reduced order models for prediction of groundwater quality impacts from CO? and brine leakage

    SciTech Connect (OSTI)

    Zheng, Liange; Carroll, Susan; Bianchi, Marco; Mansoor, Kayyum; Sun, Yunwei; Birkholzer, Jens

    2014-12-31

    A careful assessment of the risk associated with geologic CO? storage is critical to the deployment of large-scale storage projects. A potential risk is the deterioration of groundwater quality caused by the leakage of CO? and brine leakage from deep subsurface reservoirs. In probabilistic risk assessment studies, numerical modeling is the primary tool employed to assess risk. However, the application of traditional numerical models to fully evaluate the impact of CO? leakage on groundwater can be computationally complex, demanding large processing times and resources, and involving large uncertainties. As an alternative, reduced order models (ROMs) can be used as highly efficient surrogates for the complex process-based numerical models. In this study, we represent the complex hydrogeological and geochemical conditions in a heterogeneous aquifer and subsequent risk by developing and using two separate ROMs. The first ROM is derived from a model that accounts for the heterogeneous flow and transport conditions in the presence of complex leakage functions for CO? and brine. The second ROM is obtained from models that feature similar, but simplified flow and transport conditions, and allow for a more complex representation of all relevant geochemical reactions. To quantify possible impacts to groundwater aquifers, the basic risk metric is taken as the aquifer volume in which the water quality of the aquifer may be affected by an underlying CO? storage project. The integration of the two ROMs provides an estimate of the impacted aquifer volume taking into account uncertainties in flow, transport and chemical conditions. These two ROMs can be linked in a comprehensive system level model for quantitative risk assessment of the deep storage reservoir, wellbore leakage, and shallow aquifer impacts to assess the collective risk of CO? storage projects.

  9. Nashville Gas treads carefully to replace pipe

    SciTech Connect (OSTI)

    1997-06-01

    The private gas utility, Nashville Gas, was responsible for replacing damaged or inadequate 2- and 4-inch steel gas lines beneath Music City, USA. The line replacements required either size for size or upsizing. The first choice was directional drilling, which was quickly determined to be unpractical because of rocky soil conditions. The second option was open trenching. Undoubtedly, trenching would mean having to contend with angry residents and tourists, since gas lines ran beneath yards, mature trees, sidewalks, roadways, and railways. In addition to the negative social factors, trenching would require additional funds for substantial landscaping and pavement replacement. It at all possible, a no-dig alternative was desired. Nashville Gas found Grundomat piercing tools which create a bore, then pushes pipe back through it. These same tools can simultaneously pull in pipe. These tools were customized for the Nashville project.

  10. REE Sorption Study on sieved -50 +100 mesh fraction of Media #1 in Brine #1 with Different Starting pH's at 70C

    DOE Data Explorer [Office of Scientific and Technical Information (OSTI)]

    Gary Garland

    2015-09-29

    This is a continuation of the REE sorption study for shaker bath tests on 2g media #1 in 150mL brine #1 with different starting pH's at 70C. In a previous submission we reported data for shaker bath tests for brine #1 with starting pH's of 3.5, 4.5 and 5.5. In this submission we these pH's compared to starting brine #1 pH's of 6, and 7.

  11. Acquisition, Use, and Disposal of Real Estate | Department of Energy

    Energy Savers [EERE]

    Acquisition, Use, and Disposal of Real Estate Acquisition, Use, and Disposal of Real Estate PDF icon Acquisition, Use, and Disposal of Real Estate More Documents & Publications Acquisition, Use, and Disposal of Real Estate OPAM Policy Acquisition Guides Chapter 17 - Special Contracting Methods

  12. Acquisition, Use, and Disposal of Real Estate | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Acquisition, Use, and Disposal of Real Estate Acquisition, Use, and Disposal of Real Estate PDF icon Acquisition, Use, and Disposal of Real Estate More Documents & Publications Acquisition, Use, and Disposal of Real Estate OPAM Policy Acquisition Guides Chapter 17 - Special Contracting Methods

  13. The feasibility of replacing or upgrading utility distribution transformers during routine maintenance

    SciTech Connect (OSTI)

    Barnes, P.R.; Van Dyke, J.W.; McConnell, B.W.; Cohn, S.M.; Purucker, S.L.

    1995-04-01

    It is estimated that electric utilities use about 40 million distribution transformers in supplying electricity to customers in the United States. Although utility distribution transformers collectively have a high average efficiency, they account for approximately 61 billion kWh of the 229 billion kWh of energy lost annually in the delivery of electricity. Distribution transformers are being replaced over time by new, more efficient, lower-loss units during routine utility maintenance of power distribution systems. Maintenance is typically not performed on units in service. However, units removed from service with appreciable remaining life are often refurbished and returned to stock. Distribution transformers may be removed from service for many reasons, including failure, over- or underloading, or line upgrades such as voltage changes or rerouting. When distribution transformers are removed from service, a decision must be made whether to dispose of the transformer and purchase a lower-loss replacement or to refurbish the transformer and return it to stock for future use. This report contains findings and recommendations on replacing utility distribution transformers during routine maintenance, which is required by section 124(c) of the Energy Policy Act of 1992. The objectives of the study are to evaluate the practicability, cost-effectiveness, and potential energy savings of replacing or upgrading existing transformers during routine utility maintenance and to develop recommendations on was to achieve the potential energy savings.

  14. Quenching and Partitioning Process Development to Replace Hot...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Quenching and Partitioning Process Development to Replace Hot Stamping of High-Strength Automotive Steel Quenching and Partitioning Process Development to Replace Hot Stamping of ...

  15. Molecular replacement and model-building using distant homology...

    Office of Scientific and Technical Information (OSTI)

    Molecular replacement and model-building using distant homology models as templates Citation Details In-Document Search Title: Molecular replacement and model-building using...

  16. Avoiding a Train Wreck: Replacing Old Coal Plants with Energy...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Avoiding a Train Wreck: Replacing Old Coal Plants with Energy Efficiency, August 2011 Avoiding a Train Wreck: Replacing Old Coal Plants with Energy Efficiency, August 2011 This ...

  17. WPN 00-5: Approval of Replacement Refrigerators and Electric...

    Energy Savers [EERE]

    WPN 00-5: Approval of Replacement Refrigerators and Electric Water Heaters as Allowable Weatherization Measures WPN 00-5: Approval of Replacement Refrigerators and Electric Water...

  18. Hazard Classification of the Remote Handled Low-Level Waste Disposal Facility

    SciTech Connect (OSTI)

    Boyd D. Christensen

    2012-05-01

    The Battelle Energy Alliance (BEA) at the Idaho National Laboratory (INL) is constructing a new facility to replace remote-handled low-level radioactive waste disposal capability for INL and Naval Reactors Facility operations. Current disposal capability at the Radioactive Waste Management Complex (RWMC) will continue until the facility is full or closed for remediation (estimated at approximately fiscal year 2015). Development of a new onsite disposal facility is the highest ranked alternative and will provide RH-LLW disposal capability and will ensure continuity of operations that generate RH-LLW for the foreseeable future. As a part of establishing a safety basis for facility operations, the facility will be categorized according to DOE-STD-1027-92. This classification is important in determining the scope of analyses performed in the safety basis and will also dictate operational requirements of the completed facility. This paper discusses the issues affecting hazard classification in this nuclear facility and impacts of the final hazard categorization.

  19. Groundwater impact assessment report for the 1325-N Liquid Waste Disposal Facility

    SciTech Connect (OSTI)

    Alexander, D.J.; Johnson, V.G.

    1993-09-01

    In 1943 the Hanford Site was chosen as a location for the Manhattan Project to produce plutonium for use in nuclear weapons. The 100-N Area at Hanford was used from 1963 to 1987 for a dual-purpose, plutonium production and steam generation reactor and related operational support facilities (Diediker and Hall 1987). In November 1989, the reactor was put into dry layup status. During operations, chemical and radioactive wastes were released into the area soil, air, and groundwater. The 1325-N LWDF was constructed in 1983 to replace the 1301-N Liquid Waste Disposal Facility (1301-N LWDF). The two facilities operated simultaneously from 1983 to 1985. The 1301-N LWDF was retired from use in 1985 and the 1325-N LWDF continued operation until April 1991, when active discharges to the facility ceased. Effluent discharge to the piping system has been controlled by administrative means. This report discusses ground water contamination resulting from the 1325-N Liquid Waste Disposal facility.

  20. Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory

    Office of Environmental Management (EM)

    INL, Idaho EM Project: Idaho CERCLA Disposal Facility ETR Report Date: December 2007 ETR-10 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Idaho CERCLA Disposal Facility (ICDF) At Idaho National Laboratory (INL) Why DOE-EM Did This Review The Idaho CERCLA Disposal Facility (ICDF) is a land disposal facility that is used to dispose of LLW and MLW generated from remedial activities at the Idaho National Laboratory (INL). Components of

  1. Changes in Vegetation at the Monticello, Utah, Disposal Site | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Energy Changes in Vegetation at the Monticello, Utah, Disposal Site Changes in Vegetation at the Monticello, Utah, Disposal Site Changes in Vegetation at the Monticello, Utah, Disposal Site Linda Sheader and Marilyn Kastens PDF icon Changes in Vegetation at the Monticello, Utah, Disposal Site More Documents & Publications Study of Factors Affecting Shrub Establishment on the Monticello, Utah, Disposal Cell Cover Monitoring the Performance of an Alternative Landfill Cover at the

  2. Title I Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    I Disposal Sites Annual Report Title I Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites (March 2015) More Documents & Publications Title II Disposal Sites Annual Report Guidance for Developing and Implementing Long-Term Surveillance Plans for UMTRCA

  3. Title II Disposal Sites Annual Report | Department of Energy

    Energy Savers [EERE]

    II Disposal Sites Annual Report Title II Disposal Sites Annual Report 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) PDF icon 2014 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites (November 2014) More Documents & Publications Title I Disposal Sites Annual Report Guidance for Developing and Implementing Long-Term Surveillance Plans for

  4. Idaho CERCLA Disposal Facility at Idaho National Laboratory | Department of

    Energy Savers [EERE]

    Energy Idaho CERCLA Disposal Facility at Idaho National Laboratory Idaho CERCLA Disposal Facility at Idaho National Laboratory Full Document and Summary Versions are available for download PDF icon Idaho CERCLA Disposal Facility at Idaho National Laboratory PDF icon Summary - Idaho CERCLA Disposal Facility (ICDF) at Idaho National Laboratory More Documents & Publications Environmental Management Waste Management Facility (EMWMF) at Oak Ridge Proposed On-Site Waste Disposal Facility

  5. Generic Disposal System Modeling, Fiscal Year 2011 Progress Report |

    Office of Environmental Management (EM)

    Department of Energy Disposal System Modeling, Fiscal Year 2011 Progress Report Generic Disposal System Modeling, Fiscal Year 2011 Progress Report The UFD Campaign is developing generic disposal system models (GDSM) of different disposal environments and waste form options. Currently, the GDSM team is investigating four main disposal environment options: mined repositories in three geologic media (salt, clay, and granite) and the deep borehole concept in crystalline rock (DOE 2010d). Further

  6. DOE - Office of Legacy Management -- Clive Disposal Cell - 036

    Office of Legacy Management (LM)

    Clive Disposal Cell - 036 FUSRAP Considered Sites Site: Clive Disposal Cell (036 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Clive Disposal Cell is located in Tooele County, Utah. All of the mill tailings and other residual radioactive materials from the South Salt Lake City mining site were disposed of in this dedicated disposal

  7. Measure Guideline: Window Repair, Rehabilitation, and Replacement

    SciTech Connect (OSTI)

    Baker, P.

    2012-12-01

    This measure guideline provides information and guidance on rehabilitating, retrofitting, and replacing existing window assemblies in residential construction. The intent is to provide information regarding means and methods to improve the energy and comfort performance of existing wood window assemblies in a way that takes into consideration component durability, in-service operation, and long term performance of the strategies.

  8. Electrochemical apparatus comprising modified disposable rectangular cuvette

    DOE Patents [OSTI]

    Dattelbaum, Andrew M; Gupta, Gautam; Morris, David E

    2013-09-10

    Electrochemical apparatus includes a disposable rectangular cuvette modified with at least one hole through a side and/or the bottom. Apparatus may include more than one cuvette, which in practice is a disposable rectangular glass or plastic cuvette modified by drilling the hole(s) through. The apparatus include two plates and some means of fastening one plate to the other. The apparatus may be interfaced with a fiber optic or microscope objective, and a spectrometer for spectroscopic studies. The apparatus are suitable for a variety of electrochemical experiments, including surface electrochemistry, bulk electrolysis, and flow cell experiments.

  9. Disposal of bead ion exchange resin wastes

    SciTech Connect (OSTI)

    Gay, R.L.; Granthan, L.F.

    1985-12-17

    Bead ion exchange resin wastes are disposed of by a process which involves spray-drying a bead ion exchange resin waste in order to remove substantially all of the water present in such waste, including the water on the surface of the ion exchange resin beads and the water inside the ion exchange resin beads. The resulting dried ion exchange resin beads can then be solidified in a suitable solid matrix-forming material, such as a polymer, which solidifies to contain the dried ion exchange resin beads in a solid monolith suitable for disposal by burial or other conventional means.

  10. Benefits and Costs of Brine Extraction for Increasing Injection Efficiency In geologic CO2 Sequestration

    SciTech Connect (OSTI)

    Davidson, Casie L.; Watson, David J.; Dooley, James J.; Dahowski, Robert T.

    2014-12-31

    Pressure increases attendant with CO2 injection into the subsurface drive many of the risk factors associated with commercial-scale CCS projects, impacting project costs and liabilities in a number of ways. The area of elevated pressure defines the area that must be characterized and monitored; pressure drives fluid flow out of the storage reservoir along higher-permeability pathways that might exist through the caprock into overlying aquifers or hydrocarbon reservoirs; and pressure drives geomechanical changes that could potentially impact subsurface infrastructure or the integrity of the storage system itself. Pressure also limits injectivity, which can increase capital costs associated with installing additional wells to meet a given target injection rate. The ability to mitigate pressure increases in storage reservoirs could have significant value to a CCS project, but these benefits are offset by the costs of the pressure mitigation technique itself. Of particular interest for CO2 storage operators is the lifetime cost of implementing brine extraction at a CCS project site, and the relative value of benefits derived from the extraction process. This is expected to vary from site to site and from one implementation scenario to the next. Indeed, quantifying benefits against costs could allow operators to optimize their return on project investment by calculating the most effective scenario for pressure mitigation. This work builds on research recently submitted for publication by the authors examining the costs and benefits of brine extraction across operational scenarios to evaluate the effects of fluid extraction on injection rate to assess the cost effectiveness of several options for reducing the number of injection wells required. Modeling suggests that extracting at 90% of the volumetric equivalent of injection rate resulted in a 1.8% improvement in rate over a non-extraction base case; a four-fold increase in extraction rate results in a 7.6% increase in injection rate over the no-extraction base case. However, the practical impacts on capital costs suggest that this strategy is fiscally ineffective when evaluated solely on this metric, with extraction reducing injection well needs by only one per 56 (1x case) or one per 13 (4x case).

  11. Benefits and Costs of Brine Extraction for Increasing Injection Efficiency In geologic CO2 Sequestration

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Davidson, Casie L.; Watson, David J.; Dooley, James J.; Dahowski, Robert T.

    2014-12-31

    Pressure increases attendant with CO2 injection into the subsurface drive many of the risk factors associated with commercial-scale CCS projects, impacting project costs and liabilities in a number of ways. The area of elevated pressure defines the area that must be characterized and monitored; pressure drives fluid flow out of the storage reservoir along higher-permeability pathways that might exist through the caprock into overlying aquifers or hydrocarbon reservoirs; and pressure drives geomechanical changes that could potentially impact subsurface infrastructure or the integrity of the storage system itself. Pressure also limits injectivity, which can increase capital costs associated with installing additionalmore » wells to meet a given target injection rate. The ability to mitigate pressure increases in storage reservoirs could have significant value to a CCS project, but these benefits are offset by the costs of the pressure mitigation technique itself. Of particular interest for CO2 storage operators is the lifetime cost of implementing brine extraction at a CCS project site, and the relative value of benefits derived from the extraction process. This is expected to vary from site to site and from one implementation scenario to the next. Indeed, quantifying benefits against costs could allow operators to optimize their return on project investment by calculating the most effective scenario for pressure mitigation. This work builds on research recently submitted for publication by the authors examining the costs and benefits of brine extraction across operational scenarios to evaluate the effects of fluid extraction on injection rate to assess the cost effectiveness of several options for reducing the number of injection wells required. Modeling suggests that extracting at 90% of the volumetric equivalent of injection rate resulted in a 1.8% improvement in rate over a non-extraction base case; a four-fold increase in extraction rate results in a 7.6% increase in injection rate over the no-extraction base case. However, the practical impacts on capital costs suggest that this strategy is fiscally ineffective when evaluated solely on this metric, with extraction reducing injection well needs by only one per 56 (1x case) or one per 13 (4x case).« less

  12. A Guide to AC Motor Repair and Replacement

    SciTech Connect (OSTI)

    2004-03-01

    This booklet provides helpful information for making informed repair or replace decisions for electric motors.

  13. Geochemical Impacts of Carbon Dioxide, Brine, Trace Metal and Organic Leakage into an Unconfined, Oxidizing Limestone Aquifer

    Office of Scientific and Technical Information (OSTI)

    3 (2014) 4684 - 4707 Energy Procedia GHGT-12 Geochemical impacts of carbon dioxide, brine, trace metal and organic leakage into an unconfined, oxidizing limestone aquifer Diana H. Bacon3'* *, Zhenxue Daib, Liange Zhengc "Pacific Northwest National Laboratory, Richland, Washington, USA bLos Alamos National Laboratory, Los Alamos, New Mexico, USA cLawrence Berkeley National Laboratory, Berkeley, California, USA Abstract An important risk at CO2 storage sites is the potential for groundwater

  14. INNOVATIVE DISPOSAL PRACTICES AT THE NEVADA TEST SITE TO MEET ITS LLW GENERATORS FUTURE DISPOSAL NEEDS

    National Nuclear Security Administration (NNSA)

    Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs E.F. Di Sanza, J.T. Carilli U.S. Department of Energy National Nuclear Security Administration Nevada Site Office P.O. Box 98518, Las Vegas, NV 89193-8518 USA ABSTRACT Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly

  15. Replaces EIA-459E OMB Control No.

    Energy Savers [EERE]

    5 (04-94) Replaces EIA-459E OMB Control No. 1910-0400 U.S. DEPARTMENT OF ENERGY FEDERAL ASSISTANCE MANAGEMENT SUMMARY REPORT Page of Public reporting burden for this collection of information is estimated to average 3.38 hours per response, including the time for reviewing instructions, search- ing existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comments regarding this burden estimate or any other aspect of this

  16. Land Disposal Restrictions (LDR) program overview

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    The Hazardous and Solid Waste Amendments (HSWA) to the Resource Conservation and Recovery Act (RCRA) enacted in 1984 required the Environmental Protection Agency (EPA) to evaluate all listed and characteristic hazardous wastes according to a strict schedule and to develop requirements by which disposal of these wastes would be protective of human health and the environment. The implementing regulations for accomplishing this statutory requirement are established within the Land Disposal Restrictions (LDR) program. The LDR regulations (40 CFR Part 268) impose significant requirements on waste management operations and environmental restoration activities at DOE sites. For hazardous wastes restricted by statute from land disposal, EPA is required to set levels or methods of treatment that substantially reduce the waste`s toxicity or the likelihood that the waste`s hazardous constituents will migrate. Upon the specified LDR effective dates, restricted wastes that do not meet treatment standards are prohibited from land disposal unless they qualify for certain variances or exemptions. This document provides an overview of the LDR Program.

  17. Low level tank waste disposal study

    SciTech Connect (OSTI)

    Mullally, J.A.

    1994-09-29

    Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

  18. Treatment and Disposal of Unanticipated 'Scavenger' Wastewater

    SciTech Connect (OSTI)

    Payne, W.L.

    2003-09-15

    The Savannah River Site often generates wastewater for disposal that is not included as a source to one of the site's wastewater treatment facilities that are permitted by the South Carolina Department of Health and Environmental Control. The techniques used by the SRS contract operator (Westinghouse Savannah River Company) to evaluate and treat this unanticipated 'scavenger' wastewater may benefit industries and municipalities who experience similar needs. Regulations require that scavenger wastewater be treated and not just diluted. Each of the pollutants that are present must meet effluent permit limitations and/or receiving stream water quality standards. if a scavenger wastewater is classified as 'hazardous' under the Resource Conservation and Recovery Act (RCRA) its disposal must comply with RCRA regulations. Westinghouse Savannah River Company obtained approval from SCDHEC to dispose of scavenger wastewater under specific conditions that are included within the SRS National Pollutant Discharge Elimination System permit. Scavenger wastewater is analyzed in a laboratory to determine its constituency. Pollutant values are entered into spreadsheets that calculate treatment plant removal capabilities and instream concentrations. Disposal rates are computed, ensuring compliance with regulatory requirements and protection of treatment system operating units. Appropriate records are maintained in the event of an audit.

  19. Solving the problems of infectious waste disposal

    SciTech Connect (OSTI)

    Hoffman, S.L.; Cabral, N.J. )

    1989-06-01

    Lawmakers are increasing pressures to ensure safe, appropriate disposal of infectious waste. This article discusses the problems, the regulatory climate, innovative approaches, and how to pay for them. The paper discusses the regulatory definition of infectious waste, federal and state regulations, and project finance.

  20. Grout treatment facility land disposal restriction management plan

    SciTech Connect (OSTI)

    Hendrickson, D.W.

    1991-04-04

    This document establishes management plans directed to result in the land disposal of grouted wastes at the Hanford Grout Facilities in compliance with Federal, State of Washington, and Department of Energy land disposal restrictions. 9 refs., 1 fig.

  1. Disposal in Crystalline Rocks: FY’15 Progress Report

    Broader source: Energy.gov [DOE]

    The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and...

  2. Low-Level Waste Disposal Facility Federal Review Group Manual

    Broader source: Energy.gov [DOE]

    This Revision 3 of the Low-Level Waste Disposal  Facility Federal Review Group (LFRG) Manual was prepared primarily to include review criteria for the review of transuranic (TRU) waste disposal...

  3. Strategy for the Management and Disposal of Used Nuclear Fuel...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level...

  4. Recommendation 212: Evaluate additional storage and disposal options |

    Office of Environmental Management (EM)

    Department of Energy 2: Evaluate additional storage and disposal options Recommendation 212: Evaluate additional storage and disposal options The ORSSAB encourages DOE to evaluate additional storage and disposal options for DOE legacy waste that could result from an expansion of the WIPP disposal mission. PDF icon Recommendation 212 PDF icon DOE response to recommendation 212 More Documents & Publications EM SSAB Recommendations and Letters - 2013-01 EM SSAB Recommendations and Letters -

  5. Recommendation 223: Recommendations on Additional Waste Disposal Capacity |

    Office of Environmental Management (EM)

    Department of Energy 3: Recommendations on Additional Waste Disposal Capacity Recommendation 223: Recommendations on Additional Waste Disposal Capacity ORSSAB's recommendations encourage DOE to continue planning for an additional on-site disposal facility for low-level waste and that a second facility be placed in an area already used for similar waste disposal. PDF icon Recommendation 223 PDF icon Response to Recommendation 223 More Documents & Publications ORSSAB Meeting - February

  6. Disposal Practices at the Savannah River Site | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Practices at the Savannah River Site Disposal Practices at the Savannah River Site Full Document and Summary Versions are available for download PDF icon Disposal Practices at the Savannah River Site PDF icon Summary - Disposal Practices at the Savannah River Site More Documents & Publications Compilation of ETR Summaries Disposal Practices at the Nevada Test Site 2008 Briefing: DOE EM ITR Landfill Assessment Project Lessons Learned

  7. Shirley Basin South, Wyoming, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Shirley Basin South, Wyoming, Disposal Site This fact sheet provides information about the Shirley Basin South, Wyoming, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the Shirley Basin South, Wyoming, Disposal Site Site Description and History The Shirley Basin South disposal site is located in rural Carbon County about 60 miles south of Casper and 35 miles

  8. Operational Issues at the Environmental Restoration Disposal Facility at

    Energy Savers [EERE]

    Hanford | Department of Energy Operational Issues at the Environmental Restoration Disposal Facility at Hanford Operational Issues at the Environmental Restoration Disposal Facility at Hanford Full Document and Summary Versions are available for download PDF icon Operational Issues at the Environmental Restoration Disposal Facility at Hanford PDF icon Summary - Operational Issues at the Environmental Restoration Disposal Facility (ERDF) at Hanford More Documents & Publications Idaho

  9. January 28, 2016 Webinar - Borehole Disposal of Spent Radioactive Sources |

    Energy Savers [EERE]

    Department of Energy January 28, 2016 Webinar - Borehole Disposal of Spent Radioactive Sources January 28, 2016 Webinar - Borehole Disposal of Spent Radioactive Sources Performance & RIsk Assessment (P&RA) Community of Practice (CoP) Webinar - January 28, 2016 - Borehole Disposal of Spent Radioactive Sources (Dr. Matt Kozak, INTERA). Webinar Recording PDF icon Agenda & Webinar Instructions - January 28, 2016 - P&RA CoP Webinar PDF icon Borehole Disposal of Spent Sources

  10. Enhancements to Generic Disposal System Modeling Capabilities Rev2 |

    Office of Environmental Management (EM)

    Department of Energy Enhancements to Generic Disposal System Modeling Capabilities Rev2 Enhancements to Generic Disposal System Modeling Capabilities Rev2 Contributions are described for the development of an enhanced generic disposal system modeling and analysis capability that takes advantage of high-performance computing (HPC) environments to simulate the important multi-physics phenomena and couplings associated with a geologic repository for UNF and HLW. The enhanced disposal system

  11. DOE - Office of Legacy Management -- Estes Gulch Disposal Cell - 010

    Office of Legacy Management (LM)

    Estes Gulch Disposal Cell - 010 FUSRAP Considered Sites Site: Estes Gulch Disposal Cell (010) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: All of the uranium mill tailings and other residual radioactive materials from the Old and New Rifle sites were disposed of in this dedicated disposal cell. The Department of Energy's Grand Junction

  12. DOE - Office of Legacy Management -- Burro Canyon Disposal Cell - 007

    Office of Legacy Management (LM)

    Burro Canyon Disposal Cell - 007 FUSRAP Considered Sites Site: Burro Canyon Disposal Cell (007) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: All of the uranium mill tailings and other residual radioactive materials from the Slick Rock/Old North Continent site and the Slick Rock/Union Carbide site were disposed of in this dedicated disposal

  13. DOE - Office of Legacy Management -- Cheney Disposal Cell - 008

    Office of Legacy Management (LM)

    Cheney Disposal Cell - 008 FUSRAP Considered Sites Site: Cheney Disposal Cell (008) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: All of the uranium mill tailings and other residual radioactive materials from the former Grand Junction uranium mill site were disposed of in this dedicated disposal cell. The cell is authorized to remain open

  14. Ambrosia Lake, New Mexico, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    Ambrosia Lake, New Mexico, Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal site located at Ambrosia Lake, New Mexico. The site is managed by the U.S. Department of Energy Office of Legacy Management. Location of the Ambrosia Lake Disposal Site Site Description and History The Ambrosia Lake disposal site is a former uranium-ore processing facility in McKinley County, approximately 25 miles north of Grants, New

  15. ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 4: PROPERTY DISPOSAL RECORDS (Revision 2) ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) These records pertain to the sales by agencies of real and personal property surplus to the needs of the Government. PDF icon ADMINISTRATIVE RECORDS SCHEDULE 4: PROPERTY DISPOSAL RECORDS (Revision 2) More Documents & Publications PROPERTY DISPOSAL RECORDS ADMINISTRATIVE RECORDS: PROCUREMENT, SUPPLY, AND GRANT RECORDS ADMINISTRATIVE RECORDS SCHEDULE 3:

  16. Deep Borehole Disposal Research: Demonstration Site Selection Guidelines,

    Office of Environmental Management (EM)

    Borehole Seals Design, and RD&D Needs | Department of Energy Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs The U.S. Department of Energy has been investigating deep borehole disposal as one alternative for the disposal of spent nuclear fuel and other radioactive waste forms, along with research and

  17. Experiments and modeling of variably permeable carbonate reservoir samples in contact with CO₂-acidified brines

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Smith, Megan M.; Hao, Yue; Mason, Harris E.; Carroll, Susan A.

    2014-12-31

    Reactive experiments were performed to expose sample cores from the Arbuckle carbonate reservoir to CO₂-acidified brine under reservoir temperature and pressure conditions. The samples consisted of dolomite with varying quantities of calcite and silica/chert. The timescales of monitored pressure decline across each sample in response to CO₂ exposure, as well as the amount of and nature of dissolution features, varied widely among these three experiments. For all samples cores, the experimentally measured initial permeability was at least one order of magnitude or more lower than the values estimated from downhole methods. Nondestructive X-ray computed tomography (XRCT) imaging revealed dissolution featuresmore » including “wormholes,” removal of fracture-filling crystals, and widening of pre-existing pore spaces. In the injection zone sample, multiple fractures may have contributed to the high initial permeability of this core and restricted the distribution of CO₂-induced mineral dissolution. In contrast, the pre-existing porosity of the baffle zone sample was much lower and less connected, leading to a lower initial permeability and contributing to the development of a single dissolution channel. While calcite may make up only a small percentage of the overall sample composition, its location and the effects of its dissolution have an outsized effect on permeability responses to CO₂ exposure. The XRCT data presented here are informative for building the model domain for numerical simulations of these experiments but require calibration by higher resolution means to confidently evaluate different porosity-permeability relationships.« less

  18. Application of Generic Disposal System Models

    SciTech Connect (OSTI)

    Mariner, Paul; Hammond, Glenn Edward; Sevougian, S. David; Stein, Emily

    2015-11-01

    This report describes specific GDSA activities in fiscal year 2015 (FY2015) toward the development of the enhanced disposal system modeling and analysis capability for geologic disposal of nuclear waste. The GDSA framework employs the PFLOTRAN thermal-hydrologic-chemical multi-physics code (Hammond et al., 2011) and the Dakota uncertainty sampling and propagation code (Adams et al., 2013). Each code is designed for massively-parallel processing in a high-performance computing (HPC) environment. Multi-physics representations in PFLOTRAN are used to simulate various coupled processes including heat flow, fluid flow, waste dissolution, radionuclide release, radionuclide decay and ingrowth, precipitation and dissolution of secondary phases, and radionuclide transport through the engineered barriers and natural geologic barriers to a well location in an overlying or underlying aquifer. Dakota is used to generate sets of representative realizations and to analyze parameter sensitivity.

  19. Environmental Restoration Disposal Facility - Hanford Site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Environmental Restoration Disposal Facility About Us About Hanford Cleanup Hanford History Hanford Site Wide Programs Contact Us 100 Area 118-K-1 Burial Ground 200 Area 222-S Laboratory 242-A Evaporator 300 Area 324 Building 325 Building 400 Area/Fast Flux Test Facility 618-10 and 618-11 Burial Grounds 700 Area B Plant B Reactor C Reactor Canister Storage Building and Interim Storage Area Canyon Facilities Cold Test Facility D and DR Reactors Effluent Treatment Facility Environmental Restoration

  20. Public attitudes toward garbage disposal. Special report

    SciTech Connect (OSTI)

    1990-05-03

    This document is meant to inform the reader about the results of the National Solid Waste Management Association`s opinion research which focused on public attitudes toward recycling, garbage disposal, waste-to-energy, and other waste management concerns. The general public and opinion leaders were asked a wide range of questions about managing our nation`s solid waste and their responses are listed in percentages.

  1. Evaluation Prompts ENERGY STAR Program to Replace Web Tool, Saving...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Prompts ENERGY STAR Program to Replace Web Tool, Saving 90 Percent of Annual Costs Evaluation Prompts ENERGY STAR Program to Replace Web Tool, Saving 90 Percent of Annual Costs ...

  2. California: SQAMD Replaces Drayage Trucks with CNG | Department...

    Energy Savers [EERE]

    California: SQAMD Replaces Drayage Trucks with CNG California: SQAMD Replaces Drayage Trucks with CNG November 6, 2013 - 12:00am Addthis In 2008, the South Coast Air Quality ...

  3. Summary - Disposal Practices at the Savannah River Site

    Office of Environmental Management (EM)

    ETR-19 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Disposal Practices at the Savannah River Site Why DOE-EM Did This Review Disposal operations have been ongoing at the Savannah River Site (SRS) for over 50 years. Active disposal in E-Area, is near the center of the site. Although a wide range of wastes are being managed at the SRS, only low level radioactive wastes (LLRW) are disposed of on site. Wastes are disposed of in

  4. LANL completes excavation of 1940s waste disposal site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Excavation of waste disposal site completed LANL completes excavation of 1940s waste disposal site The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. September 30, 2011 Material Disposal Area B Material Disposal Area B, the Lab's oldest waste disposal site, was excavated inside sturdy metal enclosures.There was no open air excavation at MDA-B. Contact Small Business Office (505) 667-4419 Email "Safety for the public, the environment, and

  5. L-Bar, New Mexico, Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    L-Bar, New Mexico, Disposal Site This fact sheet provides information about the L-Bar, New Mexico, Disposal Site. This site is managed by the U.S. Department of Energy Office of Legacy Management under Title II of the Uranium Mill Tailings Radiation Control Act of 1978. Location of the L-Bar, New Mexico, Disposal Site Site Description and History The L-Bar disposal site is in Cibola County approximately 47 miles west of Albuquerque, New Mexico, and 10 miles north of Laguna Pueblo. The disposal

  6. Text-Alternative Version: LED Replacements for Linear Fluorescent Lamps

    Broader source: Energy.gov [DOE]

    Below is the text-alternative version of the "LED Replacements for Linear Fluorescent Lamps" webcast, held June 20, 2011.

  7. Trim or Replace Impellers on Oversized Pumps | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Trim or Replace Impellers on Oversized Pumps Trim or Replace Impellers on Oversized Pumps This tip sheet discusses the reasoning behind trimming or replacing impellers on oversized pumps and describes how it works to improve pumping system efficiency. PUMPING SYSTEMS TIP SHEET #7 PDF icon Trim or Replace Impellers on Oversized Pumps (September 2006) More Documents & Publications Improving Pumping System Performance: A Sourcebook for Industry - Second Edition Match Pumps to System

  8. LED T8 Replacement Lamps | Department of Energy

    Energy Savers [EERE]

    LED T8 Replacement Lamps LED T8 Replacement Lamps This documents provides an overview of LED T8 replacement lamps and helps define a reasonable minimum performance level for the purpose of plant-wide improvement. PDF icon LED T8 Replacement Lamps (April 2010) More Documents & Publications Emerging Lighting Technology General Service LED Lamps Guiding Market Introduction of High-Performance SSL Products

  9. Modifications of Carbonate Fracture Hydrodynamic Properties by CO{sub 2}-Acidified Brine Flow

    SciTech Connect (OSTI)

    Deng, Hang; Ellis, Brian R.; Peters, Catherine A.; Fitts, Jeffrey P.; Crandall, Dustin; Bromhal, Grant S.

    2013-08-01

    Acidic reactive flow in fractures is relevant in subsurface activities such as CO{sub 2} geological storage and hydraulic fracturing. Understanding reaction-induced changes in fracture hydrodynamic properties is essential for predicting subsurface flows such as leakage, injectability, and fluid production. In this study, x-ray computed tomography scans of a fractured carbonate caprock were used to create three dimensional reconstructions of the fracture before and after reaction with CO{sub 2}-acidified brine (Ellis et al., 2011, Greenhouse Gases: Sci. Technol., 1:248-260). As expected, mechanical apertures were found to increase substantially, doubling and even tripling in some places. However, the surface geometry evolved in complex ways including comb-tooth structures created from preferential dissolution of calcite in transverse sedimentary bands, and the creation of degraded zones, i.e. porous calcite-depleted areas on reacted fracture surfaces. These geometric alterations resulted in increased fracture roughness, as measured by surface Z{sub 2} parameters and fractal dimensions D{sub f}. Computational fluid dynamics (CFD) simulations were conducted to quantify the changes in hydraulic aperture, fracture transmissivity and permeability. The results show that the effective hydraulic apertures are smaller than the mechanical apertures, and the changes in hydraulic apertures are nonlinear. Overestimation of flow rate by a factor of two or more would be introduced if fracture hydrodynamic properties were based on mechanical apertures, or if hydraulic aperture is assumed to change proportionally with mechanical aperture. The differences can be attributed, in part, to the increase in roughness after reaction, and is likely affected by contiguous transverse sedimentary features. Hydraulic apertures estimated by the 1D statistical model and 2D local cubic law (LCL) model are consistently larger than those calculated from the CFD simulations. In addition, a novel ternary segmentation method was devised to handle the degraded zones, allowing for a bounding analysis of the effects on hydraulic properties. We found that the degraded zones account for less than 15% of the fracture volume, but cover 70% to 80% of the fracture surface. When the degraded zones are treated as part of the fracture, the fracture transmissivities are two to four times larger because the fracture surfaces after reaction are not as rough as they would be if one considers the degraded zone as part of the rock. Therefore, while degraded zones created during geochemical reactions may not significantly increase mechanical aperture, this type of feature cannot be ignored and should be treated with prudence when predicting fracture hydrodynamic properties.

  10. GEOCHEMICAL INVESTIGATIONS OF CO?-BRINE-ROCK INTERACTIONS OF THE KNOX GROUP IN THE ILLINOIS BASIN

    SciTech Connect (OSTI)

    Yoksoulian, Lois; Berger, Peter; Freiburg, Jared; Butler, Shane; Leetaru, Hannes

    2014-09-30

    Increased output of greenhouse gases, particularly carbon dioxide (CO?), into the atmosphere from anthropogenic sources is of great concern. A potential technology to reduce CO? emissions is geologic carbon sequestration. This technology is currently being evaluated in the United States and throughout the world. The geology of the Illinois Basin exhibits outstanding potential as a carbon sequestration target, as demonstrated by the ongoing Illinois Basin Decatur Project that is using the Mt. Simon Sandstone reservoir and Eau Claire Shale seal system to store and contain 1 million tonnes of CO?. The Knox Group-Maquoketa Shale reservoir and seal system, located stratigraphically above the Mt. Simon Sandstone-Eau Claire Shale reservoir and seal system, has little economic value as a resource for fossil fuels or as a potable water source, making it ideal as a potential carbon sequestration target. In order for a reservoir-seal system to be effective, it must be able to contain the injected CO? without the potential for the release of harmful contaminants liberated by the reaction between CO?-formation fluids and reservoir and seal rocks. This study examines portions of the Knox Group (Potosi Dolomite, Gunter Sandstone, New Richmond Sandstone) and St. Peter Sandstone, and Maquoketa Shale from various locations around the Illinois Basin. A total of 14 rock and fluid samples were exposed to simulated sequestration conditions (91019860 kPa [13201430 psi] and 3242C [90 108F]) for varying amounts of time (6 hours to 4 months). Knox Group reservoir rocks exhibited dissolution of dolomite in the presence of CO? as indicated by petrographic examination, X-ray diffraction analysis, and fluid chemistry analysis. These reactions equilibrated rapidly, and geochemical modeling confirmed that these reactions reached equilibrium within the time frames of the experiments. Pre-reaction sample mineralogy and postreaction fluid geochemistry from this study suggests only limited potential for the release of United States Environmental Protection Agency regulated inorganic contaminants into potable water sources. Short-term core flood experiments further verify that the carbonate reactions occurring in Knox Group reservoir samples reach equilibrium rapidly. The core flood experiments also lend insight to pressure changes that may occur during CO? injection. The Maquoketa Shale experiments reveal that this rock is initially chemically reactive when in contact with CO? and brine. However, due to the conservative nature of silicate and clay reaction kinetics and the rapid equilibration of carbonate reactions that occur in the shale, these reactions would not present a significant risk to the competency of the shale as an effective seal rock.

  11. Microsoft Word - DisposalInSaltDifferentThanDisposalInWIPP.doc

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    DOE Issues Statement Concerning Debates Over Waste Disposal in Salt CARLSBAD, N.M., July 24, 2009 - The U.S. Department of Energy and its Carlsbad Field Office recognize and respect the long history that led to the current regulations that govern operations at the Waste Isolation Pilot Plant (WIPP). The WIPP is authorized to ship and dispose of transuranic (TRU) waste that was created by U.S. defense programs. TRU waste is a category of waste strictly defined by legislation and legal agreements.

  12. Review of Yucca Mountain Disposal Criticality Studies

    SciTech Connect (OSTI)

    Scaglione, John M [ORNL] [ORNL; Wagner, John C [ORNL] [ORNL

    2011-01-01

    The U.S. Department of Energy (DOE), Office of Civilian Radioactive Waste Management, submitted a license application for construction authorization of a deep geologic repository at Yucca Mountain, Nevada, in June of 2008. The license application is currently under review by the U.S. Nuclear Regulatory Commission. However,on March 3, 2010 the DOE filed a motion requesting withdrawal of the license application. With the withdrawal request and the development of the Blue Ribbon Commission to seek alternative strategies for disposing of spent fuel, the status of the proposed repository at Yucca Mountain is uncertain. What is certain is that spent nuclear fuel (SNF) will continue to be generated and some long-lived components of the SNF will eventually need a disposition path(s). Strategies for the back end of the fuel cycle will continue to be developed and need to include the insights from the experience gained during the development of the Yucca Mountain license application. Detailed studies were performed and considerable progress was made in many key areas in terms of increased understanding of relevant phenomena and issues regarding geologic disposal of SNF. This paper reviews selected technical studies performed in support of the disposal criticality analysis licensing basis and the use of burnup credit. Topics include assembly misload analysis, isotopic and criticality validation, commercial reactor critical analyses, loading curves, alternative waste package and criticality control studies, radial burnup data and effects, and implementation of a conservative application model in the criticality probabilistic evaluation as well as other information that is applicable to operations regarding spent fuel outside the reactor. This paper summarizes the work and significant accomplishments in these areas and provides a resource for future, related activities.

  13. Evaporite Caprock Integrity. An experimental study of reactive mineralogy and pore-scale heterogeneity during brine-CO2 exposure

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Smith, Megan M.; Sholokhova, Yelena; Hao, Yue; Carroll, Susan A.

    2012-07-25

    Characterization and geochemical data are presented from a core-flooding experiment on a sample from the Three Fingers evaporite unit forming the lower extent of caprock at the Weyburn-Midale reservoir, Canada. This low-permeability sample was characterized in detail using X-ray computed microtomography before and after exposure to CO 2-acidified brine, allowing mineral phase and voidspace distributions to be quantified in three dimensions. Solution chemistry indicated that CO 2-acidified brine preferentially dissolved dolomite until saturation was attained, while anhydrite remained unreactive. Dolomite dissolution contributed to increases in bulk permeability through the formation of a localized channel, guided by microfractures as well asmore » porosity and reactive phase distributions aligned with depositional bedding. An indirect effect of carbonate mineral reactivity with CO 2-acidified solution is voidspace generation through physical transport of anhydrite freed from the rock matrix following dissolution of dolomite. The development of high permeability fast pathways in this experiment highlights the role of carbonate content and potential fracture orientations in evaporite caprock formations considered for both geologic carbon sequestration and CO 2-enhanced oil recovery operations.« less

  14. Wetting behavior of selected crude oil/brine/rock systems. Topical report, March 1, 1995--March 31, 1996

    SciTech Connect (OSTI)

    Zhou, X.; Morrow, N.R.; Ma, S.

    1996-12-31

    Previous studies of crude oil/brine/rock (COBR) and related ensembles showed that wettability and its effect on oil recovery depend on numerous complex interactions. In the present work, the wettability of COBR ensembles prepared using Prudhoe Bay crude oil, a synthetic formation brine, and Berea Sandstone was varied by systematic change in initial water saturation and length of aging time at reservoir temperature (88 C). All displacement tests were run at ambient temperature. Various degrees of water wetness were achieved and quantified by a modified Amott wettability index to water, the relative pseudo work of imbibition, and a newly defined apparent advancing dynamic contact angle. Pairs of spontaneous imbibition (oil recovery by spontaneous imbibition of water) and waterflood (oil recovery vs. pore volumes of water injected) curves were measured for each of the induced wetting states. Several trends were observed. Imbibition rate, and hence water wetness, decreased with increase in aging time and with decrease in initial water saturation. Breakthrough recoveries and final oil recovery by waterflooding increased with decrease in water wetness. Correlations between water wetness and oil recovery by waterflooding and spontaneous imbibition are presented.

  15. REE Sorption Study for Media #1 and Media #2 in Brine #1 and #2 at different Liquid to Solid Ratio's at Ambient Temperature

    SciTech Connect (OSTI)

    Gary Garland

    2015-03-27

    This data set shows the different loading capacities of Media #1 and Media #2 in a high and low salt content brine matrix at different liquid to solid ratio's. These data sets are shaker bath tests on media #1 and media #2 in brine's #1 and #2 at 500mL-.5g(1000-1 ratio), 150mL-.75g(200-1 ratio), and 150mL-2.5g(60-1 ratio) at ambient temperature.

  16. REGULATIONS ON PHOTOVOLTAIC MODULE DISPOSAL AND RECYCLING.

    SciTech Connect (OSTI)

    FTHENAKIS,V.

    2001-01-29

    Environmental regulations can have a significant impact on product use, disposal, and recycling. This report summarizes the basic aspects of current federal, state and international regulations which apply to end-of-life photovoltaic (PV) modules and PV manufacturing scrap destined for disposal or recycling. It also discusses proposed regulations for electronics that may set the ground of what is to be expected in this area in the near future. In the US, several states have started programs to support the recycling of electronic equipment, and materials destined for recycling often are excepted from solid waste regulations during the collection, transfer, storage and processing stages. California regulations are described separately because they are different from those of most other states. International agreements on the movement of waste between different countries may pose barriers to cross-border shipments. Currently waste moves freely among country members of the Organization of Economic Cooperation and Development (OECD), and between the US and the four countries with which the US has bilateral agreements. However, it is expected, that the US will adopt the rules of the Basel Convention (an agreement which currently applies to 128 countries but not the US) and that the Convection's waste classification system will influence the current OECD waste-handling system. Some countries adopting the Basel Convention consider end-of-life electronics to be hazardous waste, whereas the OECD countries consider them to be non-hazardous. Also, waste management regulations potentially affecting electronics in Germany and Japan are mentioned in this report.

  17. Transuranic waste disposal in the United State

    SciTech Connect (OSTI)

    Thompson, J.D.

    1986-01-01

    The US is unique in having created a special class of radioactive waste disposal based on the concentration of transuranic (TRU) elements in the waste. Since 1970, the US has been placing newly generated TRU waste in retrievable storage. It is intended that these wastes will be placed in a permanent deep geologic repository, the Waste Isolation Pilot Plant (WIPP). The WIPP opening for a demonstration emplacement period is set for October 1988. Transuranic wastes derive from some of the manufacturing and research activities carried out by the US Department of Energy (DOE). The bulk of this waste is generated in plutonium parts fabrication activities. A variety of plutonium-contaminated materials ranging from glove boxes, high-efficiency particulate air filters, and machine tools, to chemical sludges derived from plutonium recovery streams are stored as TRU wastes. Other processes that generate TRU waste are plutonium production operations, preparation for and cleanup from fuel reprocessing, manufacturing of plutonium heat sources, and nuclear fuel cycle research activities. Extensive procedures will be used to examine and prepare waste before it is placed in the WIPP for disposal. After the WIPP opens, certified waste will be transported to it and emplaced in the repository.

  18. Alternatives to proposed replacement production reactors

    SciTech Connect (OSTI)

    Cullingford, H.S.

    1981-06-01

    To insure adequate supplies of plutonium and tritium for defense purposes, an independent evaluation was made by Los Alamos National Laboratory of the numerous alternatives to the proposed replacement production reactors (RPR). This effort concentrated on the defense fuel cycle operation and its technical implications in identifying the principal alternatives for the 1990s. The primary options were identified as (1) existing commercial reactors, (2) existing and planned government-owned facilities (not now used for defense materials production), and (3) other RPRs (not yet proposed) such as CANDU or CANDU-type heavy-water reactors (HWR) for both plutonium and tritium production. The evaluation considered features and differences of various options that could influence choice of RPR alternatives. Barring a change in the US approach to civilian and defense fuel cycles and precluding existing commercial reactors at government-owned sites, the most significant alternatives were identified as a CANDU-type HWR at Savannah River Plant (SRP) site or the Three Mile Island commercial reactor with reprocessing capability at Barnwell Nuclear Fuel Plant and at SRP.

  19. Defense High Level Waste Disposal Container System Description

    SciTech Connect (OSTI)

    2000-10-12

    The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials will be selected for the disposal container inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lids will be a barrier made of high-nickel alloy. The defense HLW disposal container interfaces with the emplacement drift environment and the internal waste by transferring heat from the canisters to the external environment and by protecting the canisters and their contents from damage/degradation by the external environment. The disposal container also interfaces with the canisters by limiting access of moderator and oxidizing agents to the waste. A loaded and sealed disposal container (waste package) interfaces with the Emplacement Drift System's emplacement drift waste package supports upon which the waste packages are placed. The disposal container interfaces with the Canister Transfer System, Waste Emplacement /Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement, and retrieval for the disposal container/waste package.

  20. FY 2006 ANNUAL REVIEW-SALTSTONE DISPOSAL FACILITY PERFORMANCE ASSESSMENT

    SciTech Connect (OSTI)

    Crapse, K; Benjamin Culbertson, B

    2007-03-15

    The Z-Area Saltstone Disposal Facility (SDF) consists of two disposal units, Vaults 1 and 4, described in the Performance Assessment (PA) (WSRC 1992). The FY06 PA Annual Review concludes that both vaults contain much lower levels of radionuclides (curies) than that allowed by the PA. The PA controls established to govern waste operations and monitor disposal facility performance are determined to be adequate.

  1. Section 3116 Waste Determinationfor Salt Disposal at the Savannah River

    Office of Environmental Management (EM)

    Site, signed by Secretary of Energy, Samuel W. Bodman | Department of Energy Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman PDF icon Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman More Documents &

  2. 2009 Performance Assessment for the Saltstone Disposal Facility |

    Office of Environmental Management (EM)

    Department of Energy Performance Assessment for the Saltstone Disposal Facility 2009 Performance Assessment for the Saltstone Disposal Facility This Performance Assessment (PA) for the Savannah River Site (SRS) was prepared to support the operation and eventual closure of the Saltstone Disposal Facility (SDF). This PA was prepared to demonstrate compliance with the pertinent requirements of the United States Department of Energy (DOE) Order 435.1, Change 1, Radioactive Waste Management,

  3. LANL completes excavation of 1940s waste disposal site

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    LANL completes excavation LANL completes excavation of 1940s waste disposal site The excavation removed about 43,000 cubic yards of contaminated debris and soil from the six-acre site. September 22, 2011 Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation Workers sample contents of LANL's Material Disposal Area B (MDA-B) before excavation. Contact Colleen Curran Communications Office (505) 664-0344 Email LOS ALAMOS, New Mexico, September 22, 2011-Los Alamos

  4. Microsoft Word - WIPP Marks A Decade of Safe Disposal

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Marks a Decade of Safe Disposal CARLSBAD, N.M., March 25, 2009 - The nation's first and only deep geologic repository for the disposal of defense-related transuranic (TRU) radioactive waste has safely operated for more than 10 years. The U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) began disposal operations March 26, 1999 and today serves as an international model for radioactive waste management. "What this project has accomplished is remarkable," said DOE

  5. Durango, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Durango, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing and disposal sites located at Durango, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Durango Processing and Disposal Sites Site Description and History The Durango processing site is a former uranium-ore processing facility located a quarter of a mile southwest of

  6. Naturita, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Naturita, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing and disposal sites located at Naturita, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Naturita, Colorado, Processing and Disposal Sites Site Description and History The Naturita processing site is a former uranium- and vanadium-ore processing facility in western

  7. Rifle, Colorado, Processing Sites and Disposal Site Fact Sheet

    Office of Legacy Management (LM)

    5 Fact Sheet UMTRCA Title I UMTRCA Title I Rifle, Colorado, Processing Sites and Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing sites and disposal site near Rifle, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Rife Processing Sites and Disposal Site Site Description and History Two former uranium and vanadium processing sites are located near the

  8. Slick Rock, Colorado, Processing Sites and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Slick Rock, Colorado, Processing Sites and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing sites and disposal site at Slick Rock, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Slick Rock, Colorado, Processing and Disposal Sites Site Descriptions and History The Slick Rock processing sites consist of two former uranium- and vanadium-ore processing

  9. Summary of Investigations on Technical Feasibility of Direct Disposal of

    Energy Savers [EERE]

    Dual-Purpose Canisters R1 | Department of Energy Summary of Investigations on Technical Feasibility of Direct Disposal of Dual-Purpose Canisters R1 Summary of Investigations on Technical Feasibility of Direct Disposal of Dual-Purpose Canisters R1 This study has evaluated the technical feasibility of direct disposal in a geologic repository, of commercial spent nuclear fuel (SNF) in dual-purpose canisters (DPCs) of existing designs. The investigation considered waste isolation safety,

  10. Repository Reference Disposal Concepts and Thermal Load Management Analysis

    Energy Savers [EERE]

    | Department of Energy Repository Reference Disposal Concepts and Thermal Load Management Analysis Repository Reference Disposal Concepts and Thermal Load Management Analysis A disposal concept consists of three parts: waste inventory (7 waste types examined), geologic setting (e.g., clay/shale, salt, crystalline, other sedimentary), and the engineering concept of operations (range of generic operational concepts examined). Two major categories for waste package emplacement modes are

  11. Status of UFD Campaign International Activities in Disposal Research |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Status of UFD Campaign International Activities in Disposal Research Status of UFD Campaign International Activities in Disposal Research Several international organizations have made significant progress in the characterization and performance evaluation of other disposal design options and host rock characteristics (clay/shale, granite), most of which were very different from those studied in the United States. The DOE recognizes that close international collaboration

  12. DOE - Office of Legacy Management -- Maryland Disposal Site - MD 05

    Office of Legacy Management (LM)

    Maryland Disposal Site - MD 05 FUSRAP Considered Sites Site: MARYLAND DISPOSAL SITE (MD.05 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Baltimore - Vicinity , Maryland MD.05-1 Evaluation Year: 1989 MD.05-1 Site Operations: Proposed disposal site - never developed. MD.05-1 Site Disposition: Eliminated Radioactive Materials Handled: None Indicated Primary Radioactive Materials Handled: None Indicated Radiological Survey(s): None

  13. Evaluation of Options for Permanent Geologic Disposal of Spent...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    This study provides a technical basis for informing policy decisions regarding strategies for the management and permanent disposal of spent nuclear fuel (SNF) and high-level ...

  14. Repository Reference Disposal Concepts and Thermal Load Management...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    These help inform development of waste management strategies and decision making. PDF icon RepositoryReferenceDisposalConceptsThermalLoadManagementAnalysis More Documents & ...

  15. Passive and active plasma deceleration for the compact disposal...

    Office of Scientific and Technical Information (OSTI)

    Passive and active plasma deceleration for the compact disposal of electron beams Citation Details In-Document Search This content will become publicly available on August 11, 2016...

  16. Low-Level Waste Disposal Facility Federal Review Group Manual

    Office of Environmental Management (EM)

    Low- LEVEL WASTE DISPOSAL FACILITY FEDERAL REVIEW GROUP MANUAL REVISION 3 JUNE 2008 (This page intentionally left blank) Low-Level JVllsfe Disposal Fllcili~l' Federal Review Group il1allUlli Revision 3, June 200S Concurrence The Low-Level Waste Disposal Facility Federal Review Group Manual, Revision 3, is approved for use as of the most recent date below. Date Chair, Low-Level Waste Disposal Federal Review Group Andrew WalJo, 1II Deputy Director, Otlice of Nuclear Safety, Quality Assurance, and

  17. Investigations of Dual-Purpose Canister Direct Disposal Feasibility...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    feasible, at least for some DPCs, and for some disposal concepts (geologic host media). ... zone (partial desiccation) in the host rock, limited mostly to a few meters with ...

  18. An Investigation for Disposal of Drill Cuttings into Unconsolidated...

    Office of Scientific and Technical Information (OSTI)

    Subject: 02 PETROLEUM; DRILLING FLUIDS; MINERAL WASTES; ROCK MECHANICS; SANDSTONES; CLAYS; DISPOSAL WELLS; ABANDONED WELLS; GROUND WATER; WATER POLLUTION CONTROL; WASTE MANAGEMENT ...

  19. Hazardous Waste Treatment, Storage and Disposal Facilities (TSDF...

    Open Energy Info (EERE)

    Treatment, Storage and Disposal Facilities (TSDF) Guidance Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - GuideHandbook:...

  20. Deep Borehole Disposal Research: Geological Data Evaluation Alternativ...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    much of the enhanced geothermal focus on stimulating fracture development (e.g., fracking) at depth is not directly relevant to deep borehole disposal. For deep borehole...

  1. RRC - Injection/Disposal Well Permitting, Testing, and Monitoring...

    Open Energy Info (EERE)

    InjectionDisposal Well Permitting, Testing, and Monitoring manual Jump to: navigation, search OpenEI Reference LibraryAdd to library PermittingRegulatory Guidance - Guide...

  2. An Investigation for Disposal of Drill Cuttings into Unconsolidated...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 02 PETROLEUM; DRILLING FLUIDS; MINERAL WASTES; ROCK MECHANICS; SANDSTONES; CLAYS; DISPOSAL WELLS; ABANDONED WELLS; ...

  3. WIPP Concludes Zone Recovery Activities for Panel 7 Disposal...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Activities for Panel 7 Disposal Pathway After months of catch-up rock bolting and contamination mitigation, zone recovery activities along the pathway to Panel 7 have been...

  4. Low-Level Waste Disposal Alternatives Analysis Report

    SciTech Connect (OSTI)

    Timothy Carlson; Kay Adler-Flitton; Roy Grant; Joan Connolly; Peggy Hinman; Charles Marcinkiewicz

    2006-09-01

    This report identifies and compares on-site and off-site disposal options for the disposal of contract-handled and remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Potential disposal options are screened for viability by waste type resulting in a short list of options for further consideration. The most crediable option are selected after systematic consideration of cost, schedule constraints, and risk. In order to holistically address the approach for low-level waste disposal, options are compiled into comprehensive disposal schemes, that is, alternative scenarios. Each alternative scenario addresses the disposal path for all low-level waste types over the period of interest. The alternative scenarios are compared and ranked using cost, risk and complexity to arrive at the recommended approach. Schedule alignment with disposal needs is addressed to ensure that all waste types are managed appropriately. The recommended alternative scenario for the disposal of low-level waste based on this analysis is to build a disposal facility at the Idaho National Laboratory Site.

  5. Depleted uranium storage and disposal trade study: Summary report

    SciTech Connect (OSTI)

    Hightower, J.R.; Trabalka, J.R.

    2000-02-01

    The objectives of this study were to: identify the most desirable forms for conversion of depleted uranium hexafluoride (DUF6) for extended storage, identify the most desirable forms for conversion of DUF6 for disposal, evaluate the comparative costs for extended storage or disposal of the various forms, review benefits of the proposed plasma conversion process, estimate simplified life-cycle costs (LCCs) for five scenarios that entail either disposal or beneficial reuse, and determine whether an overall optimal form for conversion of DUF6 can be selected given current uncertainty about the endpoints (specific disposal site/technology or reuse options).

  6. Summary - Disposal Practices at the Nevada Test Site

    Energy Savers [EERE]

    Area 5 LLRW & MLLW Disposal ETR Report Date: July 2008 ETR-14 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of Disposal Practices at the Nevada Test Site Why DOE-EM Did This Review Radioactively contaminated materials from the Nevada Test Site (NTS), other DOE facilities and other federal agencies are disposed of at NTS at two low-level radioactive waste (LLRW) management sites: Areas 3 and 5. Disposal operations at Area 3 have been

  7. Sustainable LED Fluorescent Light Replacement Technology

    SciTech Connect (OSTI)

    2011-06-30

    Ilumisys and the National Center for Manufacturing Sciences (NCMS) partnered on a three-year project awarded by the United States (U.S.) Department of Energy (DOE), to quantify the impacts of LED lamps, incandescent lamps and fluorescent benchmark lamps over a product lifecycle – i.e. to develop a sustainable design and manufacturing strategy that addresses product manufacturing, use, recycling and disposal scenarios for LED-based lighting. Based on the knowledge gained from extensive product tear-down studies of fluorescent and screw-in lighting products, lifecycle assessment tools, and accelerated lifecycle testing protocols, an interactive Sustainable LED Design Guide has been developed to aid architectural and lighting designers and engineers in making design decisions that consider three important environmental impacts (greenhouse gas emissions, energy use and mercury emission) across all phases of the life of an LED lighting product. Critical information developed for the lifecycle analysis and product feature comparisons is the useful life of the lighting product as well as its performance. The Design Guide is available at www.ncms.org, and was developed based on operational and durability testing of a variety of lighting products including power consumption, light output, and useful life of a lamp in order to allow a more realistic comparison of lamp designs. This report describes the main project tasks, results and innovative features of the lifecycle assessment (LCA)-based design tools, and the key considerations driving the sustainable design of LED lighting systems. The Design Guide incorporates the following three novel features for efficiently evaluating LED lighting features in value-chains: • Bill-of-Materials (BOM) Builder – Designers may import process data for each component and supply functional data for the product, including power, consumption, lumen output and expected useful life. • Environmental Impact Review – Designs are comparable across lifecycle phases, subsystems, and environmental impact category, and can be normalized to a userdefined functional unit. • Drill-down Review – These provide an indepth look at individual lamp designs with the ability to review across subsystem or lifecycle phase.

  8. Virent is Replacing Crude Oil | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Virent is Replacing Crude Oil Virent is Replacing Crude Oil Breakout Session 2A-Conversion Technologies II: Bio-Oils, Sugar Intermediates, Precursors, Distributed Models, and Refinery Co-Processing Virent is Replacing Crude Oil Randy Cortright, Founder & Chief Technology Officer, Virent PDF icon cortright_biomass_2014.pdf More Documents & Publications Bioproducts and Biofuels - Growing Together! NABC Webinar Navigating Roadblocks on the Path to Advanced Biofuels Deployment

  9. Applications of molecular replacement to G protein-coupled receptors

    Office of Scientific and Technical Information (OSTI)

    (Journal Article) | SciTech Connect Applications of molecular replacement to G protein-coupled receptors Citation Details In-Document Search Title: Applications of molecular replacement to G protein-coupled receptors The use of molecular replacement in solving the structures of G protein-coupled receptors is discussed, with specific examples being described in detail. G protein-coupled receptors (GPCRs) are a large class of integral membrane proteins involved in regulating virtually every

  10. Replacement-1 Wholesale Power Rate Schedule | Department of Energy

    Energy Savers [EERE]

    Replacement-1 Wholesale Power Rate Schedule Replacement-1 Wholesale Power Rate Schedule Area: Replacement Energy System: Georgia-Alabama-South Carolina This rate schedule shall be available to public bodies and cooperatives (any one of whom is hereinafter called the Customer) in Georgia, Alabama, Mississippi, Florida, South Carolina, or North Carolina to whom power is provided pursuant to contracts between the Government and the Customer. This rate schedule shall be applicable to the sale at

  11. LED Replacements for Linear Fluorescent Lamps Webcast | Department of

    Energy Savers [EERE]

    Energy Replacements for Linear Fluorescent Lamps Webcast LED Replacements for Linear Fluorescent Lamps Webcast In this June 20, 2011 webcast on LED products marketed as replacements for linear fluorescent lamps, Jason Tuenge of the Pacific Northwest National Laboratory (PNNL) discussed current Lighting Facts-listed products as well as products evaluated in the latest CALiPER reports. Eric Richman, also of PNNL, reported on a recently completed GATEWAY demonstration project, in which LED and

  12. Building America Technology Solutions for New and Existing Homes: Replacing

    Energy Savers [EERE]

    Resistance Heating with Mini-Split Heat Pumps | Department of Energy Replacing Resistance Heating with Mini-Split Heat Pumps Building America Technology Solutions for New and Existing Homes: Replacing Resistance Heating with Mini-Split Heat Pumps In this project, the Advanced Residential Integrated Solutions team investigated the suitability of mini-split heat pumps for multifamily retrofits. PDF icon Replacing Resistance Heating with Mini-Split Heat Pumps More Documents & Publications

  13. Arizona: Solar Panels Replace Inefficient Fossil Fuel-Powered Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Systems | Department of Energy Arizona: Solar Panels Replace Inefficient Fossil Fuel-Powered Energy Systems Arizona: Solar Panels Replace Inefficient Fossil Fuel-Powered Energy Systems May 1, 2014 - 9:33am Addthis The Agricultural Renewable Energy Conversion Incentive Program, funded in part by DOE's State Energy Program (SEP), assists farmers and ranchers to convert fossil-fueled agricultural production systems to renewable energy power. The program will install solar panels to replace

  14. Replace Fossil Fuels, Final Technical Report Roberts, William...

    Office of Scientific and Technical Information (OSTI)

    Crude Glycerol as Cost-Effective Fuel for Combined Heat and Power to Replace Fossil Fuels, Final Technical Report Roberts, William L 09 BIOMASS FUELS biofuels, glycerin, glycerol,...

  15. EERE Success Story-Arizona: Solar Panels Replace Inefficient...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Arizona: Solar Panels Replace Inefficient Fossil Fuel-Powered Energy Systems EERE Success Story-Arizona: ... fossil-fueled agricultural production systems to renewable energy power. ...

  16. Exploring the speed and performance of molecular replacement...

    Office of Scientific and Technical Information (OSTI)

    ab initio protein models Citation Details In-Document Search Title: Exploring the speed and performance of molecular replacement with AMPLE using QUARK ab initio protein models Two ...

  17. Quenching and Partitioning Process Development to Replace Hot...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ADVANCED MANUFACTURING OFFICE Quenching and Partitioning Process Development to Replace Hot Stamping of High-Strength Automotive Steel Novel Steel Heat Treatment Process to Produce ...

  18. Replace Pressure-Reducing Valves with Backpressure Turbogenerators

    Broader source: Energy.gov [DOE]

    This tip sheet on replacing pressure-reducing valves provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  19. Building America Case Study: Boiler Control Replacement for Hydronical...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... of the control parameters and provides real-time access to apartment temperature data. ... Boiler Control Replacement and Monitoring Study, at: buildingamerica.gov Image credit: All ...

  20. Jordan Malheur Resource Area Jonesboro Diversion Dam Replacement...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    The proposed replacement would help improve fish passage and facilitate continued ... the existing diversion dam to help improve fish passage and facilitate continued ...

  1. EA-1994: Malheur Resource Area Jonesboro Diversion Dam Replacement...

    Broader source: Energy.gov (indexed) [DOE]

    Burns Paiute Tribe for replacement of an existing diversion dam and installation of a fish passage structure. BPA's proposed action was to fund the project. PUBLIC COMMENT...

  2. Monitoring Galvanic Replacement of Ag Nanoparticles by Pd using...

    Office of Scientific and Technical Information (OSTI)

    Conference: Monitoring Galvanic Replacement of Ag Nanoparticles by Pd using Low Dose In Situ Liquid STEM. Citation Details In-Document Search Title: Monitoring Galvanic ...

  3. Magnetic Nanoparticle Capilary Flow as a Replacement for Lateral...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Magnetic Nanoparticle Capilary Flow as a Replacement for Lateral Flow Chromatography Colorado School of Mines Contact CSM About This Technology Technology Marketing SummaryThis...

  4. "Green" Replacement for Industrial Applications of Polar Organic...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Find More Like This Return to Search "Green" Replacement for Industrial Applications ... The lower volatility can lead to more energy intensive separation of the solvent; however, ...

  5. DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

    SciTech Connect (OSTI)

    E. F. Loros

    2000-06-30

    The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai

  6. Transuranic waste disposal in the United States

    SciTech Connect (OSTI)

    Hoffman, R.B.

    1986-01-01

    The United States is unique in having created a special class of radioactive waste disposal based on the concentration of transuranic elements in the waste. Since 1970, the US has been placing newly generated transuranic waste in retrievable storage. It is intended that these wastes will be placed in a permanent deep geologic repository, the Waste Isolation Pilot Plant (WIPP). WIPP opening for a demonstration emplacement period is set for October, 1988. Transuranic wastes derive from some of the manufacturing and research activities carried out by DOE. The bulk of this waste is generated in plutonium parts fabrication activities. A variety of plutonium contaminated materials ranging from glove boxes, HEPA filters, and machine tools, to chemical sludges derived from plutonium recovery streams are stored as TRU wastes. Other processes that generate TRU waste are plutonium production operations, preparation for and cleanup from fuel reprocessing, manufacturing of plutonium heat sources, and nuclear fuel cycle research activities.

  7. Disposable sludge dewatering container and method

    DOE Patents [OSTI]

    Cole, Clifford M. (1905 Cottonwood Dr., Aiken, SC 29803)

    1993-01-01

    A device and method for preparing sludge for disposal comprising a box with a thin layer of gravel on the bottom and a thin layer of sand on the gravel layer, an array of perforated piping deployed throughout the gravel layer, and a sump in the gravel layer below the perforated piping array. Standpipes connect the array and sump to an external ion exchanger/fine particulate filter and a pump. Sludge is deposited on the sand layer and dewatered using a pump connected to the piping array, topping up with more sludge as the aqueous component of the sludge is extracted. When the box is full and the free standing water content of the sludge is acceptable, the standpipes are cut and sealed and the lid secured to the box.

  8. Method for disposing of hazardous wastes

    DOE Patents [OSTI]

    Burton, Frederick G. (West Richland, WA); Cataldo, Dominic A. (Kennewick, WA); Cline, John F. (Prosser, WA); Skiens, W. Eugene (Richland, WA)

    1995-01-01

    A method and system for long-term control of root growth without killing the plants bearing those roots involves incorporating a 2,6-dinitroaniline in a polymer and disposing the polymer in an area in which root control is desired. This results in controlled release of the substituted aniline herbicide over a period of many years. Herbicides of this class have the property of preventing root elongation without translocating into other parts of the plant. The herbicide may be encapsulated in the polymer or mixed with it. The polymer-herbicide mixture may be formed into pellets, sheets, pipe gaskets, pipes for carrying water, or various other forms. The invention may be applied to other protection of buried hazardous wastes, protection of underground pipes, prevention of root intrusion beneath slabs, the dwarfing of trees or shrubs and other applications. The preferred herbicide is 4-difluoromethyl-N,N-dipropyl- 2,6-dinitro-aniline, commonly known as trifluralin.

  9. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    8947.1 09/13 On-Site Disposal Facility Inspection Report September 2013 6319-D6242 8947.2 09/13 East Face Cell 1 West Face Cell 1 6319D-6208 6319D-6231 8947.3 09/13 North Face Cell 1 North Drainage (looking west) 6319D-6206 6319D-6205 8947.4 09/13 East Face Cell 2 West Face Cell 2 6319D-6230 6319D-6209 8947.5 09/13 East Face Cell 3 West Face Cell 3 6319D-6229 6319D-6210 8947.6 09/13 East Face Cell 4 West Face Cell 4 6319D-6227 6319D-62111 8947.7 09/13 East Face Cell 5 West Face Cell 5 6319D-6226

  10. On-Site Disposal Facility Inspection Report

    Office of Legacy Management (LM)

    72.1 06/14 On-Site Disposal Facility Inspection Report June 2014 6319-D6320 8972.2 06/14 East Face Cell 1 West Face Cell 1 6319D-6322 6319D-6346 8972.3 06/14 North Face Cell 1 North Drainage (looking west) 6319D-6321 6319D-6320 8972.4 06/14 East Face Cell 2 West Face Cell 2 6319D-6345 6319D-6324 8972.5 06/14 East Face Cell 3 West Face Cell 3 6319D-6344 6319D-6325 8972.6 06/14 East Face Cell 4 West Face Cell 4 6319D-6342 6319D-63261 8972.7 06/14 East Face Cell 5 West Face Cell 5 6319D-6341

  11. Consolidation and disposal of PWR fuel inserts

    SciTech Connect (OSTI)

    Wakeman, B.H. (Virginia Electric and Power Co., Glen Allen, VA (United States))

    1992-08-01

    Design and licensing of the Surry Power Station Independent Spent Fuel Storage Installation was initiated in 1982 by Virginia Power as part of a comprehensive strategy to increase spent fuel storage capacity at the Station. Designed to use large, metal dry storage casks, the Surry Installation will accommodate 84 such casks with a total storage capacity of 811 MTU of spent pressurized water reactor fuel assemblies. Virginia Power provided three storage casks for testing at the Idaho National Engineerinq Laboratory's Test Area North and the testing results have been published by the Electric Power Research Institute. Sixty-nine spent fuel assemblies were transported in truck casks from the Surry Power Station to Test Area North for testing in the three casks. Because of restrictions imposed by the cask testing equipment at Test Area North, the irradiated insert components stored in these fuel assemblies at Surry were removed prior to transport of the fuel assemblies. Retaining these insert components proved to be a problem because of a shortage of spent fuel assemblies in the spent fuel storage pool that did not already contain insert components. In 1987 Virginia Power contracted with Chem-Nuclear Systems, Inc. to process and dispose of 136 irradiated insert components consisting of 125 burnable poison rod assemblies, 10 thimble plugging devices and 1 part-length rod cluster control assembly. This work was completed in August and September 1987, culminating in the disposal at the Barnwell, SC low-level radioactive waste facility of two CNS 3-55 liners containing the consolidated insert components.

  12. REE Sorption Study of Sieved -50 +100 mesh Media #1 in Brine #1 with Different Starting pH's at 70C

    SciTech Connect (OSTI)

    Gary Garland

    2015-07-21

    This dataset described shaker table experiments ran with sieved -50 +100 mesh media #1 in brine #1 that have 2ppm each of the 7 REE metals at different starting pH's of 3.5, 4.5, and 5.5. The experimental conditions are 2g media to 150mL of REE solution, at 70C.

  13. Trim or Replace Impellers on Oversized Pumps

    SciTech Connect (OSTI)

    Not Available

    2006-09-01

    One in a series of tip sheets to help manufacturers optimize their industrial pumping systems. As a result of conservative engineering practices, pumps are often substantially larger than they need to be for an industrial plant's process requirements. Centrifugal pumps can often be oversized because of ''rounding up'', trying to accommodate gradual increases in pipe surface roughness and flow resistance over time, or anticipating future plant capacity expansions. In addition, the plant's pumping requirements might not have been clearly defined during the design phase. Because of this conservative approach, pumps can have operating points completely different from their design points. The pump head is often less than expected, while the flow rate is greater. This can cause cavitation and waste energy as the flow rate typically must be regulated with bypass or throttle control. Oversized and throttled pumps that produce excess pressure are excellent candidates for impeller replacement or ''trimming'', to save energy and reduce costs. Trimming involves machining the impeller to reduce its diameter. Trimming should be limited to about 75% of a pump's maximum impeller diameter, because excessive trimming can result in a mismatched impeller and casing. As the impeller diameter decreases, added clearance between the impeller and the fixed pump casing increases internal flow recirculation, causes head loss, and lowers pumping efficiency. For manufacturing standardization purposes, pump casings and shafts are designed to accommodate impellers in a range of sizes. Many pump manufacturers provide pump performance curves that indicate how various models will perform with different impeller diameters or trims. The impeller should not be trimmed any smaller than the minimum diameter shown on the curve. Net positive suction head requirements (NPSHR) usually decrease at lower flow rates and can increase at the higher end of the pump head curve. The NPSHR at a given flow rate will normally be greater with a smaller impeller, but engineers should consult with the pump manufacturer to determine variations in NPSHR before trimming the impeller. Manufacturers can often provide trim correction charts based on historical test data.

  14. Rare-earth elements in hot brines (165 to 190 degree C) from the Salton Sea geothermal field

    SciTech Connect (OSTI)

    Lepel, E.A.; Laul, J.C.; Smith, M.R.

    1988-01-01

    Rare-earth element (REE) concentrations are important indicators for revealing various chemical fractionation processes (water/rock interactions) and source region geochemistry. Since the REE patterns are characteristic of geologic materials (basalt, granite, shale, sediments, etc.) and minerals (K-feldspar, calcite, illite, epidote, etc.), their study in geothermal fluids may serve as a geothermometer. The REE study may also enable us to address the issue of groundwater mixing. In addition, the behavior of the REE can serve as analogs of the actinides in radioactive waste (e.g., neodymium is an analog of americium and curium). In this paper, the authors port the REE data for a Salton Sea Geothermal Field (SSGF) brine (two aliquots: port 4 at 165{degree}C and port 5 at 190{degree}C) and six associated core samples.

  15. Reactive transport modeling to study changes in water chemistry induced by CO2 injection at the Frio-I brine pilot

    SciTech Connect (OSTI)

    Kharaka, Y.K; Doughty, C.; Freifeld, B.M.; Daley, T.M.; Xu, T.

    2009-11-01

    To demonstrate the potential for geologic storage of CO{sub 2} in saline aquifers, the Frio-I Brine Pilot was conducted, during which 1600 tons of CO{sub 2} were injected into a high-permeability sandstone and the resulting subsurface plume of CO{sub 2} was monitored using a variety of hydrogeological, geophysical, and geochemical techniques. Fluid samples were obtained before CO{sub 2} injection for baseline geochemical characterization, during the CO{sub 2} injection to track its breakthrough at a nearby observation well, and after injection to investigate changes in fluid composition and potential leakage into an overlying zone. Following CO{sub 2} breakthrough at the observation well, brine samples showed sharp drops in pH, pronounced increases in HCO{sub 3}{sup -} and aqueous Fe, and significant shifts in the isotopic compositions of H{sub 2}O and dissolved inorganic carbon. Based on a calibrated 1-D radial flow model, reactive transport modeling was performed for the Frio-I Brine Pilot. A simple kinetic model of Fe release from the solid to aqueous phase was developed, which can reproduce the observed increases in aqueous Fe concentration. Brine samples collected after half a year had lower Fe concentrations due to carbonate precipitation, and this trend can be also captured by our modeling. The paper provides a method for estimating potential mobile Fe inventory, and its bounding concentration in the storage formation from limited observation data. Long-term simulations show that the CO{sub 2} plume gradually spreads outward due to capillary forces, and the gas saturation gradually decreases due to its dissolution and precipitation of carbonates. The gas phase is predicted to disappear after 500 years. Elevated aqueous CO{sub 2} concentrations remain for a longer time, but eventually decrease due to carbonate precipitation. For the Frio-I Brine Pilot, all injected CO{sub 2} could ultimately be sequestered as carbonate minerals.

  16. July 2015 Groundwater Sampling at the Sherwood, Washington, Disposal Site

    Office of Legacy Management (LM)

    Sherwood, Washington, Disposal Site October 2015 LMS/SHE/S00715 This page intentionally left blank U.S. Department of Energy DVP-July 2015, Sherwood, Washington October 2015 RIN 15077204 Page i Contents Sampling Event Summary ...............................................................................................................1 Sherwood, Washington, Disposal Site, Sample Location Map .......................................................3 Data Assessment Summary

  17. Interpretation of brine-permeability tests of the Salado Formation at the Waste Isolation Pilot Plant site: First interim report

    SciTech Connect (OSTI)

    Beauheim, R.L. ); Saulnier, G.J. Jr.; Avis, J.D. )

    1991-08-01

    Pressure-pulse tests have been performed in bedded evaporites of the Salado Formation at the Waste Isolation Pilot Plant (WIPP) site to evaluate the hydraulic properties controlling brine flow through the Salado. Hydraulic conductivities ranging from about 10{sup {minus}14} to 10{sup {minus}11} m/s (permeabilities of about 10{sup {minus}21} to 10{sup {minus}18} m{sup 2}) have been interpreted from nine tests conducted on five stratigraphic intervals within eleven meters of the WIPP underground excavations. Tests of a pure halite layer showed no measurable permeability. Pore pressures in the stratigraphic intervals range from about 0.5 to 9.3 MPa. An anhydrite interbed (Marker Bed 139) appears to be one or more orders of magnitude more permeable than the surrounding halite. Hydraulic conductivities appear to increase, and pore pressures decrease, with increasing proximity to the excavations. These effects are particularly evident within two to three meters of the excavations. Two tests indicated the presence of apparent zero-flow boundaries about two to three meters from the boreholes. The other tests revealed no apparent boundaries within the radii of influence of the tests, which were calculated to range from about four to thirty-five meters from the test holes. The data are insufficient to determine if brine flow through evaporites results from Darcy-like flow driven by pressure gradients within naturally interconnected porosity or from shear deformation around excavations connecting previously isolated pores, thereby providing pathways for fluids at or near lithostatic pressure to be driven towards the low-pressure excavations. Future testing will be performed at greater distances from the excavations to evaluate hydraulic properties and processes beyond the range of excavation effects.

  18. Composite analysis E-area vaults and saltstone disposal facilities

    SciTech Connect (OSTI)

    Cook, J.R.

    1997-09-01

    This report documents the Composite Analysis (CA) performed on the two active Savannah River Site (SRS) low-level radioactive waste (LLW) disposal facilities. The facilities are the Z-Area Saltstone Disposal Facility and the E-Area Vaults (EAV) Disposal Facility. The analysis calculated potential releases to the environment from all sources of residual radioactive material expected to remain in the General Separations Area (GSA). The GSA is the central part of SRS and contains all of the waste disposal facilities, chemical separations facilities and associated high-level waste storage facilities as well as numerous other sources of radioactive material. The analysis considered 114 potential sources of radioactive material containing 115 radionuclides. The results of the CA clearly indicate that continued disposal of low-level waste in the saltstone and EAV facilities, consistent with their respective radiological performance assessments, will have no adverse impact on future members of the public.

  19. Generic Argillite/Shale Disposal Reference Case

    SciTech Connect (OSTI)

    Zheng, Liange; Colon, Carlos Jov; Bianchi, Marco; Birkholzer, Jens

    2014-08-08

    Radioactive waste disposal in a deep subsurface repository hosted in clay/shale/argillite is a subject of widespread interest given the desirable isolation properties, geochemically reduced conditions, and widespread geologic occurrence of this rock type (Hansen 2010; Bianchi et al. 2013). Bianchi et al. (2013) provides a description of diffusion in a clay-hosted repository based on single-phase flow and full saturation using parametric data from documented studies in Europe (e.g., ANDRA 2005). The predominance of diffusive transport and sorption phenomena in this clay media are key attributes to impede radionuclide mobility making clay rock formations target sites for disposal of high-level radioactive waste. The reports by Hansen et al. (2010) and those from numerous studies in clay-hosted underground research laboratories (URLs) in Belgium, France and Switzerland outline the extensive scientific knowledge obtained to assess long-term clay/shale/argillite repository isolation performance of nuclear waste. In the past several years under the UFDC, various kinds of models have been developed for argillite repository to demonstrate the model capability, understand the spatial and temporal alteration of the repository, and evaluate different scenarios. These models include the coupled Thermal-Hydrological-Mechanical (THM) and Thermal-Hydrological-Mechanical-Chemical (THMC) models (e.g. Liu et al. 2013; Rutqvist et al. 2014a, Zheng et al. 2014a) that focus on THMC processes in the Engineered Barrier System (EBS) bentonite and argillite host hock, the large scale hydrogeologic model (Bianchi et al. 2014) that investigates the hydraulic connection between an emplacement drift and surrounding hydrogeological units, and Disposal Systems Evaluation Framework (DSEF) models (Greenberg et al. 2013) that evaluate thermal evolution in the host rock approximated as a thermal conduction process to facilitate the analysis of design options. However, the assumptions and the properties (parameters) used in these models are different, which not only make inter-model comparisons difficult, but also compromise the applicability of the lessons learned from one model to another model. The establishment of a reference case would therefore be helpful to set up a baseline for model development. A generic salt repository reference case was developed in Freeze et al. (2013) and the generic argillite repository reference case is presented in this report. The definition of a reference case requires the characterization of the waste inventory, waste form, waste package, repository layout, EBS backfill, host rock, and biosphere. This report mainly documents the processes in EBS bentonite and host rock that are potentially important for performance assessment and properties that are needed to describe these processes, with brief description other components such as waste inventory, waste form, waste package, repository layout, aquifer, and biosphere. A thorough description of the generic argillite repository reference case will be given in Jov Colon et al. (2014).

  20. Disposal of Rocky Flats residues as waste

    SciTech Connect (OSTI)

    Dustin, D.F.; Sendelweck, V.S. . Rocky Flats Plant); Rivera, M.A. )

    1993-01-01

    Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes.

  1. Disposal of Rocky Flats residues as waste

    SciTech Connect (OSTI)

    Dustin, D.F.; Sendelweck, V.S.; Rivera, M.A.

    1993-03-01

    Work is underway at the Rocky Flats Plant to evaluate alternatives for the removal of a large inventory of plutonium-contaminated residues from the plant. One alternative under consideration is to package the residues as transuranic wastes for ultimate shipment to the Waste Isolation Pilot Plant. Current waste acceptance criteria and transportation regulations require that approximately 1000 cubic yards of residues be repackaged to produce over 20,000 cubic yards of WIPP certified waste. The major regulatory drivers leading to this increase in waste volume are the fissile gram equivalent, surface radiation dose rate, and thermal power limits. In the interest of waste minimization, analyses have been conducted to determine, for each residue type, the controlling criterion leading to the volume increase, the impact of relaxing that criterion on subsequent waste volume, and the means by which rules changes may be implemented. The results of this study have identified the most appropriate changes to be proposed in regulatory requirements in order to minimize the costs of disposing of Rocky Flats residues as transuranic wastes.

  2. In Situ Grouting of Liquid Waste Disposal Trenches and Experimental Reactor Fuel Disposal Wells at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Johnson, Ch.; Cange, J.; Lambert, R. [Bechtel Jacobs Company, LLC, Oak Ridge, TN (United States); Trujillo, E. [BWXT Pantex, LLC, Amarillo, TX (United States); Julius, J. [U.S. DOE, Oak Ridge Operations Office, Oak Ridge, TN (United States)

    2008-07-01

    In the early to mid-1960's, liquid low-level wastes (LLLW) generated at Oak Ridge National Laboratory were disposed of in specially-constructed, gravel-filled trenches within the Melton Valley watershed at the lab. The initial selected remedy for Trenches 5 and 7 was in situ vitrification; however, an amendment to the record of decision changed the remedy to in situ grouting of the trenches. The work was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout. At the HRE fuel wells, a 1-m ring of soil surrounding the fuel wells was grouted with acrylamide. The results of the hydraulic conductivity tests ranged from 4.74 x 10{sup -6} to 3.60 x 10{sup -7} cm/sec, values that were well below the 1 x 10{sup -5} cm/sec design criterion. In summary: The ISG Project was conducted to decrease hydraulic conductivity and thereby decrease water flow and contaminate migration from the area of the trenches. The initial remedy for Trenches 5 and 7 in the Melton Valley ROD was for in situ vitrification of the trench matrix. The remedy was changed to in situ grouting of the trenches and HRE fuel wells through an amendment to the ROD after moisture was found in the trenches. The grouting of the trenches was accomplished by filling the void space within the crushed stone section of each trench with cementitious grout. The contaminated soil surrounding the trenches (1-m perimeter) was then grouted with acrylamide grout to further reduce water infiltration. Soil backfill above each of the seven HRE fuel wells was removed to a depth of approximately 1 m by augering, and the soils were replaced with a cement plug to prevent water infiltration from migrating down the original borehole. Soil surrounding the fuel wells was then grouted with acrylamide to ensure water infiltration through the HRE fuel wells is prevented. A summary of the quantities used is shown. After completion of grouting, in-situ hydraulic conductivities of the grouted materials were measured to verify attainment of the design objective. The areas were then covered with multi-layer caps as part of the MV hydrologic isolation project. (authors)

  3. Standardization of DOE Disposal Facilities Waste Acceptance Process

    SciTech Connect (OSTI)

    SHRADER, T.; MACBETH, P.

    2002-01-01

    On February 25, 2000, the US. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLWMLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLWMLLW. A structured, systematic, analytical process using the Six Sigma system identified disposal process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  4. Effect of Oxygen Co-Injected with Carbon Dioxide on Gothic Shale Caprock-CO2-Brine Interaction during Geologic Carbon Sequestration

    SciTech Connect (OSTI)

    Jung, Hun Bok; Um, Wooyong; Cantrell, Kirk J.

    2013-09-16

    Co-injection of oxygen, a significant component in CO2 streams produced by the oxyfuel combustion process, can cause a significant alteration of the redox state in deep geologic formations during geologic carbon sequestration. The potential impact of co-injected oxygen on the interaction between synthetic CO2-brine (0.1 M NaCl) and shale caprock (Gothic shale from the Aneth Unit in Utah) and mobilization of trace metals was investigated at ~10 MPa and ~75 C. A range of relative volume percentages of O2 to CO2 (0, 1, 4 and 8%) were used in these experiments to address the effect of oxygen on shale-CO2-brine interaction under various conditions. Major mineral phases in Gothic shale are quartz, calcite, dolomite, montmorillonite, and pyrite. During Gothic shale-CO2-brine interaction in the presence of oxygen, pyrite oxidation occurred extensively and caused enhanced dissolution of calcite and dolomite. Pyrite oxidation and calcite dissolution subsequently resulted in the precipitation of Fe(III) oxides and gypsum (CaSO42H2O). In the presence of oxygen, dissolved Mn and Ni were elevated because of oxidative dissolution of pyrite. The mobility of dissolved Ba was controlled by barite (BaSO4) precipitation in the presence of oxygen. Dissolved U in the experimental brines increased to ~814 ?g/L, with concentrations being slightly higher in the absence of oxygen than in the presence of oxygen. Experimental and modeling results indicate the interaction between shale caprock and oxygen co-injected with CO2 during geologic carbon sequestration can exert significant impacts on brine pH, solubility of carbonate minerals, stability of sulfide minerals, and mobility of trace metals. The major impact of oxygen is most likely to occur in the zone near CO2 injection wells where impurity gases can accumulate. Oxygen in CO2-brine migrating away from the injection well will be continually consumed through the reactions with sulfide minerals in deep geologic formations.

  5. REQUEST FOR LOST/STOLEN BADGE REPLACEMENT | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    REQUEST FOR LOST/STOLEN BADGE REPLACEMENT REQUEST FOR LOST/STOLEN BADGE REPLACEMENT Form documents the circumstances surrounding the loss of the security badge, i.e., the date the badge was Iost/stolen, location where the badge may have been Iost/stolen, attempts to find the lost badge, etc. PDF icon REQUEST FOR LOST/STOLEN BADGE REPLACEMENT More Documents & Publications DOE HQ F 473.1 (fillable pdf) DOE F 5639.2 DOE F 5634.1

  6. LED Performance Specification Series: T8 Replacement Lamps

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Photo credit: PNNL LED T8 replacements may contain dozens of high power LEDs or hundreds of 5mm LEDs behind a clear or frosted lens, all in a medium bi-pin T8 lamp package. Table 1. CALiPER Test Results for 4-foot LED T8 Replacements with Fluorescent Benchmarks Performance Characteristics LED T8 Replacements Fluorescent Benchmarks Range (12 lamps tested) Average Mfr. Data (75 lamps) CALiPER (2 fxtures tested) Initial Lamp Light Output (lm) 345 - 1,579 1,111 2,778 3,091 Initial 2-Lamp System

  7. Maintenance Guide for DOE Low-Level Waste Disposal Facility | Department of

    Energy Savers [EERE]

    Energy Maintenance Guide for DOE Low-Level Waste Disposal Facility Maintenance Guide for DOE Low-Level Waste Disposal Facility Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses PDF icon Maintenance Guide for DOE Low-Level Waste Disposal Facility More Documents & Publications Format and Content Guide for DOE Low-Level Waste Disposal Facility Format and Content Guide for DOE Low-Level Waste Disposal Facility

  8. Innovative Technique Accelerates Waste Disposal at Idaho Site | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Energy Technique Accelerates Waste Disposal at Idaho Site Innovative Technique Accelerates Waste Disposal at Idaho Site May 15, 2013 - 12:00pm Addthis A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. A product drum of mixed low-level waste is lowered into a high-density polyethylene macro-pack. Macro-packs from the Idaho site are shown here safely and compliantly disposed. Macro-packs from the Idaho site are shown here safely and compliantly

  9. Immobilized low-level waste disposal options configuration study

    SciTech Connect (OSTI)

    Mitchell, D.E.

    1995-02-01

    This report compiles information that supports the eventual conceptual and definitive design of a disposal facility for immobilized low-level waste. The report includes the results of a joint Westinghouse/Fluor Daniel Inc. evaluation of trade-offs for glass manufacturing and product (waste form) disposal. Though recommendations for the preferred manufacturing and disposal option for low-level waste are outside the scope of this document, relative ranking as applied to facility complexity, safety, remote operation concepts and ease of retrieval are addressed.

  10. Analysis of alternatives for immobilized low activity waste disposal

    SciTech Connect (OSTI)

    Burbank, D.A.

    1997-10-28

    This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

  11. Salt Lake City, Utah, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Salt Lake City, Utah, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site and disposal site at Salt Lake City, Utah. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Salt Lake City Processing and Disposal Sites Site Descriptions and History The former Salt Lake City processing site is located about 4 miles south-southwest of the center of Salt

  12. Municipal garbage disposal: A problem we cannot ignore

    SciTech Connect (OSTI)

    Not Available

    1989-01-01

    In 1980 the US generated 150 million metric tons of municipal solid waste, and this figure is expected to increase to over 200 million metric tons by 1990. This comment discusses the traditional approaches to waste management, as well as current options available for waste disposal and the federal environmental laws that impinge on these options. Next, the national dimensions of the garbage disposal problem, as epitomized by the garbage barge and the international export of waste generated by this country, are discussed. This Comment concludes with recommendations for a change in public policy to foster recycling, taxing non-biodegradable products, as well as more stringent regulatory controls on solid waste disposal.

  13. Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Full Document...

  14. Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant Proposed On-Site Disposal Facility (OSDF) at the Paducah Gaseous Diffusion Plant Full Document and Summary Versions...

  15. EA-0923: Winnett School District Boiler Replacement Project, Winnett, Montana

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to replace the Winnett School District complex's existing oil-fired heating system with a new coal-fired heating system with funds...

  16. Laboratory Evaluation of LED T8 Replacement Lamp Products

    SciTech Connect (OSTI)

    Richman, Eric E.; Kinzey, Bruce R.; Miller, Naomi J.

    2011-05-23

    A report on a lab setting analysis involving LED lamps intended to directly replace T8 fluorescent lamps (4') showing light output, power, and economic comparisons with other fluorescent options.

  17. Ultrasound image guided acetabular implant orientation during total hip replacement

    DOE Patents [OSTI]

    Chang, John; Haddad, Waleed; Kluiwstra, Jan-Ulco; Matthews, Dennis; Trauner, Kenneth

    2003-08-19

    A system for assisting in precise location of the acetabular implant during total hip replacement. The system uses ultrasound imaging for guiding the placement and orientation of the implant.

  18. Reminder: Y-12 Public Warning Siren System being replaced, tested...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    located around the Oak Ridge area is being replaced this month with a test of the new system on Sept. 26. The vendor, American Signal, will be testing the sirens Sept. 26...

  19. Replace Pressure-Reducing Valves with Backpressure Turbogenerators

    SciTech Connect (OSTI)

    Not Available

    2006-01-01

    This revised ITP steam tip sheet on replacing pressure-reducing valves provides how-to advice for improving industrial steam systems using low-cost, proven practices and technologies.

  20. Washington State Department of Ecology: Replacement Wells Requiring...

    Open Energy Info (EERE)

    Ecology: Replacement Wells Requiring a Water Right Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- OtherOther: Washington State Department of...

  1. Quenching and Partitioning Process Development to Replace Hot Stamping of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    High-Strength Automotive Steel | Department of Energy Quenching and Partitioning Process Development to Replace Hot Stamping of High-Strength Automotive Steel Quenching and Partitioning Process Development to Replace Hot Stamping of High-Strength Automotive Steel A combination of deep alloy development experience, designed experiments, computational tools, and characterization instruments will develop Quenching and Partitioning processing for Third-Generation Advanced High-Strength Steels

  2. Exploring the speed and performance of molecular replacement with AMPLE

    Office of Scientific and Technical Information (OSTI)

    using QUARK ab initio protein models (Journal Article) | SciTech Connect Exploring the speed and performance of molecular replacement with AMPLE using QUARK ab initio protein models Citation Details In-Document Search Title: Exploring the speed and performance of molecular replacement with AMPLE using QUARK ab initio protein models Two ab initio modelling programs solve complementary sets of targets, enhancing the success of AMPLE with small proteins. AMPLE clusters and truncates ab initio

  3. Cobalt discovery replaces precious metals as industrial catalyst

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cobalt Discovery Replaces Precious Metals Cobalt discovery replaces precious metals as industrial catalyst Cobalt holds promise as an industrial catalyst with potential applications in such energy-related technologies such as production of biofuels and reduction of carbon dioxide. November 26, 2012 The artwork depicts the substitution of cobalt for precious metals in catalysis as a variation on the ancient alchemical theme of transmuting base metals into precious ones. The artwork depicts the

  4. Cobalt discovery replaces precious metals as industrial catalyst

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Cobalt Discovery Replaces Precious Metals Cobalt discovery replaces precious metals as industrial catalyst Cobalt holds promise as an industrial catalyst with potential applications in such energy-related technologies such as production of biofuels and reduction of carbon dioxide. November 26, 2012 The artwork depicts the substitution of cobalt for precious metals in catalysis as a variation on the ancient alchemical theme of transmuting base metals into precious ones. The artwork depicts the

  5. Replacement-2-A Wholesale Power Rate Schedule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    2-A Wholesale Power Rate Schedule Replacement-2-A Wholesale Power Rate Schedule Area: Replacement Energy System: Kerr-Philpott This rate schedule shall be available to public bodies and cooperatives (any one of whom is hereinafter called the Customer) in North Carolina and Virginia to whom power is provided pursuant to contracts between the Government and the customer from the John H. Kerr and Philpott Projects (or Kerr-Philpott System). This rate schedule shall be applicable to the sale of

  6. Biomass 2011: Replace the Whole Barrel, Supply the Whole Market |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy 1: Replace the Whole Barrel, Supply the Whole Market Biomass 2011: Replace the Whole Barrel, Supply the Whole Market The New Horizons of Bioenergy Biomass 2011 July 26-27, 2011 Gaylord National Resort and Convention Center 201 Waterfront Street National Harbor, MD 20745 Thank you to everyone who attended and participated to help make Biomass 2011 a remarkable success. More than 600 speakers, moderators, sponsors, exhibitors, and attendees were able to listen to

  7. EERE Success Story-Arizona: Solar Panels Replace Inefficient Fossil

    Office of Environmental Management (EM)

    Fuel-Powered Energy Systems | Department of Energy Arizona: Solar Panels Replace Inefficient Fossil Fuel-Powered Energy Systems EERE Success Story-Arizona: Solar Panels Replace Inefficient Fossil Fuel-Powered Energy Systems May 1, 2014 - 9:33am Addthis The Agricultural Renewable Energy Conversion Incentive Program, funded in part by DOE's State Energy Program (SEP), assists farmers and ranchers to convert fossil-fueled agricultural production systems to renewable energy power. The program

  8. Figure ES2. Annual Indices of Real Disposable Income, Vehicle...

    U.S. Energy Information Administration (EIA) Indexed Site

    ES2 Figure ES2. Annual Indices of Real Disposable Income, Vehicle-Miles Traveled, Consumer Price Index (CPI-U), and Real Average Retail Gasoline Price, 1978-2004, 1985100...

  9. Basis for Section 3116 Determination for Salt Waste Disposal...

    Office of Environmental Management (EM)

    WD-2005-001 January 2006 Basis for Section 3116 Determination for Salt Waste Disposal at ......... 28 4.0 THE WASTE DOES NOT REQUIRE PERMANENT ISOLATION IN A ...

  10. NNSS Waste Disposal Proves Vital Resource for DOE Complex

    Broader source: Energy.gov [DOE]

    The NNSS is home to a state-of-the-art waste management facility, providing a permanent disposal option for a select group of LLW/ MLLW generators whose programs have passed a rigorous approval process.

  11. EIS-0026; Waste Isolation Pilot Plant Disposal Phase Final Supplementa...

    Office of Environmental Management (EM)

    by calling 1 (800) 336-9477 COVER SHEET Lead Agency: U.S. Department of Energy Title: Waste Isolation Pilot Plant Disposal Phase Final Supplemental Environmental Impact Statement...

  12. ORS 466 - Storage, Treatment, and Disposal of Hazardous Waste...

    Open Energy Info (EERE)

    ORS 466 - Storage, Treatment, and Disposal of Hazardous Waste and Materials Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: ORS...

  13. 6.0 TREATMENT, STORAGE, AND DISPOSAL UNIT PROCESS

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    6-1 6.0 TREATMENT, STORAGE, AND DISPOSAL UNIT PROCESS 6.1 INTRODUCTION This section discusses the requirements of RCRA and the State of Washington Hazardous Waste Management Act,...

  14. Laboratory to demolish excavation enclosures at Material Disposal...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work...

  15. Integration of EBS Models with Generic Disposal System Models

    Broader source: Energy.gov [DOE]

    This report summarizes research activities on engineered barrier system (EBS) model integration with the generic disposal system model (GDSM), and used fuel degradation and radionuclide mobilization (RM) in support of the EBS evaluation and tool development within the UFD campaign.

  16. Disposal Facility Reaches 15-Million-Ton Milestone

    Broader source: Energy.gov [DOE]

    RICHLAND, Wash. EMs Environmental Restoration Disposal Facility (ERDF) a massive landfill for low-level radioactive and hazardous waste at the Hanford site has achieved a major cleanup milestone.

  17. 17.3 - Acquisition, Use and Disposal of Real Property

    Broader source: Energy.gov (indexed) [DOE]

    and Disposal of Real Estate DOE Directives DOE Order 413.3B, Program and Project Management for the Acquisition of Capital Assets, or current version DOE Order 430.1B, Real...

  18. Draft Geologic Disposal Requirements Basis for STAD Specification

    SciTech Connect (OSTI)

    Ilgen, Anastasia G.; Bryan, Charles R.; Hardin, Ernest

    2015-03-25

    This document provides the basis for requirements in the current version of Performance Specification for Standardized Transportation, Aging, and Disposal Canister Systems, (FCRD-NFST-2014-0000579) that are driven by storage and geologic disposal considerations. Performance requirements for the Standardized Transportation, Aging, and Disposal (STAD) canister are given in Section 3.1 of that report. Here, the requirements are reviewed and the rationale for each provided. Note that, while FCRD-NFST-2014-0000579 provides performance specifications for other components of the STAD storage system (e.g. storage overpack, transfer and transportation casks, and others), these have no impact on the canister performance during disposal, and are not discussed here.

  19. Supporting Calculations For Submerged Bed Scrubber Condensate Disposal Preconceptual Study

    SciTech Connect (OSTI)

    Pajunen, A. J.; Tedeschi, A. R.

    2012-09-18

    This document provides supporting calculations for the preparation of the Submerged Bed Scrubber Condensate Disposal Preconceptual Study report The supporting calculations include equipment sizing, Hazard Category determination, and LAW Melter Decontamination Factor Adjustments.

  20. ORS 454 - Sewage Treatment and Disposal Systems | Open Energy...

    Open Energy Info (EERE)

    54 - Sewage Treatment and Disposal Systems Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: ORS 454 - Sewage Treatment and...

  1. NE-23 Disposal of Offsite-Generated Defense Radioactive Waste...

    Office of Legacy Management (LM)

    piL +3 *3L 52. NE-23 Disposal of Offsite-Generated Defense Radioactive Waste, Ventron FUSRAP Site Jill E. Lytle, DP-12 NE-23 The Office of Remedial Action and Waste Technology has...

  2. Microsoft Word - Panel 5 Disposal Operations Complete.docx

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    rogram con rground is c Each disp roximately 1 feet of TRU en dispose perations in r football fie 1 or Immed pletes D of the W 15, 2011 - T 5 of the Wa nth, the fina nel, which t...

  3. Salt disposal of heat-generating nuclear waste.

    SciTech Connect (OSTI)

    Leigh, Christi D.; Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

  4. Operational Issues at the Environmental Restoration Disposal Facility at Hanford

    Office of Environmental Management (EM)

    Hanford Operations Evaluating Operational Issues at the Environmental Restoration Disposal Facility at Hanford By Craig H. Benson, PhD, PE; William H. Albright, PhD; and David P. Ray, PE Sponsored by: The Office of Engineering and Technology (EM-20) 17 June 2007 i TABLE OF CONTENTS EXECUTIVE SUMMARY ii ACKNOWLEDGEMENTS iv INTRODUCTION 1 BACKGROUND 1 Environmental Restoration Disposal Facility 1 Source of Concern 2 LINES OF INQUIRY 2 1. Validate Scope of Identified Problems 2 2. Assess Contractor

  5. Research, Development, and Demonstration Roadmap for Deep Borehole Disposal

    Office of Energy Efficiency and Renewable Energy (EERE)

    This roadmap is intended to advance deep borehole disposal (DBD) from its current conceptual status to potential future deployment as a disposal system for spent nuclear fuel (SNF) and high-level waste (HLW). The objectives of the DBD RD&D roadmap include providing the technical basis for fielding a DBD demonstration project, defining the scientific research activities associated with site characterization and postclosure safety, and defining the engineering demonstration activities associated with deep borehole drilling, completion, and surrogate waste canister emplacement.

  6. An Investigation for Disposal of Drill Cuttings into Unconsolidated

    Office of Scientific and Technical Information (OSTI)

    Sandstones and Clayey Sands (Technical Report) | SciTech Connect Technical Report: An Investigation for Disposal of Drill Cuttings into Unconsolidated Sandstones and Clayey Sands Citation Details In-Document Search Title: An Investigation for Disposal of Drill Cuttings into Unconsolidated Sandstones and Clayey Sands This project include experimental data and a set of models for relating elastic moduli/porosity/texture and static-to-dynamic moduli to strength and failure relationships for

  7. Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Facility in Texas | Department of Energy Delivers First Radioactive Waste Shipment to Disposal Facility in Texas Portsmouth Site Delivers First Radioactive Waste Shipment to Disposal Facility in Texas August 27, 2013 - 12:00pm Addthis Waste management and transportation personnel worked late to complete the first shipment to WCS. Through a contract with DOE, WCS will treat and accept potentially hazardous waste that has been at the Portsmouth site for decades. Pictured (from left) are Scott

  8. FACT SHEET: The Path Forward on Nuclear Waste Disposal

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    The Path Forward on Nuclear Waste Disposal Finding a path forward for disposition of nuclear waste is needed to help ensure the long-term contribution of nuclear power to meeting the nation's energy needs and to fulfill the federal government's responsibility to manage nuclear waste. Today, Secretary Moniz outlined several steps towards this vital goal. First, President Obama today authorized the Department of Energy (DOE) to begin the process of developing a repository to be used for disposal

  9. Naval Spent Nuclear Fuel disposal Container System Description Document

    SciTech Connect (OSTI)

    N. E. Pettit

    2001-07-13

    The Naval Spent Nuclear Fuel Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers/waste packages are loaded and sealed in the surface waste handling facilities, transferred underground through the access drifts using a rail mounted transporter, and emplaced in emplacement drifts. The Naval Spent Nuclear Fuel Disposal Container System provides long term confinement of the naval spent nuclear fuel (SNF) placed within the disposal containers, and withstands the loading, transfer, emplacement, and retrieval operations. The Naval Spent Nuclear Fuel Disposal Container System provides containment of waste for a designated period of time and limits radionuclide release thereafter. The waste package maintains the waste in a designated configuration, withstands maximum credible handling and rockfall loads, limits the waste form temperature after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Each naval SNF disposal container will hold a single naval SNF canister. There will be approximately 300 naval SNF canisters, composed of long and short canisters. The disposal container will include outer and inner cylinder walls and lids. An exterior label will provide a means by which to identify a disposal container and its contents. Different materials will be selected for the waste package inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and the natural barrier will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel while the outer cylinder and outer cylinder lids will be made of high-nickel alloy.

  10. Grand Junction, Colorado, Processing Site and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Grand Junction, Colorado, Disposal and Processing Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I disposal and processing sites at Grand Junction, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Grand Junction, Colorado, Sites Site Description and History The former Grand Junction processing site, historically known as the Climax uranium mill, sits at an elevation of

  11. Gunnison, Colorado, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Gunnison, Colorado, Processing and Disposal Sites This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site and disposal site at Gunnison, Colorado. These sites are managed by the U.S. Department of Energy Office of Legacy Management. Location of the Gunnison, Colorado, Sites Site Description and History The Gunnison, Colorado, Processing Site is a former uranium-ore processing site on a 61.5-acre tract of land adjacent to the

  12. Lakeview, Oregon, Processing and Disposal Sites Fact Sheet

    Office of Legacy Management (LM)

    Lakeview, Oregon, Processing/Disposal Site This fact sheet provides information about the Uranium Mill Tailings Radiation Control Act of 1978 Title I processing site and disposal site near Lakeview, Oregon. This site is managed by the U.S. Department of Energy Office of Legacy Management. Locations of the Lakeview, Oregon, Sites Site Description and History The Lakeview processing site is a former uranium-ore processing facility located approximately 1.5 miles north- northwest of the town of

  13. Final Environmental Impact Statement Brings DOE Closer to Disposing Unique

    Energy Savers [EERE]

    Waste | Department of Energy Final Environmental Impact Statement Brings DOE Closer to Disposing Unique Waste Final Environmental Impact Statement Brings DOE Closer to Disposing Unique Waste March 16, 2016 - 12:45pm Addthis Theresa Kliczewski, environmental protection specialist in EM’s Office of Disposition Planning and Policy, explains the GTCC EIS path forward to participants in the Waste Management Symposia 2016 in Phoenix. Theresa Kliczewski, environmental protection specialist in

  14. Moving Forward to Address Nuclear Waste Storage and Disposal | Department

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    of Energy Moving Forward to Address Nuclear Waste Storage and Disposal Moving Forward to Address Nuclear Waste Storage and Disposal March 24, 2015 - 2:15pm Addthis Three trucks transport nuclear waste from the Savannah River Site in South Carolina. | Energy Department photo. Three trucks transport nuclear waste from the Savannah River Site in South Carolina. | Energy Department photo. John Kotek John Kotek Acting Assistant Secretary for the Office of Nuclear Energy Thirty years ago, our

  15. DOE - Office of Legacy Management -- Pennsylvania Disposal Site - PA 43

    Office of Legacy Management (LM)

    Disposal Site - PA 43 FUSRAP Considered Sites Site: Pennsylvania Disposal Site (PA.43) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This site is one of a group of 77 FUSRAP considered sites for which few, if any records are available in their respective site files to provide an historical account of past operations and their relationship, if

  16. Disposal Systems Evaluations and Tool Development - Engineered Barrier

    Office of Environmental Management (EM)

    System (EBS) Evaluation | Department of Energy Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation Disposal Systems Evaluations and Tool Development - Engineered Barrier System (EBS) Evaluation The engineered barrier system (EBS) plays a key role in the long-term isolation of nuclear waste in geological repository environments. This report focuses on the progress made in the evaluation of EBS design concepts, assessment of clay phase stability at

  17. REE Sorption Study of Seived -50 +100 Mesh Fraction of Media #1 in Brine #1 at Different Concentrations of REE at 70C

    SciTech Connect (OSTI)

    Gary Garland

    2015-06-29

    This dataset shows the sorption capacities of smaller grain size (-50 +100 mesh) of media #1 in brine #1 at different starting concentrations of REE's at elevated temperature of 70C. The experimental conditions are 2g of -50 +100 mesh media #1 to 150mL of REE solution at concentartions of .2ppm each, 2ppm each, and 20ppm each. The pH of the solution is 5.5, and the temperature was at 70C.

  18. Uncanistered Spent Nuclear fuel Disposal Container System Description Document

    SciTech Connect (OSTI)

    N. E. Pettit

    2001-07-13

    The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident.

  19. Standardization of DOE Disposal Facilities Waste Acceptance Processes

    SciTech Connect (OSTI)

    Shrader, T. A.; Macbeth, P. J.

    2002-02-26

    On February 25, 2000, the U.S. Department of Energy (DOE) issued the Record of Decision (ROD) for the Waste Management Programmatic Environmental Impact Statement (WM PEIS) for low-level and mixed low-level wastes (LLW/ MLLW) treatment and disposal. The ROD designated the disposal sites at Hanford and the Nevada Test Site (NTS) to dispose of LLW/MLLW from sites without their own disposal facilities. DOE's Richland Operations Office (RL) and the National Nuclear Security Administration's Nevada Operations Office (NV) have been charged with effectively implementing the ROD. To accomplish this task NV and RL, assisted by their operating contractors Bechtel Nevada (BN), Fluor Hanford (FH), and Bechtel Hanford (BH) assembled a task team to systematically map out and evaluate the current waste acceptance processes and develop an integrated, standardized process for the acceptance of LLW/MLLW. A structured, systematic, analytical process using the Six Sigma system identified dispos al process improvements and quantified the associated efficiency gains to guide changes to be implemented. The review concluded that a unified and integrated Hanford/NTS Waste Acceptance Process would be a benefit to the DOE Complex, particularly the waste generators. The Six Sigma review developed quantitative metrics to address waste acceptance process efficiency improvements, and provides an initial look at development of comparable waste disposal cost models between the two disposal sites to allow quantification of the proposed improvements.

  20. Evaluation of experimentally measured and model-calculated pH for rock-brine-CO2 systems under geologic CO2 sequestration conditions

    SciTech Connect (OSTI)

    Shao, Hongbo; Thompson, Christopher J.; Cantrell, Kirk J.

    2013-11-01

    pH is an essential parameter for understanding the geochemical reactions that occur in rock-brine-CO2 systems when CO2 is injected into deep geologic formations for long-term storage. Due to a lack of reliable experimental methods, most laboratory studies conducted under geological CO2 sequestration (GCS) conditions have relied on thermodynamic modeling to estimate pH. The accuracy of these model predictions is typically uncertain. In our previous work, we have developed a method for pH determination by in-situ spectrophotometry. In the present work, we expanded the applicable pH range for this method and measured the pH of several rock-brine-CO2 systems at GCS conditions for five rock samples collected from ongoing GCS demonstration projects. Experimental measurements were compared with pH values calculated using several geochemical modeling approaches. The effect of different thermodynamic databases on the accuracy of model prediction was evaluated. Results indicate that the accuracy of model calculations is rock-dependent. For rocks comprised of carbonate and sandstone, model results generally agreed well with experimentally measured pH; however, for basalt, significant differences were observed. These discrepancies may be due to the models failure to fully account for certain reaction occurring between the basalt minerals the CO2-saturated brine solutions.

  1. Waste disposal technology transfer matching requirement clusters for waste disposal facilities in China

    SciTech Connect (OSTI)

    Dorn, Thomas; Nelles, Michael; Flamme, Sabine; Jinming, Cai

    2012-11-15

    Highlights: Black-Right-Pointing-Pointer We outline the differences of Chinese MSW characteristics from Western MSW. Black-Right-Pointing-Pointer We model the requirements of four clusters of plant owner/operators in China. Black-Right-Pointing-Pointer We examine the best technology fit for these requirements via a matrix. Black-Right-Pointing-Pointer Variance in waste input affects result more than training and costs. Black-Right-Pointing-Pointer For China technology adaptation and localisation could become push, not pull factors. - Abstract: Even though technology transfer has been part of development aid programmes for many decades, it has more often than not failed to come to fruition. One reason is the absence of simple guidelines or decision making tools that help operators or plant owners to decide on the most suitable technology to adopt. Practical suggestions for choosing the most suitable technology to combat a specific problem are hard to get and technology drawbacks are not sufficiently highlighted. Western counterparts in technology transfer or development projects often underestimate or don't sufficiently account for the high investment costs for the imported incineration plant; the differing nature of Chinese MSW; the need for trained manpower; and the need to treat flue gas, bunker leakage water, and ash, all of which contain highly toxic elements. This article sets out requirements for municipal solid waste disposal plant owner/operators in China as well as giving an attribute assessment for the prevalent waste disposal plant types in order to assist individual decision makers in their evaluation process for what plant type might be most suitable in a given situation. There is no 'best' plant for all needs and purposes, and requirement constellations rely on generalisations meaning they cannot be blindly applied, but an alignment of a type of plant to a type of owner or operator can realistically be achieved. To this end, a four-step approach is suggested and a technology matrix is set out to ease the choice of technology to transfer and avoid past errors. The four steps are (1) Identification of plant owner/operator requirement clusters; (2) Determination of different municipal solid waste (MSW) treatment plant attributes; (3) Development of a matrix matching requirement clusters to plant attributes; (4) Application of Quality Function Deployment Method to aid in technology localisation. The technology transfer matrices thus derived show significant performance differences between the various technologies available. It is hoped that the resulting research can build a bridge between technology transfer research and waste disposal research in order to enhance the exchange of more sustainable solutions in future.

  2. Strontium isotope quantification of siderite, brine and acid mine drainage contributions to abandoned gas well discharges in the Appalachian Plateau

    SciTech Connect (OSTI)

    Chapman, Elizabeth C.; Capo, Rosemary C.; Stewart, Brian W.; Hedin, Robert S.; Weaver, Theodore J.; Edenborn, Harry M.

    2013-04-01

    Unplugged abandoned oil and gas wells in the Appalachian region can serve as conduits for the movement of waters impacted by fossil fuel extraction. Strontium isotope and geochemical analysis indicate that artesian discharges of water with high total dissolved solids (TDS) from a series of gas wells in western Pennsylvania result from the infiltration of acidic, low Fe (Fe < 10 mg/L) coal mine drainage (AMD) into shallow, siderite (iron carbonate)-cemented sandstone aquifers. The acidity from the AMD promotes dissolution of the carbonate, and metal- and sulfate-contaminated waters rise to the surface through compromised abandoned gas well casings. Strontium isotope mixing models suggest that neither upward migration of oil and gas brines from Devonian reservoirs associated with the wells nor dissolution of abundant nodular siderite present in the mine spoil through which recharge water percolates contribute significantly to the artesian gas well discharges. Natural Sr isotope composition can be a sensitive tool in the characterization of complex groundwater interactions and can be used to distinguish between inputs from deep and shallow contamination sources, as well as between groundwater and mineralogically similar but stratigraphically distinct rock units. This is of particular relevance to regions such as the Appalachian Basin, where a legacy of coal, oil and gas exploration is coupled with ongoing and future natural gas drilling into deep reservoirs.

  3. Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-09-01

    According to an American Petroleum Institute production waste survey reported on by P.G. Wakim in 1987 and 1988, the exploration and production segment of the US oil and gas industry generated more than 360 million barrels (bbl) of drilling wastes, more than 20 billion bbl of produced water, and nearly 12 million bbl of associated wastes in 1985. Current exploration and production activities are believed to be generating comparable quantities of these oil field wastes. Wakim estimates that 28% of drilling wastes, less than 2% of produced water, and 52% of associated wastes are disposed of in off-site commercial facilities. In recent years, interest in disposing of oil field wastes in solution-mined salt caverns has been growing. This report provides information on the availability of commercial disposal companies in oil-and gas-producing states, the treatment and disposal methods they employ, and the amounts they charge. It also compares cavern disposal costs with the costs of other forms of waste disposal.

  4. Methods for disassembling, replacing and assembling parts of a steam cooling system for a gas turbine

    DOE Patents [OSTI]

    Wilson, Ian D. (Mauldin, SC); Wesorick, Ronald R. (Albany, NY)

    2002-01-01

    The steam cooling circuit for a gas turbine includes a bore tube assembly supplying steam to circumferentially spaced radial tubes coupled to supply elbows for transitioning the radial steam flow in an axial direction along steam supply tubes adjacent the rim of the rotor. The supply tubes supply steam to circumferentially spaced manifold segments located on the aft side of the 1-2 spacer for supplying steam to the buckets of the first and second stages. Spent return steam from these buckets flows to a plurality of circumferentially spaced return manifold segments disposed on the forward face of the 1-2 spacer. Crossover tubes couple the steam supply from the steam supply manifold segments through the 1-2 spacer to the buckets of the first stage. Crossover tubes through the 1-2 spacer also return steam from the buckets of the second stage to the return manifold segments. Axially extending return tubes convey spent cooling steam from the return manifold segments to radial tubes via return elbows. The bore tube assembly, radial tubes, elbows, manifold segments and crossover tubes are removable from the turbine rotor and replaceable.

  5. Multi-pack Disposal Concepts for Spent Fuel (Rev. 0)

    SciTech Connect (OSTI)

    Hadgu, Teklu; Hardin, Ernest; Matteo, Edward N.

    2015-12-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media (Hardin et al., 2012). Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design (CRWMS M&O, 1999). Thermal analysis showed that, if “enclosed” concepts are constrained by peak package/buffer temperature, waste package capacity is limited to 4 PWR assemblies (or 9-BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems (EnergySolution, 2015). This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  6. Multi-Pack Disposal Concepts for Spent Fuel (Revision 1)

    SciTech Connect (OSTI)

    Hardin, Ernest; Matteo, Edward N.; Hadgu, Teklu

    2016-01-01

    At the initiation of the Used Fuel Disposition (UFD) R&D campaign, international geologic disposal programs and past work in the U.S. were surveyed to identify viable disposal concepts for crystalline, clay/shale, and salt host media. Concepts for disposal of commercial spent nuclear fuel (SNF) and high-level waste (HLW) from reprocessing are relatively advanced in countries such as Finland, France, and Sweden. The UFD work quickly showed that these international concepts are all “enclosed,” whereby waste packages are emplaced in direct or close contact with natural or engineered materials . Alternative “open” modes (emplacement tunnels are kept open after emplacement for extended ventilation) have been limited to the Yucca Mountain License Application Design. Thermal analysis showed that if “enclosed” concepts are constrained by peak package/buffer temperature, that waste package capacity is limited to 4 PWR assemblies (or 9 BWR) in all media except salt. This information motivated separate studies: 1) extend the peak temperature tolerance of backfill materials, which is ongoing; and 2) develop small canisters (up to 4-PWR size) that can be grouped in larger multi-pack units for convenience of storage, transportation, and possibly disposal (should the disposal concept permit larger packages). A recent result from the second line of investigation is the Task Order 18 report: Generic Design for Small Standardized Transportation, Aging and Disposal Canister Systems. This report identifies disposal concepts for the small canisters (4-PWR size) drawing heavily on previous work, and for the multi-pack (16-PWR or 36-BWR).

  7. Location standards for RCRA Treatment, Storage, and Disposal Facilities (TSDFs). RCRA Information Brief

    SciTech Connect (OSTI)

    Not Available

    1993-10-01

    This bulletin describes RCRA location standards for hazardous waste storage and disposal facilities.

  8. Disposal of oil field wastes into salt caverns: Feasibility, legality, risk, and costs

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-10-01

    Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of oil field wastes, the risks to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne`s research indicates that disposal of oil field wastes into salt caverns is feasible and legal. The risk from cavern disposal of oil field wastes appears to be below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

  9. Uncanistered Spent Nuclear fuel Disposal Container System Description Document

    SciTech Connect (OSTI)

    2000-10-12

    The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.

  10. Integrated Disposal Facility FY2011 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Westsik, Joseph H.

    2011-09-29

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 x 10{sup 5} m{sup 3} of glass (Certa and Wells 2010). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 8.9 x 10{sup 14} Bq total activity) of long-lived radionuclides, principally {sup 99}Tc (t{sub 1/2} = 2.1 x 10{sup 5}), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2011 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses.

  11. Disposal Practices at the Nevada Test Site 2008 | Department of Energy

    Energy Savers [EERE]

    Disposal Practices at the Nevada Test Site 2008 Disposal Practices at the Nevada Test Site 2008 Full Document and Summary Versions are available for download PDF icon Disposal Practices at the Nevada Test Site 2008 PDF icon Summary - Disposal Practices at the Nevada Test Site More Documents & Publications Briefing: DOE EM ITR Landfill Assessment Project Lessons Learned Disposal Practices at the Savannah River Site Compilation of ETR Summaries

  12. Los Alamos Lab Completes Excavation of Waste Disposal Site Used in the

    Energy Savers [EERE]

    1940s | Department of Energy Lab Completes Excavation of Waste Disposal Site Used in the 1940s Los Alamos Lab Completes Excavation of Waste Disposal Site Used in the 1940s Los Alamos National Laboratory recently completed excavation of its oldest waste disposal site, Material Disposal Area B (MDA-B), thanks to American Recovery and Reinvestment Act funding. PDF icon Los Alamos Lab Completes Excavation of Waste Disposal Site Used in the 1940s More Documents & Publications Manhattan

  13. DOE - Office of Legacy Management -- 11 E (2) Disposal Cell - 037

    Office of Legacy Management (LM)

    11 E (2) Disposal Cell - 037 FUSRAP Considered Sites Site: 11 E. (2) Disposal Cell (037) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: This designation refers to an Envirocare of Utah disposal cell for byproduct material as defined under Section 11 e. (2) of the Atomic Energy Act. Aportion of the material disposed at this 11 e. (2) disposal

  14. Simple Maintenance Saves Costly Furnace Repair/Replacement | Department of

    Energy Savers [EERE]

    Energy Simple Maintenance Saves Costly Furnace Repair/Replacement Simple Maintenance Saves Costly Furnace Repair/Replacement January 6, 2010 - 8:26am Addthis Chris Stewart Senior Communicator at DOE's National Renewable Energy Laboratory For the past few weeks, my forced-air gas furnace has been on the fritz. I blame this on the fact that I haven't been as diligent as I should have been with regular furnace maintenance, which includes: Checking the condition of the vent connection pipe and

  15. Mineral dissolution and precipitation during CO2 injection at the Frio-I Brine Pilot: Geochemical modeling and uncertainty analysis

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Ilgen, A. G.; Cygan, R. T.

    2015-12-07

    During the Frio-I Brine Pilot CO2 injection experiment in 2004, distinct geochemical changes in response to the injection of 1600 tons of CO2 were recorded in samples collected from the monitoring well. Previous geochemical modeling studies have considered dissolution of calcite and iron oxyhydroxides, or release of adsorbed iron, as the most likely sources of the increased ion concentrations. We explore in this modeling study possible alternative sources of the increasing calcium and iron, based on the data from the detailed petrographic characterization of the Upper Frio Formation “C”. Particularly, we evaluate whether dissolution of pyrite and oligoclase (anorthitemore » component) can account for the observed geochemical changes. Due to kinetic limitations, dissolution of pyrite and anorthite cannot account for the increased iron and calcium concentrations on the time scale of the field test (10 days). However, dissolution of these minerals is contributing to carbonate and clay mineral precipitation on the longer time scales (1000 years). The one-dimensional reactive transport model predicts carbonate minerals, dolomite and ankerite, as well as clay minerals kaolinite, nontronite and montmorillonite, will precipitate in the Frio Formation “C” sandstone as the system progresses towards chemical equilibrium during a 1000-year period. Cumulative uncertainties associated with using different thermodynamic databases, activity correction models (Pitzer vs. B-dot), and extrapolating to reservoir temperature, are manifested in the difference in the predicted mineral phases. Furthermore, these models are consistent with regards to the total volume of mineral precipitation and porosity values which are predicted to within 0.002%.« less

  16. Geological aspects of the nuclear waste disposal problem

    SciTech Connect (OSTI)

    Laverov, N.P.; Omelianenko, B.L.; Velichkin, V.I.

    1994-06-01

    For the successful solution of the high-level waste (HLW) problem in Russia one must take into account such factors as the existence of the great volume of accumulated HLW, the large size and variety of geological conditions in the country, and the difficult economic conditions. The most efficient method of HLW disposal consists in the maximum use of protective capacities of the geological environment and in using inexpensive natural minerals for engineered barrier construction. In this paper, the principal trends of geological investigation directed toward the solution of HLW disposal are considered. One urgent practical aim is the selection of sites in deep wells in regions where the HLW is now held in temporary storage. The aim of long-term investigations into HLW disposal is to evaluate geological prerequisites for regional HLW repositories.

  17. International Collaboration Activities in Different Geologic Disposal Environments

    SciTech Connect (OSTI)

    Birkholzer, Jens

    2015-09-01

    This report describes the current status of international collaboration regarding geologic disposal research in the Used Fuel Disposition (UFD) Campaign. Since 2012, in an effort coordinated by Lawrence Berkeley National Laboratory, UFD has advanced active collaboration with several international geologic disposal programs in Europe and Asia. Such collaboration allows the UFD Campaign to benefit from a deep knowledge base with regards to alternative repository environments developed over decades, and to utilize international investments in research facilities (such as underground research laboratories), saving millions of R&D dollars that have been and are being provided by other countries. To date, UFDs International Disposal R&D Program has established formal collaboration agreements with five international initiatives and several international partners, and national lab scientists associated with UFD have conducted specific collaborative R&D activities that align well with its R&D priorities.

  18. Used Fuel Disposal in Crystalline Rocks. FY15 Progress Report

    SciTech Connect (OSTI)

    Wang, Yifeng

    2015-08-20

    The objective of the Crystalline Disposal R&D Work Package is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and computational capabilities to evaluate various disposal concepts in such media. Chapter headings are as follows: Fuel matrix degradation model and its integration with performance assessments, Investigation of thermal effects on the chemical behavior of clays, Investigation of uranium diffusion and retardation in bentonite, Long-term diffusion of U(VI) in bentonite: dependence on density, Sorption and desorption of plutonium by bentonite, Dissolution of plutonium intrinsic colloids in the presence of clay and as a function of temperature, Laboratory investigation of colloid-facilitated transport of cesium by bentonite colloids in a crystalline rock system, Development and demonstration of discrete fracture network model, Fracture continuum model and its comparison with discrete fracture network model.

  19. Earth melter and method of disposing of feed materials

    DOE Patents [OSTI]

    Chapman, C.C.

    1994-10-11

    An apparatus, and method of operating the apparatus is described, wherein a feed material is converted into a glassified condition for subsequent use or disposal. The apparatus is particularly useful for disposal of hazardous or noxious waste materials which are otherwise either difficult or expensive to dispose of. The apparatus is preferably constructed by excavating a melt zone in a quantity of soil or rock, and lining the melt zone with a back fill material if refractory properties are needed. The feed material is fed into the melt zone and, preferably, combusted to an ash, whereupon the heat of combustion is used to melt the ash to a molten condition. Electrodes may be used to maintain the molten feed material in a molten condition, and to maintain homogeneity of the molten materials. 3 figs.

  20. Earth melter and method of disposing of feed materials

    DOE Patents [OSTI]

    Chapman, Christopher C. (Richland, WA)

    1994-01-01

    An apparatus, and method of operating the apparatus, wherein a feed material is converted into a glassified condition for subsequent use or disposal. The apparatus is particularly useful for disposal of hazardous or noxious waste materials which are otherwise either difficult or expensive to dispose of. The apparatus is preferably constructed by excavating a melt zone in a quantity of soil or rock, and lining the melt zone with a back fill material if refractory properties are needed. The feed material is fed into the melt zone and, preferably, combusted to an ash, whereupon the heat of combustion is used to melt the ash to a molten condition. Electrodes may be used to maintain the molten feed material in a molten condition, and to maintain homogeneity of the molten materials.

  1. Classified Component Disposal at the Nevada National Security Site

    SciTech Connect (OSTI)

    Poling, J.; Arnold, P.; Saad, M.; DiSanza, F.; Cabble, K.

    2012-11-05

    The Nevada National Security Site (NNSS) has added the capability needed for the safe, secure disposal of non-nuclear classified components that have been declared excess to national security requirements. The NNSS has worked with U.S. Department of Energy, National Nuclear Security Administration senior leadership to gain formal approval for permanent burial of classified matter at the NNSS in the Area 5 Radioactive Waste Management Complex owned by the U.S. Department of Energy. Additionally, by working with state regulators, the NNSS added the capability to dispose non-radioactive hazardous and non-hazardous classified components. The NNSS successfully piloted the new disposal pathway with the receipt of classified materials from the Kansas City Plant in March 2012.

  2. Idaho CERCLA Disposal Facility Complex Waste Acceptance Criteria

    SciTech Connect (OSTI)

    W. Mahlon Heileson

    2006-10-01

    The Idaho Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Disposal Facility (ICDF) has been designed to accept CERCLA waste generated within the Idaho National Laboratory. Hazardous, mixed, low-level, and Toxic Substance Control Act waste will be accepted for disposal at the ICDF. The purpose of this document is to provide criteria for the quantities of radioactive and/or hazardous constituents allowable in waste streams designated for disposal at ICDF. This ICDF Complex Waste Acceptance Criteria is divided into four section: (1) ICDF Complex; (2) Landfill; (3) Evaporation Pond: and (4) Staging, Storage, Sizing, and Treatment Facility (SSSTF). The ICDF Complex section contains the compliance details, which are the same for all areas of the ICDF. Corresponding sections contain details specific to the landfill, evaporation pond, and the SSSTF. This document specifies chemical and radiological constituent acceptance criteria for waste that will be disposed of at ICDF. Compliance with the requirements of this document ensures protection of human health and the environment, including the Snake River Plain Aquifer. Waste placed in the ICDF landfill and evaporation pond must not cause groundwater in the Snake River Plain Aquifer to exceed maximum contaminant levels, a hazard index of 1, or 10-4 cumulative risk levels. The defined waste acceptance criteria concentrations are compared to the design inventory concentrations. The purpose of this comparison is to show that there is an acceptable uncertainty margin based on the actual constituent concentrations anticipated for disposal at the ICDF. Implementation of this Waste Acceptance Criteria document will ensure compliance with the Final Report of Decision for the Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13. For waste to be received, it must meet the waste acceptance criteria for the specific disposal/treatment unit (on-Site or off-Site) for which it is destined.

  3. Maintenance Guide for DOE Low-Level Waste Disposal Facility

    Office of Environmental Management (EM)

    4 G Approved: XX-XX-XX IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses U.S. DEPARTMENT OF ENERGY DOE G 435.1-4 i (and ii) DRAFT XX-XX-XX LLW Maintenance Guide Revision 0, XX-XX-XX Maintenance Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses CONTENTS 1. INTRODUCTION . . . . . . . . . . . . . . . . . . .

  4. 2009 Performance Assessment for the Saltstone Disposal Facility

    Broader source: Energy.gov [DOE]

    This Performance Assessment (PA) for the Savannah River Site (SRS) was prepared to support the operation and eventual closure of the Saltstone Disposal Facility (SDF). This PA was prepared to demonstrate compliance with the pertinent requirements of the United States Department of Energy (DOE) Order 435.1, Change 1, Radioactive Waste Management, Chapter IV, and Title 10, of the Code of Federal Regulations (CFR) Part 61, Licensing Requirements for Land Disposal of Radioactive Waste, Subpart C as required by the Ronald W. Reagan National Defense Authorization Act (NDAA) for Fiscal Year 2005, Section 3116. [DOE O 435.1-1, 10 CFR 61, NDAA_3116

  5. Evaluate disposable sample chips and complete the (Technical Report) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Evaluate disposable sample chips and complete the Citation Details In-Document Search Title: Evaluate disposable sample chips and complete the × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to utilize additional information resources in energy science and technology. A paper copy of this document is also

  6. Laboratory to demolish excavation enclosures at Material Disposal Area B

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    near DP road Excavation enclosures at MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  7. Laboratory to demolish excavation enclosures at Material Disposal Area B

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    near DP Road Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  8. Laboratory to demolish excavation enclosures at Material Disposal Area B

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    near DP Road Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  9. INERT-MATRIX FUEL: ACTINIDE ''BURINGIN'' AND DIRECT DISPOSAL

    SciTech Connect (OSTI)

    Rodney C. Ewing; Lumin Wang

    2002-10-30

    Excess actinides result from the dismantlement of nuclear weapons (Pu) and the reprocessing of commercial spent nuclear fuel (mainly 241 Am, 244 Cm and 237 Np). In Europe, Canada and Japan studies have determined much improved efficiencies for burnup of actinides using inert-matrix fuels. This innovative approach also considers the properties of the inert-matrix fuel as a nuclear waste form for direct disposal after one-cycle of burn-up. Direct disposal can considerably reduce cost, processing requirements, and radiation exposure to workers.

  10. D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE

    Office of Environmental Management (EM)

    2 10 CFR Ch. X (1-1-12 Edition) Pt. 1022 D11 WASTE DISPOSAL FACILITIES FOR TRANSURANIC WASTE Siting, construction or expansion, and op- eration of disposal facilities for transuranic (TRU) waste and TRU mixed waste (TRU waste also containing hazardous waste as designated in 40 CFR part 261). D12 INCINERATORS Siting, construction, and operation of in- cinerators, other than research and develop- ment incinerators or incinerators for non- hazardous solid waste (as designated in 40 CFR 261.4(b)).

  11. A Critical Step Toward Sustainable Nuclear Fuel Disposal | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy A Critical Step Toward Sustainable Nuclear Fuel Disposal A Critical Step Toward Sustainable Nuclear Fuel Disposal January 26, 2012 - 2:30pm Addthis Secretary Chu Secretary Chu Former Secretary of Energy The Blue Ribbon Commission on America's Nuclear Future was formed at the direction of the President to conduct a comprehensive review of polices for managing the back end of the nuclear fuel cycle. If we are going to ensure that the United States remains at the forefront of nuclear

  12. Microsoft Word - Appendix C_DisposalCellContents.doc

    Office of Legacy Management (LM)

    Disposal Cell Contents Table C-1. Contents of the Weldon Spring, Missouri, Disposal Cell U.S. Department of Energy Weldon Spring Site LTS&M Plan July 2005 Doc. No. S0079000 Page C-3 Work Zone Per WP437 and Material Description Cell Placement Considerations Occupied Cell Volume (cy) Raffinate Pits Work Zone CSS Grout Produced in CSS Plant and pumped to cell. Volume as determined at the plant. 188,443.00 Raffinate Pit 4 residual sludge Stabilized in situ with grout then mixed with TSA

  13. CALiPER Special Summary Report: Retail Replacement Lamp Testing

    SciTech Connect (OSTI)

    2011-04-01

    CALiPER testing has evaluated many products for commercial lighting markets and found some excellent performers. However, many of these are not available on the retail market. This special testing was undertaken to identify and test solid-state lighting (SSL) replacement lamp products that are available to the general public through retail stores and websites.

  14. Replacing the whole barrel of oil with plants and microbes

    ScienceCinema (OSTI)

    Simmons, Blake

    2014-06-24

    In this May 13, 2013 talk, Blake Simmons discusses how scientists are exploring how plants and microbes can be used to replace many of the everyday goods we use that are derived from petroleum. To watch the entire entire Science at the Theater event, in which seven of our scientists present BIG ideas in eight minutes each.

  15. CALiPER Exploratory Study Retail Replacement Lamps – 2011

    SciTech Connect (OSTI)

    2012-04-02

    In 2010, CALiPER conducted a study on LED replacement lamps found in retail stores. The results were less than satisfactory, and many products were classified as being unlikely to meet consumer expectations. In November 2011, CALiPER purchased a new sample of products for a follow-up study, with the intent of characterizing the progress of this essential market segment.

  16. Measure Guideline. Wood Window Repair, Rehabilitation, and Replacement

    SciTech Connect (OSTI)

    Baker, P.; Eng, P.

    2012-12-01

    This measure guideline provides information and guidance on rehabilitating, retrofitting, and replacing existing window assemblies in residential construction. The intent is to provide information regarding means and methods to improve the energy and comfort performance of existing wood window assemblies in a way that takes into consideration component durability, in-service operation, and long term performance of the strategies.

  17. Replacing the whole barrel of oil with plants and microbes

    SciTech Connect (OSTI)

    Simmons, Blake

    2013-05-29

    In this May 13, 2013 talk, Blake Simmons discusses how scientists are exploring how plants and microbes can be used to replace many of the everyday goods we use that are derived from petroleum. To watch the entire entire Science at the Theater event, in which seven of our scientists present BIG ideas in eight minutes each.

  18. HVAC & Building Management Control System Energy Efficiency Replacements

    SciTech Connect (OSTI)

    Hernandez, Adriana

    2012-09-21

    The project objective was the replacement of an aging, un-repairable HVAC system which has grown inefficient and a huge energy consumer with low energy and efficient HVAC units, and installation of energy efficient building control technologies at City's YMCA Community Center.

  19. Replacement of alloy 800H superheated steam line

    SciTech Connect (OSTI)

    Barbier, R.A.; Bullock, J.W. [Sterling Chemicals, Texas City, TX (United States)

    1996-07-01

    Sterling Chemicals utilizes alloy 800HT (UNS N08811) piping for superheated steam service in its styrene dehydrogenation unit. An engineering project to replace these lines was recently completed. Material acquisition, shop fabrication, inspection requirements, and field erection will be highlighted in this paper.

  20. Selection and Implementation of a Replacement Cutting Tool Selection Application

    SciTech Connect (OSTI)

    Rice, Gordon

    2008-10-06

    A new commercial cutting tool software package replaced an internally created legacy system. This report describes the issues that surfaced during the migration and installation of the commercial package and the solutions employed. The primary issues discussed are restructuring the data between two drastically different database schemas and the creation of individual component graphics.

  1. ARP/wARP and molecular replacement: the next generation

    SciTech Connect (OSTI)

    Cohen, Serge X. Ben Jelloul, Marouane; Long, Fei; Vagin, Alexei; Knipscheer, Puck; Lebbink, Joyce; Sixma, Titia K.; Lamzin, Victor S.; Murshudov, Garib N.; Perrakis, Anastassis

    2008-01-01

    A systematic test shows how ARP/wARP deals with automated model building for structures that have been solved by molecular replacement. A description of protocols in the flex-wARP control system and studies of two specific cases are also presented. Automatic iterative model (re-)building, as implemented in ARP/wARP and its new control system flex-wARP, is particularly well suited to follow structure solution by molecular replacement. More than 100 molecular-replacement solutions automatically solved by the BALBES software were submitted to three standard protocols in flex-wARP and the results were compared with final models from the PDB. Standard metrics were gathered in a systematic way and enabled the drawing of statistical conclusions on the advantages of each protocol. Based on this analysis, an empirical estimator was proposed that predicts how good the final model produced by flex-wARP is likely to be based on the experimental data and the quality of the molecular-replacement solution. To introduce the differences between the three flex-wARP protocols (keeping the complete search model, converting it to atomic coordinates but ignoring atom identities or using the electron-density map calculated from the molecular-replacement solution), two examples are also discussed in detail, focusing on the evolution of the models during iterative rebuilding. This highlights the diversity of paths that the flex-wARP control system can employ to reach a nearly complete and accurate model while actually starting from the same initial information.

  2. Accident Investigation of the February 7, 2013, Scissor Lift Accident in the West Hackberry Brine Tank-14 Resulting in Injury, Strategic Petroleum Reserve West Hackberry, LA

    Broader source: Energy.gov [DOE]

    On February 15, 2013, an Accident Investigation Board (the Board) was appointed to investigate an accident that resulted in serious injuries caused when a scissor lift tipped over in Brine Tank-14 (WHT-14) at the Strategic Petroleum Reserve, West Hackberry, Louisiana, site on February 7, 2013. The Board’s responsibilities have been completed with respect to this investigation. The analysis and the identification of the direct cause, root causes, contributing causes, and judgments of need resulting from this investigation were performed in accordance with the Department of Energy (DOE) Order 225.1B, Accident Investigations.

  3. Deep Borehole Disposal Remediation Costs for Off-Normal Outcomes

    SciTech Connect (OSTI)

    Finger, John T.; Cochran, John R.; Hardin, Ernest

    2015-08-17

    This memo describes rough-order-of-magnitude (ROM) cost estimates for a set of off-normal (accident) scenarios, as defined for two waste package emplacement method options for deep borehole disposal: drill-string and wireline. It summarizes the different scenarios and the assumptions made for each, with respect to fishing, decontamination, remediation, etc.

  4. Integrated Disposal Facility FY 2012 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Kerisit, Sebastien N.; Krogstad, Eirik J.; Burton, Sarah D.; Bjornstad, Bruce N.; Freedman, Vicky L.; Cantrell, Kirk J.; Snyder, Michelle MV; Crum, Jarrod V.; Westsik, Joseph H.

    2013-03-29

    PNNL is conducting work to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility for Hanford immobilized low-activity waste (ILAW). Before the ILAW can be disposed, DOE must conduct a performance assessment (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program, PNNL is implementing a strategy, consisting of experimentation and modeling, to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. Key activities in FY12 include upgrading the STOMP/eSTOMP codes to do near-field modeling, geochemical modeling of PCT tests to determine the reaction network to be used in the STOMP codes, conducting PUF tests on selected glasses to simulate and accelerate glass weathering, developing a Monte Carlo simulation tool to predict the characteristics of the weathered glass reaction layer as a function of glass composition, and characterizing glasses and soil samples exhumed from an 8-year lysimeter test. The purpose of this report is to summarize the progress made in fiscal year (FY) 2012 and the first quarter of FY 2013 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of LAW glasses.

  5. Combination gas producing and waste-water disposal well

    DOE Patents [OSTI]

    Malinchak, Raymond M.

    1984-01-01

    The present invention is directed to a waste-water disposal system for use in a gas recovery well penetrating a subterranean water-containing and methane gas-bearing coal formation. A cased bore hole penetrates the coal formation and extends downwardly therefrom into a further earth formation which has sufficient permeability to absorb the waste water entering the borehole from the coal formation. Pump means are disposed in the casing below the coal formation for pumping the water through a main conduit towards the water-absorbing earth formation. A barrier or water plug is disposed about the main conduit to prevent water flow through the casing except for through the main conduit. Bypass conduits disposed above the barrier communicate with the main conduit to provide an unpumped flow of water to the water-absorbing earth formation. One-way valves are in the main conduit and in the bypass conduits to provide flow of water therethrough only in the direction towards the water-absorbing earth formation.

  6. Remote-Handled Low-Level Waste (RHLLW) Disposal Project Code of Record

    SciTech Connect (OSTI)

    S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

    2010-10-01

    The Remote-Handled Low-Level Waste Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of fiscal year 2015). Development of a new onsite disposal facility, the highest ranked alternative, will provide necessary remote handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability.

  7. Special Analysis: Revision of Saltstone Vault 4 Disposal Limits (U)

    SciTech Connect (OSTI)

    Cook, J

    2005-05-26

    New disposal limits have been computed for Vault 4 of the Saltstone Disposal Facility based on several revisions to the models in the existing Performance Assessment and the Special Analysis issued in 2002. The most important changes are the use of a more rigorous groundwater flow and transport model, and consideration of radon emanation. Other revisions include refinement of the aquifer mesh to more accurately model the footprint of the vault, a new plutonium chemistry model accounting for the different transport properties of oxidation states III/IV and V/VI, use of variable infiltration rates to simulate degradation of the closure system, explicit calculation of gaseous releases and consideration of the effects of settlement and seismic activity on the vault structure. The disposal limits have been compared with the projected total inventory expected to be disposed in Vault 4. The resulting sum-of-fractions of the 1000-year disposal limits is 0.2, which indicates that the performance objectives and requirements of DOE 435.1 will not be exceeded. This SA has not altered the conceptual model (i.e., migration of radionuclides from the Saltstone waste form and Vault 4 to the environment via the processes of diffusion and advection) of the Saltstone PA (MMES 1992) nor has it altered the conclusions of the PA (i.e., disposal of the proposed waste in the SDF will meet DOE performance measures). Thus a PA revision is not required and this SA serves to update the disposal limits for Vault 4. In addition, projected doses have been calculated for comparison with the performance objectives laid out in 10 CFR 61. These doses are 0.05 mrem/year to a member of the public and 21.5 mrem/year to an inadvertent intruder in the resident scenario over a 10,000-year time-frame, which demonstrates that the 10 CFR 61 performance objectives will not be exceeded. This SA supplements the Saltstone PA and supersedes the two previous SAs (Cook et al. 2002; Cook and Kaplan 2003).

  8. UMTRA project disposal cell cover biointrusion sensitivity assessment, Revision 1

    SciTech Connect (OSTI)

    1995-10-01

    This study provides an analysis of potential changes that may take place in a Uranium Mill Tailings Remedial Action (UMTRA) Project disposal cell cover system as a result of plant biointrusion. Potential changes are evaluated by performing a sensitivity analysis of the relative impact of root penetrations on radon flux out of the cell cover and/or water infiltration into the cell cover. Data used in this analysis consist of existing information on vegetation growth on selected cell cover systems and information available from published studies and/or other available project research. Consistent with the scope of this paper, no new site-specific data were collected from UMTRA Project sites. Further, this paper does not focus on the issue of plant transport of radon gas or other contaminants out of the disposal cell cover though it is acknowledged that such transport has the potential to be a significant pathway for contaminants to reach the environment during portions of the design life of a disposal cell where plant growth occurs. Rather, this study was performed to evaluate the effects of physical penetration and soil drying caused by plant roots that have and are expected to continue to grow in UMTRA Project disposal cell covers. An understanding of the biological and related physical processes that take place within the cover systems of the UMTRA Project disposal cells helps the U.S. Department of Energy (DOE) determine if the presence of a plant community on these cells is detrimental, beneficial, or of mixed value in terms of the cover system`s designed function. Results of this investigation provide information relevant to the formulation of a vegetation control policy.

  9. Update on cavern disposal of NORM-contaminated oil field wastes.

    SciTech Connect (OSTI)

    Veil, J. A.

    1998-09-22

    Some types of oil and gas production and processing wastes contain naturally occurring radioactive material (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. Argonne National Laboratory has previously evaluated the feasibility, legality, risk and economics of disposing of nonhazardous oil field wastes, other than NORM waste, in salt caverns. Cavern disposal of nonhazardous oil field waste, other than NORM waste, is occurring at four Texas facilities, in several Canadian facilities, and reportedly in Europe. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns as well. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, a review of federal regulations and regulations from several states indicated that there are no outright prohibitions against NORM disposal in salt caverns or other Class II wells, except for Louisiana which prohibits disposal of radioactive wastes or other radioactive materials in salt domes. Currently, however, only Texas and New Mexico are working on disposal cavern regulations, and no states have issued permits to allow cavern disposal of NORM waste. On the basis of the costs currently charged for cavern disposal of nonhazardous oil field waste (NOW), NORM waste disposal in caverns is likely to be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

  10. Measure Guideline: Air Conditioner Diagnostics, Maintenance, and Replacement

    SciTech Connect (OSTI)

    Springer, D.; Dakin, B.

    2013-03-01

    This guideline responds to the need for an efficient means of identifying, diagnosing, and repairing faults in air conditioning systems in existing homes that are undergoing energy upgrades. Inadequate airflow due to constricted ducts or undersized filters, improper refrigerant charge, and other system defects can be corrected at a fraction of the cost of equipment replacement and can yield significant savings. The guideline presents a two-step approach to diagnostics and repair.

  11. Polypeptide having an amino acid replaced with N-benzylglycine

    DOE Patents [OSTI]

    Mitchell, Alexander R. (Livermore, CA); Young, Janis D. (Los Angeles, CA)

    1996-01-01

    The present invention relates to one or more polypeptides having useful biological activity in a mammal, which comprise: a polypeptide related to bradykinin of four to ten amino acid residues wherein one or more specific amino acids in the polypeptide chain are replaced with achiral N-benzylglycine. These polypeptide analogues have useful potent agonist or antagonist pharmacological properties depending upon the structure. A preferred polypeptide is (N-benzylglycine.sup.7)-bradykinin.

  12. OSRAM SYLVANIA Develops High-Efficiency LED Troffer Replacement

    Broader source: Energy.gov [DOE]

    With the help of DOE funding, OSRAM SYLVANIA is developing a high-efficiency LED 2'x2' troffer replacement that is expected to be commercially available in the spring of 2012 and to be cost-competitive with existing troffers of that size. It is projected to have a light output of up to 4,000 lumens, an efficacy of more than 100 lm/W, and a CCT of 3500K.

  13. Replacement-3 Wholesale Power Rate Schedule | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    3 Wholesale Power Rate Schedule Replacement-3 Wholesale Power Rate Schedule Area: Virginia, North Carolina, Tennessee, Georgia, Alabama, Mississippi, Kentucky, southern Illinois System: CU This rate schedule shall be available to public bodies and cooperatives ( any one of whom is hereinafter called the Customer) in Virginia, North Carolina, Tennessee, Georgia, Alabama, Mississippi, Kentucky and southern Illinois to whom power is provided pursuant to contracts between the Government and the

  14. COLLOQUIUM: Are Mushrooms the Next Polymers?: Growing Plastic Replacements

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    with Fungi | Princeton Plasma Physics Lab March 20, 2013, 4:15pm to 6:30pm Colloquia MBG Auditorium COLLOQUIUM: Are Mushrooms the Next Polymers?: Growing Plastic Replacements with Fungi Mr. Gavin McIntyre Ecovative Design LLC Colloquium Committee: The Princeton Plasma Physics Laboratory 2015-2016 Colloquium Committee is comprised of the following people. Please feel free to contact them by e-mail regarding any possible speakers or topics for future colloquia. Carol Ann Austin,

  15. Window Replacement, Rehabilitation, & Repair Guides - Building America Top

    Broader source: Energy.gov (indexed) [DOE]

    Innovation | Department of Energy window repair.jpg This Top Innovation describes research by Building Science Corporation to determine that whole-house energy savings of up to 10% can be achieved through repair and rehabilitation of windows, potentially improving the energy efficiency of more than 5 million U.S. homes annually. The team developed a series of guides for homeowners and contractors that recommend various options for repairing or replacing old windows. The options include

  16. Estimates of the solubilities of waste element radionuclides in waste isolation pilot plant brines: A report by the expert panel on the source term

    SciTech Connect (OSTI)

    Hobart, D.E.; Bruton, C.J.; Millero, F.J.; Chou, I.M.; Trauth, K.M.; Anderson, D.R.

    1996-05-01

    Evaluation of the long-term performance of the WIPP includes estimation of the cumulative releases of radionuclide elements to the accessible environment. Nonradioactive lead is added because of the large quantity expected in WIPP wastes. To estimate the solubilities of these elements in WIPP brines, the Panel used the following approach. Existing thermodynamic data were used to identify the most likely aqueous species in solution through the construction of aqueous speciation diagrams. Existing thermodynamic data and expert judgment were used to identify potential solubility-limiting solid phases. Thermodynamic data were used to calculate the activities of the radionuclide aqueous species in equilibrium with each solid. Activity coefficients of the radionuclide-bearing aqueous species were estimated using Pitzer`s equations. These activity coefficients were then used to calculate the concentration of each radionuclide at the 0.1 and 0.9 fractiles. The 0.5 fractile was chosen to represent experimental data with activity coefficient corrections as described above. Expert judgment was used to develop the 0.0, 0.25, 0.75, and 1.0 fractiles by considering the sensitivity of solubility to the potential variability in the composition of brine and gas, and the extent of waste contaminants, and extending the probability distributions accordingly. The results were used in the 1991 and 1992 performance assessment calculations. 68 refs.

  17. Format and Content Guide for DOE Low-Level Waste Disposal Facility

    Office of Environmental Management (EM)

    Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility ... for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments ...

  18. Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth...

    Office of Environmental Management (EM)

    Review of the Proposed On-Site Waste Disposal Facility (OSWDF) at the Portsmouth Gaseous Diffusion Plant Why DOE-EM Did This Review The On-Site Waste Disposal Facility (OSWDF) is ...

  19. Format and Content Guide for DOE Low-Level Waste Disposal Facility...

    Office of Environmental Management (EM)

    Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility ... for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans CONTENTS ...

  20. U.S. Department of Energy Announces the Availability of Disposal...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Disposal Contracts for New Nuclear Reactors U.S. Department of Energy Announces the Availability of Disposal Contracts for New Nuclear Reactors October 31, 2008 - 4:47pm Addthis ...

  1. DOE Will Dispose of 34 Metric Tons of Plutonium by Turning it...

    National Nuclear Security Administration (NNSA)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home About Us Our History NNSA Timeline DOE Will Dispose of 34 Metric Tons ... DOE Will Dispose of 34 Metric Tons of ...

  2. Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound...

    Office of Environmental Management (EM)

    Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell Idaho Crews Overcome Challenges to Safely Dispose 1-Million-Pound Hot Cell American Recovery and Reinvestment...

  3. Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress

    Broader source: Energy.gov [DOE]

    The objective of the Crystalline Disposal R&D work is to advance our understanding of long-term disposal of used fuel in crystalline rocks and to develop necessary experimental and...

  4. Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress...

    Office of Scientific and Technical Information (OSTI)

    Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress. Citation Details In-Document Search Title: Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress. ...

  5. 16 TAC, part 1, chapter 3, rule 3.9 Disposal Wells | Open Energy...

    Open Energy Info (EERE)

    Disposal Wells Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- RegulationRegulation: 16 TAC, part 1, chapter 3, rule 3.9 Disposal WellsLegal...

  6. 42 U.S.C. 6901 - Solid Waste Disposal Act | Open Energy Information

    Open Energy Info (EERE)

    6901 - Solid Waste Disposal Act Jump to: navigation, search OpenEI Reference LibraryAdd to library Legal Document- StatuteStatute: 42 U.S.C. 6901 - Solid Waste Disposal ActLegal...

  7. Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)

    SciTech Connect (OSTI)

    Arnold, P.

    2012-10-31

    This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams.

  8. Interface control document between PUREX Plant Transition and Solid Waste Disposal Division

    SciTech Connect (OSTI)

    Carlson, A.B.

    1995-09-01

    The interfacing responsibilities regarding solid waste management are described for the Solid Waste Disposal Division and the PUREX Transition Organization.

  9. Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14)

    Office of Environmental Management (EM)

    R1 | Department of Energy Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14) R1 Investigations of Dual-Purpose Canister Direct Disposal Feasibility (FY14) R1 Results continue to support the earlier conclusion that direct disposal of DPCs is technically feasible, at least for some DPCs, and for some disposal concepts (geologic host media). Much of the work performed has reached a point where site-specific information would be needed for further resolution. Several

  10. Strategy for the Management and Disposal of Used Nuclear Fuel and

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    High-Level Radioactive Waste | Department of Energy Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste The Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste is a framework for moving toward a sustainable program to deploy an integrated system capable of transporting, storing, and disposing of used nuclear fuel

  11. River Protection Project (RPP) Tank Waste Retrieval and Disposal Mission Technical Baseline Summary Description

    SciTech Connect (OSTI)

    DOVALLE, O.R.

    1999-12-29

    This document is one of the several documents prepared by Lockheed Martin Hanford Corp. to support the U. S. Department of Energy's Tank Waste Retrieval and Disposal mission at Hanford. The Tank Waste Retrieval and Disposal mission includes the programs necessary to support tank waste retrieval; waste feed, delivery, storage, and disposal of immobilized waste; and closure of the tank farms.

  12. August 2015 Groundwater and Surface Water Sampling at the Tuba City, Arizona, Disposal Site

    Office of Legacy Management (LM)

    and Surface Water Sampling at the Tuba City, Arizona, Disposal Site November 2015 LMS/TUB/S00815 This page intentionally left blank U.S. Department of Energy DVP-August 2015, Tuba City, Arizona, Disposal Site November 2015 RIN 15087262 Page i Contents Sampling Event Summary ...............................................................................................................1 Tuba City, Arizona, Disposal Site, Sample Location Map

  13. Remote-Handled Low Level Waste Disposal Project Alternatives Analysis

    SciTech Connect (OSTI)

    David Duncan

    2010-10-01

    This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

  14. 1994 Characterization report for the state approved land disposal site

    SciTech Connect (OSTI)

    Swanson, L.C.

    1994-09-19

    This report summarizes the results of characterization activities at the proposed state-approved land disposal site (SALDS); it updates the original characterization report with studies completed since the first characterization report. The initial characterization report discusses studies from two characterization boreholes, 699-48-77A and 699-48-77B. This revision includes data from implementation of the Groundwater Monitoring Plan and the Aquifer Test Plan. The primary sources of data are two down-gradient groundwater monitoring wells, 699-48-77C and 699-48-77D, and aquifer testing of three zones in well 699-48-77C. The SALDS is located on the Hanford Site, approximately 183 m north of the 200 West Area on the north side of the 200 Areas Plateau. The SALDS is an infiltration basin proposed for disposal of treated effluents from the 200 Areas of Hanford.

  15. Waste-to-energy: Benefits beyond waste disposal

    SciTech Connect (OSTI)

    Charles, M.A.; Kiser, J.V.L. )

    1995-01-01

    More than 125 waste-to-energy plants operate in North America, providing dependable waste disposal for thousands of communities. But the benefits of waste-to-energy plants go beyond getting rid of the garbage. Here's a look at some of the economic, environmental, and societal benefits that waste-to-energy projects have brought to their communities. The reasons vary considerably as to why communities have selected waste-to-energy as a part of their waste management systems. Common on the lists in many communities are a variety of benefits beyond dependable waste disposal. A look at experiences in four communities reveals environmental, economic, energy, and societal benefits that the projects provide to the communities they serve.

  16. Report on Separate Disposal of Defense High- Level Radioactive Waste

    Office of Environmental Management (EM)

    on Separate Disposal of Defense High- Level Radioactive Waste March 2015 [This page left blank.] i EXECUTIVE SUMMARY Purpose This report considers whether a separate repository for high-level radioactive waste (HLW) resulting from atomic energy defense activities ("Defense HLW Repository") is "required" within the meaning of Section 8(b)(2) of the Nuclear Waste Policy Act of 1982 (NWPA). In 1985, the U.S. Department of Energy (DOE) and President Reagan considered this

  17. Subseabed Disposal Program. Annual report, January-December 1978

    SciTech Connect (OSTI)

    Talbert, D.M.

    1980-02-01

    This is the fifth annual report describing the progress and evaluating the status of the Subseabed Disposal Program (SDP), which was begun in June 1973. The program was initiated by Sandia Laboratories to explore the utility of stable, uniform, and relatively unproductive areas of the world as possible repositories for high-level nuclear wastes. The program, now international in scope, is currently focused on the stable submarine geologic formations under the deep oceans.

  18. Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    System - Energy Innovation Portal Storage Energy Storage Electricity Transmission Electricity Transmission Advanced Materials Advanced Materials Find More Like This Return to Search Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister System Oak Ridge National Laboratory Contact ORNL About This Technology Publications: PDF Document Publication 11-G00239_ID2603 (2).pdf (847 KB) Technology Marketing Summary Researchers at ORNL have developed an integrated system that

  19. NNSA Reaches LEU Disposal Milestone | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration LEU Disposal Milestone | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs

  20. Anaerobic digestion as a waste disposal option for American Samoa

    SciTech Connect (OSTI)

    Rivard, C

    1993-01-01

    Tuna sludge and municipal solid waste (MSW) generated on Tutuila Island, American Samoa, represent an ongoing disposal problem as well as an emerging opportunity for use in renewable fuel production. This research project focuses on the biological conversion of the organic fraction of these wastes to useful products including methane and fertilizer-grade residue through anaerobic high solids digestion. In this preliminary study, the anaerobic bioconversion of tuna sludge with MSW appears promising.

  1. The NUMO Strategy for HLW and TRU Waste Disposal

    SciTech Connect (OSTI)

    Kitayama, K.; Oda, Y. [Nuclear Waste Management Organization of Japan (NUMO), Tokyo (Japan)

    2008-07-01

    Shortly after the Nuclear Waste Management Organization of Japan (NUMO) was established, we initiated an open call to all municipalities, requesting volunteers to host a repository for vitrified HLW. The first volunteer applied for a preliminary literature survey phase last January but, unfortunately, it withdrew the application in April. This failure provided an invaluable lesson for both the relevant authorities and NUMO; subsequently the Atomic Energy Commission of Japan and associated organizations are examining a support plan to back up NUMO's open solicitation. On another front, a recent amendment of 'The Specified Radioactive Waste Final Disposal Act' also allocates specific 'TRU' waste for deep geological disposal, requiring a demonstration of safety to a similar level as that for HLW. To implement the radioactive waste disposal project, NUMO has developed a methodology appropriate to our specific boundary conditions - the NUMO Structured Approach. This takes into account, in particular, our need to balance competing goals, such as operational safety, post-closure safety and cost, during repository tailoring to specific sites. The most important challenge for NUMO is, however, to attract volunteers. We believe that our open and structured R and D program is critical to demonstrate technical competence which, in turn, enhances the credibility of our various public relations activities. (authors)

  2. Disposal of Draeger Tubes at Savannah River Site

    SciTech Connect (OSTI)

    Malik, N.P.

    2000-10-13

    The Savannah River Site (SRS) is a Department of Energy (DOE) facility located in Aiken, South Carolina that is operated by the Westinghouse Savannah River Company (WSRC). At SRS Draeger tubes are used to identify the amount and type of a particular chemical constituent in the atmosphere. Draeger tubes rely on a chemical reaction to identify the nature and type of a particular chemical constituent in the atmosphere. Disposal practices for these tubes were identified by performing a hazardous waste evaluation per the Resource Conservation and Recovery Act (RCRA). Additional investigations were conducted to provide guidance for their safe handling, storage and disposal. A list of Draeger tubes commonly used at SRS was first evaluated to determine if they contained any material that could render them as a RCRA hazardous waste. Disposal techniques for Draeger tubes that contained any of the toxic contaminants listed in South Carolina Hazardous Waste Management Regulations (SCHWMR) R.61-79. 261.24 (b) and/or contained an acid in the liquid form were addressed.

  3. Proceedings of the 1981 subseabed disposal program. Annual workshop

    SciTech Connect (OSTI)

    Not Available

    1982-01-01

    The 1981 Annual Workshop was the twelfth meeting of the principal investigators and program management personnel participating in the Subseabed Disposal Program (SDP). The first workshop was held in June 1973, to address the development of a program (initially known as Ocean Basin Floors Program) to assess the deep sea disposal of nuclear wastes. Workshops were held semi-annually until late 1977. Since November 1977, the workshops have been conducted following the end of each fiscal year so that the program participants could review and critique the total scope of work. This volume contains a synopsis, as given by each Technical Program Coordinator, abstracts of each of the talks, and copies of the visual materials, as presented by each of the principal investigators, for each of the technical elements of the SDP for the fiscal year 1981. The talks were grouped under the following categories; general topics; site studies; thermal response studies; emplacement studies; systems analysis; chemical response studies; biological oceanography studies; physical oceanographic studies; instrumentation development; transportation studies; social environment; and international seabed disposal.

  4. Pyramiding tumuli waste disposal site and method of construction thereof

    DOE Patents [OSTI]

    Golden, Martin P. (Hamburg, NY)

    1989-01-01

    An improved waste disposal site for the above-ground disposal of low-level nuclear waste as disclosed herein. The disposal site is formed from at least three individual waste-containing tumuli, wherein each tumuli includes a central raised portion bordered by a sloping side portion. Two of the tumuli are constructed at ground level with adjoining side portions, and a third above-ground tumulus is constructed over the mutually adjoining side portions of the ground-level tumuli. Both the floor and the roof of each tumulus includes a layer of water-shedding material such as compacted clay, and the clay layer in the roofs of the two ground-level tumuli form the compacted clay layer of the floor of the third above-ground tumulus. Each tumulus further includes a shield wall, preferably formed from a solid array of low-level handleable nuclear wate packages. The provision of such a shield wall protects workers from potentially harmful radiation when higher-level, non-handleable packages of nuclear waste are stacked in the center of the tumulus.

  5. A critical comparison of ten disposable cup LCAs

    SciTech Connect (OSTI)

    Harst, Eugenie van der, E-mail: eugenie.vanderharst@wur.nl [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands); Potting, Jos, E-mail: jose.potting@wur.nl [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands) [Environmental Systems Analysis Group, Wageningen University, P.O. Box 47, NL-6700 AA Wageningen (Netherlands); Environmental Strategies Research (fms), KTH Royal Institute of Technology, SE-110 44 Stockholm (Sweden)

    2013-11-15

    Disposable cups can be made from conventional petro-plastics, bioplastics, or paperboard (coated with petro-plastics or bioplastics). This study compared ten life cycle assessment (LCA) studies of disposable cups with the aim to evaluate the robustness of their results. The selected studies have only one impact category in common, namely climate change with global warming potential (GWP) as its category indicator. Quantitative GWP results of the studies were closer examined. GWPs within and across each study show none of the cup materials to be consistently better than the others. Comparison of the absolute GWPs (after correction for the cup volume) also shows no consistent better or worse cup material. An evaluation of the methodological choices and the data sets used in the studies revealed their influence on the GWP. The differences in GWP can be attributed to a multitude of factors, i.e., cup material and weight, production processes, waste processes, allocation options, and data used. These factors basically represent different types of uncertainty. Sensitivity and scenario analyses provided only the influence of one factor at once. A systematic and simultaneous use of sensitivity and scenario analyses could, in a next research, result in more robust outcomes. -- Highlights: Conflicting results from life cycle assessment (LCA) on disposable cups GWP results of LCAs did not point to a best or worst cup material. Differences in GWP results are due to methodological choices and data sets used. Standardized LCA: transparency of LCA studies, but still different in approaches.

  6. The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan

    SciTech Connect (OSTI)

    DEFFENBAUGH, M.L.

    2000-08-01

    The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational disposal facility or disapproval to initiate construction of a new facility.''

  7. Electronic-type vacuum gauges with replaceable elements

    DOE Patents [OSTI]

    Edwards, Jr., David (7 Brown's La., Bellport, NY 11713)

    1984-01-01

    In electronic devices for measuring pressures in vacuum systems, the metal elements which undergo thermal deterioration are made readily replaceable by making them parts of a simple plug-in unit. Thus, in ionization gauges, the filament and grid or electron collector are mounted on the novel plug-in unit. In thermocouple pressure gauges, the heater and attached thermocouple are mounted on the plug-in unit. Plug-in units have been designed to function, alternatively, as ionization gauge and as thermocouple gauge, thus providing new gauges capable of measuring broader pressure ranges than is possible with either an ionization gauge or a thermocouple gauge.

  8. Electronic-type vacuum gauges with replaceable elements

    DOE Patents [OSTI]

    Edwards, D. Jr.

    1984-09-18

    In electronic devices for measuring pressures in vacuum systems, the metal elements which undergo thermal deterioration are made readily replaceable by making them parts of a simple plug-in unit. Thus, in ionization gauges, the filament and grid or electron collector are mounted on the novel plug-in unit. In thermocouple pressure gauges, the heater and attached thermocouple are mounted on the plug-in unit. Plug-in units have been designed to function, alternatively, as ionization gauge and as thermocouple gauge, thus providing new gauges capable of measuring broader pressure ranges than is possible with either an ionization gauge or a thermocouple gauge. 5 figs.

  9. New Feedstocks and Replacement Fuels - Future Energy for Mobility |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy Fuels - Future Energy for Mobility New Feedstocks and Replacement Fuels - Future Energy for Mobility Presentation given at DEER 2006, August 20-24, 2006, Detroit, Michigan. Sponsored by the U.S. DOE's EERE FreedomCar and Fuel Partnership and 21st Century Truck Programs. PDF icon 2006_deer_simnick.pdf More Documents & Publications Fuel-Cycle Energy and Emissions Analysis with the GREET Model Cross-cutting Technologies for Advanced Biofuels Well-to-Wheels Analysis of

  10. Integrated Disposal Facility FY2010 Glass Testing Summary Report

    SciTech Connect (OSTI)

    Pierce, Eric M.; Bacon, Diana H.; Kerisit, Sebastien N.; Windisch, Charles F.; Cantrell, Kirk J.; Valenta, Michelle M.; Burton, Sarah D.; Serne, R Jeffrey; Mattigod, Shas V.

    2010-09-30

    Pacific Northwest National Laboratory was contracted by Washington River Protection Solutions, LLC to provide the technical basis for estimating radionuclide release from the engineered portion of the disposal facility (e.g., source term). Vitrifying the low-activity waste at Hanford is expected to generate over 1.6 105 m3 of glass (Puigh 1999). The volume of immobilized low-activity waste (ILAW) at Hanford is the largest in the DOE complex and is one of the largest inventories (approximately 0.89 1018 Bq total activity) of long-lived radionuclides, principally 99Tc (t1/2 = 2.1 105), planned for disposal in a low-level waste (LLW) facility. Before the ILAW can be disposed, DOE must conduct a performance assessement (PA) for the Integrated Disposal Facility (IDF) that describes the long-term impacts of the disposal facility on public health and environmental resources. As part of the ILAW glass testing program PNNL is implementing a strategy, consisting of experimentation and modeling, in order to provide the technical basis for estimating radionuclide release from the glass waste form in support of future IDF PAs. The purpose of this report is to summarize the progress made in fiscal year (FY) 2010 toward implementing the strategy with the goal of developing an understanding of the long-term corrosion behavior of low-activity waste glasses. The emphasis in FY2010 was the completing an evaluation of the most sensitive kinetic rate law parameters used to predict glass weathering, documented in Bacon and Pierce (2010), and transitioning from the use of the Subsurface Transport Over Reactive Multi-phases to Subsurface Transport Over Multiple Phases computer code for near-field calculations. The FY2010 activities also consisted of developing a Monte Carlo and Geochemical Modeling framework that links glass composition to alteration phase formation by 1) determining the structure of unreacted and reacted glasses for use as input information into Monte Carlo calculations, 2) compiling the solution data and alteration phases identified from accelerated weathering tests conducted with ILAW glass by PNNL and Viteous State Laboratory/Catholic University of America as well as other literature sources for use in geochemical modeling calculations, and 3) conducting several initial calculations on glasses that contain the four major components of ILAW-Al2O3, B2O3, Na2O, and SiO2.

  11. Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure

    Energy Savers [EERE]

    Plans | Department of Energy Closure Plans Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Closure Plans PDF icon Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans More Documents & Publications Maintenance Guide for DOE Low-Level Waste Disposal Facility Format and Content Guide for DOE Low-Level Waste Disposal Facility U.S. Department of

  12. Format and Content Guide for DOE Low-Level Waste Disposal Facility |

    Energy Savers [EERE]

    Department of Energy Format and Content Guide for DOE Low-Level Waste Disposal Facility Format and Content Guide for U.S. Department of Energy Low-Level Waste Disposal Facility Performance Assessments and Composite Analyses PDF icon Format and Content Guide for DOE Low-Level Waste Disposal Facility More Documents & Publications Maintenance Guide for DOE Low-Level Waste Disposal Facility Format and Content Guide for DOE Low-Level Waste Disposal Facility Closure Plans LFRG Execution Plan

  13. 12/2000 Low-Level Waste Disposal Capacity Report Version 2 | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Waste Disposition » 12/2000 Low-Level Waste Disposal Capacity Report Version 2 12/2000 Low-Level Waste Disposal Capacity Report Version 2 The purpose of this Report is to assess whether U.S. Department of Energy (DOE or the Department) disposal facilities have sufficient volumetric and radiological capacity to accommodate the low-level waste (LLW) and mixed low-level waste (MLLW) that the Department expects to dispose at these facilities. PDF icon 12/2000 Low-Level Waste Disposal

  14. Nuclear criticality safety assessment of the proposed CFC replacement coolants

    SciTech Connect (OSTI)

    Jordan, W.C.; Dyer, H.R.

    1993-12-01

    The neutron multiplication characteristics of refrigerant-114 (R-114) and proposed replacement coolants perfluorobutane (C{sub 4}F{sub 10}) and cycloperfluorobutane C{sub 4}F{sub 8}) have been compared by evaluating the infinite media multiplication factors of UF{sub 6}/H/coolant systems and by replacement calculations considering a 10-MW freezer/sublimer. The results of these comparisons demonstrate that R-114 is a neutron absorber, due to its chlorine content, and that the alternative fluorocarbon coolants are neutron moderators. Estimates of critical spherical geometries considering mixtures of UF{sub 6}/HF/C{sub 4}F{sub 10} indicate that the flourocarbon-moderated systems are large compared with water-moderated systems. The freezer/sublimer calculations indicate that the alternative coolants are more reactive than R-114, but that the reactivity remains significantly below the condition of water in the tubes, which was a limiting condition. Based on these results, the alternative coolants appear to be acceptable; however, several follow-up tasks have been recommended, and additional evaluation will be required on an individual equipment basis.

  15. Operational Readiness Review: Savannah River Replacement Tritium Facility

    SciTech Connect (OSTI)

    Not Available

    1993-02-01

    The Operational Readiness Review (ORR) is one of several activities to be completed prior to introducing tritium into the Replacement Tritium Facility (RTF) at the Savannah River Site (SRS). The Secretary of Energy will rely in part on the results of this ORR in deciding whether the startup criteria for RTF have been met. The RTF is a new underground facility built to safely service the remaining nuclear weapons stockpile. At RTF, tritium will be unloaded from old components, purified and enriched, and loaded into new or reclaimed reservoirs. The RTF will replace an aging facility at SRS that has processed tritium for more than 35 years. RTF has completed construction and is undergoing facility startup testing. The final stages of this testing will require the introduction of limited amounts of tritium. The US Department of Energy (DOE) ORR was conducted January 19 to February 4, 1993, in accordance with an ORR review plan which was developed considering previous readiness reviews. The plan also considered the Defense Nuclear Facilities Safety Board (DNFSB) Recommendations 90-4 and 92-6, and the judgements of experienced senior experts. The review covered three major areas: (1) Plant and Equipment Readiness, (2) Personnel Readiness, and (3) Management Systems. The ORR Team was comprised of approximately 30 members consisting of a Team Leader, Senior Safety Experts, and Technical Experts. The ORR objectives and criteria were based on DOE Orders, industry standards, Institute of Nuclear Power Operations guidelines, recommendations of external oversight groups, and experience of the team members.

  16. An integrated experimental and numerical study: Developing a reaction transport model that couples chemical reactions of mineral dissolution/precipitation with spatial and temporal flow variations in CO2/brine/rock systems

    Broader source: Energy.gov [DOE]

    Project objectives: Generate and characterize mineral dissolution/precipitation reactions in supercritical CO2/brine/rock systems under pressure-temperature-chemistry conditions resembling CO2injection into EGS. Characterize three-dimensional spatial and temporal distributions of rock structures subject to mineral dissolution/precipitation processes by X-ray tomography, SEM imaging, and Microprobe analysis.

  17. How do I know if my RTUs are Efficient? When do I Replace or...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    How do I know if my RTUs are Efficient? When do I Replace or Retrofit them? How do I know if my RTUs are Efficient? When do I Replace or Retrofit them? December 2, 2015 - 3:05pm ...

  18. Webinar: The L Prize-Winning LED A19 Replacement-What Commercial...

    Energy Savers [EERE]

    The L Prize-Winning LED A19 Replacement-What Commercial Building OwnersOperators Can Expect in 2012 Webinar: The L Prize-Winning LED A19 Replacement-What Commercial Building ...

  19. CALiPER Benchmark Report: Performance of Halogen Incandescent MR16 Lamps and LED Replacement

    SciTech Connect (OSTI)

    Paget, M. L.; Lingard, R. D.; Myer, M. A.

    2008-11-01

    This benchmark report addresses the halogen MR16 lamp and its commercially available light-emitting diode (LED) replacements.

  20. The CPA Equation of State and an Activity Coefficient Model for Accurate Molar Enthalpy Calculations of Mixtures with Carbon Dioxide and Water/Brine

    SciTech Connect (OSTI)

    Myint, P. C.; Hao, Y.; Firoozabadi, A.

    2015-03-27

    Thermodynamic property calculations of mixtures containing carbon dioxide (CO2) and water, including brines, are essential in theoretical models of many natural and industrial processes. The properties of greatest practical interest are density, solubility, and enthalpy. Many models for density and solubility calculations have been presented in the literature, but there exists only one study, by Spycher and Pruess, that has compared theoretical molar enthalpy predictions with experimental data [1]. In this report, we recommend two different models for enthalpy calculations: the CPA equation of state by Li and Firoozabadi [2], and the CO2 activity coefficient model by Duan and Sun [3]. We show that the CPA equation of state, which has been demonstrated to provide good agreement with density and solubility data, also accurately calculates molar enthalpies of pure CO2, pure water, and both CO2-rich and aqueous (H2O-rich) mixtures of the two species. It is applicable to a wider range of conditions than the Spycher and Pruess model. In aqueous sodium chloride (NaCl) mixtures, we show that Duan and Suns model yields accurate results for the partial molar enthalpy of CO2. It can be combined with another model for the brine enthalpy to calculate the molar enthalpy of H2O-CO2-NaCl mixtures. We conclude by explaining how the CPA equation of state may be modified to further improve agreement with experiments. This generalized CPA is the basis of our future work on this topic.