Sample records for waste licl salt

  1. Management of Salt Waste from Electrochemical Processing of Used Nuclear Fuel

    SciTech Connect

    Michael F. Simpson; Michael N. Patterson; Joon Lee; Yifeng Wang; Joshua Versey; Ammon Williams; Supathorn Phongikaroon; James Allensworth; Man-Sung Yim

    2013-10-01

    Electrochemical processing of used nuclear fuel involves operation of one or more cells containing molten salt electrolyte. Processing of the fuel results in contamination of the salt via accumulation of fission products and transuranic (TRU) actinides. Upon reaching contamination limits, the salt must be removed and either disposed or treated to remove the contaminants and recycled back to the process. During development of the Experimental Breeder Reactor-II spent fuel treatment process, waste salt from the electrorefiner was to be stabilized in a ceramic waste form and disposed of in a high-level waste repository. With the cancellation of the Yucca Mountain high-level waste repository, other options are now being considered. One approach that involves direct disposal of the salt in a geologic salt formation has been evaluated. While waste forms such as the ceramic provide near-term resistance to corrosion, they may not be necessary to ensure adequate performance of the repository. To improve the feasibility of direct disposal, recycling a substantial fraction of the useful salt back to the process equipment could minimize the volume of the waste. Experiments have been run in which a cold finger is used for this purpose to crystallize LiCl from LiCl/CsCl. If it is found to be unsuitable for transportation, the salt waste could also be immobilized in zeolite without conversion to the ceramic waste form.

  2. Management of salt waste from electrochemical processing of used nuclear fuel

    SciTech Connect

    Simpson, M.F.; Patterson, M.N. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415 (United States); Lee, J.; Wang, Y. [Sandia National Laboratory, Albuquerque, NM (United States); Versey, J.; Phongikaroon, S. [University of Idaho, Idaho Falls, ID (United States)

    2013-07-01

    Electrochemical processing of used nuclear fuel involves operation of one or more cells containing molten salt electrolyte. Processing of the fuel results in contamination of the salt via accumulation of fission products and transuranic (TRU) actinides. Upon reaching contamination limits, the salt must be removed and either disposed or treated to remove the contaminants and recycled back to the process. During development of the Experimental Breeder Reactor-II spent fuel treatment process, waste salt from the electro-refiner was to be stabilized in a ceramic waste form and disposed of in a high-level waste repository. With the cancellation of the Yucca Mountain high-level waste repository, other options are now being considered. One approach that involves direct disposal of the salt in a geologic salt formation has been evaluated. While waste forms such as the ceramic provide near-term resistance to corrosion, they may not be necessary to ensure adequate performance of the repository. To improve the feasibility of direct disposal, recycling a substantial fraction of the useful salt back to the process equipment could minimize the volume of the waste. Experiments have been run in which a cold finger is used for this purpose to crystallize LiCl from LiCl/CsCl. If it is found to be unsuitable for transportation, the salt waste could also be immobilized in zeolite without conversion to the ceramic waste form. (authors)

  3. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

    E-print Network

    Napp, Nils

    Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan Prepared. The Order, at paragraph 22, requires the Permittees to submit a WIPP Nitrate Salt Bearing Waste Container Isolation Plan (Plan) for identified nitrate salt bearing waste disposed in the Waste Isolation Pilot Plant

  4. Viscosity and density of aqueous solutions of LiBr, LiCl, ZnBr[sub 2], CaCl[sub 2], and LiNO[sub 3]; 2: Two-salt solutions

    SciTech Connect

    Wimby, J.M.; Berntsson, T.S. (Chalmers Univ. of Technology, Gothenburg (Sweden). Dept. of Heat and Power Technology)

    1994-01-01

    Experimental data for the viscosity and density of the system LiBr + LiCl + H[sub 2]O, LiBr + LiNO[sub 3] + H[sub 2]O, LiBr + LiNO[sub 3] + H[sub 2]O, LiBr + CaCl[sub 2] + H[sub 2]O, and LiBr + ZnBr[sub 2] + H[sub 2]O are presented. The concentrations are three equally spaced salt mole ratios and five total salt:water ratios. The temperature ranges are 25--90 C for the viscosity and 20--70 C for the density.

  5. Organic waste processing using molten salt oxidation

    SciTech Connect

    Adamson, M. G., LLNL

    1998-03-01

    Molten Salt Oxidation (MSO) is a thermal means of oxidizing (destroying) the organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. The U. S. Department of Energy`s Office of Environmental Management (DOE/EM) is currently funding research that will identify alternatives to incineration for the treatment of organic-based mixed wastes. (Mixed wastes are defined as waste streams which have both hazardous and radioactive properties.) One such project is Lawrence Livermore National Laboratory`s Expedited Technology Demonstration of Molten Salt Oxidation (MSO). The goal of this project is to conduct an integrated demonstration of MSO, including off-gas and spent salt treatment, and the preparation of robust solid final forms. Livermore National Laboratory (LLNL) has constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are presently being performed under carefully controlled (experimental) conditions. The system consists of a MSO process vessel with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. In this paper we describe the integrated system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is to identify the most suitable waste streams and waste types for MSO treatment.

  6. Alternative Waste Forms for Electro-Chemical Salt Waste

    SciTech Connect

    Crum, Jarrod V.; Sundaram, S. K.; Riley, Brian J.; Matyas, Josef; Arreguin, Shelly A.; Vienna, John D.

    2009-10-28

    This study was undertaken to examine alternate crystalline (ceramic/mineral) and glass waste forms for immobilizing spent salt from the Advanced Fuel Cycle Initiative (AFCI) electrochemical separations process. The AFCI is a program sponsored by U.S. Department of Energy (DOE) to develop and demonstrate a process for recycling spent nuclear fuel (SNF). The electrochemical process is a molten salt process for the reprocessing of spent nuclear fuel in an electrorefiner and generates spent salt that is contaminated with alkali, alkaline earths, and lanthanide fission products (FP) that must either be cleaned of fission products or eventually replaced with new salt to maintain separations efficiency. Currently, these spent salts are mixed with zeolite to form sodalite in a glass-bonded waste form. The focus of this study was to investigate alternate waste forms to immobilize spent salt. On a mole basis, the spent salt is dominated by alkali and Cl with minor amounts of alkaline earth and lanthanides. In the study reported here, we made an effort to explore glass systems that are more compatible with Cl and have not been previously considered for use as waste forms. In addition, alternate methods were explored with the hope of finding a way to produce a sodalite that is more accepting of as many FP present in the spent salt as possible. This study was done to investigate two different options: (1) alternate glass families that incorporate increased concentrations of Cl; and (2) alternate methods to produce a mineral waste form.

  7. Disposal of NORM waste in salt caverns

    SciTech Connect

    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.

  8. Waste salt recovery, recycle, and destruction

    SciTech Connect

    Hickman, R.G.

    1992-12-01

    Starting in 1943 and continuing into the 1970s, radioactive wastes resulting from plutonium processing at Hanford were stored underground in 149 single shell tanks. Of these tanks, 66 are known or believedto be leaking, and over a period are believed to have leaked about 750,000 gal into the surrounding soil. The bulk of the aqueous solution has been removed and transferred to double shell tanks, none of which are leaking. The waste consists of 37 million gallons of salt cake and sludge. Most of the salt cake is sodium nitrate and other sodium salts. A substantial fraction of the sludge is sodium nitrate. Small amounts of the radionuclides are present in the sludge as oxides or hydroxides. In addition, some of the tanks contain organic compounds and ferrocyanide complexes, many of which have undergone radiolytic induced chemical changes during the years of storage. As part of the Hanford site remediation effort, the tank wastes must be removed, treated, and the residuals must be immobilized and disposed of in an environmentally acceptable manner. Removal methods of the waste from the tanks fall generally into three approaches: dry removal, slurry removal, and solution removed. The latter two methods are likely to result in some additional leakage to the surrounding soil, but that may be acceptable if the tank can be emptied and remediated before the leaked material permeates deeply into the soil. This effort includes three parts: salt splitting, acid separation, and destruction, with initial emphasis on salt splitting.

  9. Molten salt destruction of energetic waste materials

    DOEpatents

    Brummond, William A. (Livermore, CA); Upadhye, Ravindra S. (Pleasanton, CA); Pruneda, Cesar O. (Livermore, CA)

    1995-01-01

    A molten salt destruction process is used to treat and destroy energetic waste materials such as high explosives, propellants, and rocket fuels. The energetic material is pre-blended with a solid or fluid diluent in safe proportions to form a fluid fuel mixture. The fuel mixture is rapidly introduced into a high temperature molten salt bath. A stream of molten salt is removed from the vessel and may be recycled as diluent. Additionally, the molten salt stream may be pumped from the reactor, circulated outside the reactor for further processing, and delivered back into the reactor or cooled and circulated to the feed delivery system to further dilute the fuel mixture entering the reactor.

  10. Cementitious Stabilization of Mixed Wastes with High Salt Loadings

    SciTech Connect

    Spence, R.D.; Burgess, M.W.; Fedorov, V.V.; Downing, D.J.

    1999-04-01

    Salt loadings approaching 50 wt % were tolerated in cementitious waste forms that still met leach and strength criteria, addressing a Technology Deficiency of low salt loadings previously identified by the Mixed Waste Focus Area. A statistical design quantified the effect of different stabilizing ingredients and salt loading on performance at lower loadings, allowing selection of the more effective ingredients for studying the higher salt loadings. In general, the final waste form needed to consist of 25 wt % of the dry stabilizing ingredients to meet the criteria used and 25 wt % water to form a workable paste, leaving 50 wt % for waste solids. The salt loading depends on the salt content of the waste solids but could be as high as 50 wt % if all the waste solids are salt.

  11. Modeling Solute Thermokinetics in LiCI-KCI Molten Salt for Nuclear Waste Separation

    SciTech Connect

    Morgan, Dane; Eapen, Jacob

    2013-10-01

    Recovery of actinides is an integral part of a closed nuclear fuel cycle. Pyrometallurgical nuclear fuel recycling processes have been developed in the past for recovering actinides from spent metallic and nitride fuels. The process is essentially to dissolve the spent fuel in a molten salt and then extract just the actinides for reuse in a reactor. Extraction is typically done through electrorefining, which involves electrochemical reduction of the dissolved actinides and plating onto a cathode. Knowledge of a number of basic thermokinetic properties of salts and salt-fuel mixtures is necessary for optimizing present and developing new approaches for pyrometallurgical waste processing. The properties of salt-fuel mixtures are presently being studied, but there are so many solutes and varying concentrations that direct experimental investigation is prohibitively time consuming and expensive (particularly for radioactive elements like Pu). Therefore, there is a need to reduce the number of required experiments through modeling of salt and salt-fuel mixture properties. This project will develop first-principles-based molecular modeling and simulation approaches to predict fundamental thermokinetic properties of dissolved actinides and fission products in molten salts. The focus of the proposed work is on property changes with higher concentrations (up to 5 mol%) of dissolved fuel components, where there is still very limited experimental data. The properties predicted with the modeling will be density, which is used to assess the amount of dissolved material in the salt; diffusion coefficients, which can control rates of material transport during separation; and solute activity, which determines total solubility and reduction potentials used during electrorefining. The work will focus on La, Sr, and U, which are chosen to include the important distinct categories of lanthanides, alkali earths, and actinides, respectively. Studies will be performed using LiCl-KCl salt at the eutectic composition (58 mol% LiCl, 42 mol% KCl), which is used for treating spent EBR-II fuel. The same process being used for EBRII fuel is currently being studied for widespread international implementation. The methods will focus on first-principles and first- principles derived interatomic potential based simulations, primarily using molecular dynamics. Results will be validated against existing literature and parallel ongoing experimental efforts. The simulation results will be of value for interpreting experimental results, validating analytical models, and for optimizing waste separation by potentially developing new salt configurations and operating conditions.

  12. Delivery system for molten salt oxidation of solid waste

    DOEpatents

    Brummond, William A. (Livermore, CA); Squire, Dwight V. (Livermore, CA); Robinson, Jeffrey A. (Manteca, CA); House, Palmer A. (Walnut Creek, CA)

    2002-01-01

    The present invention is a delivery system for safety injecting solid waste particles, including mixed wastes, into a molten salt bath for destruction by the process of molten salt oxidation. The delivery system includes a feeder system and an injector that allow the solid waste stream to be accurately metered, evenly dispersed in the oxidant gas, and maintained at a temperature below incineration temperature while entering the molten salt reactor.

  13. Waste Isolation Pilot Plant Salt Decontamination Testing

    SciTech Connect

    Rick Demmer; Stephen Reese

    2014-09-01

    On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. At the request of WIPP’s operations contractor, Idaho National Laboratory (INL) personnel developed several methods of decontaminating WIPP salt, using surrogate contaminants and also americium (241Am). The effectiveness of the methods is evaluated qualitatively, and to the extent possible, quantitatively. One of the requirements of this effort was delivering initial results and recommendations within a few weeks. That requirement, in combination with the limited scope of the project, made in-depth analysis impractical in some instances. Of the methods tested (dry brushing, vacuum cleaning, water washing, strippable coatings, and mechanical grinding), the most practical seems to be water washing. Effectiveness is very high, and it is very easy and rapid to deploy. The amount of wastewater produced (2 L/m2) would be substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from the strippable coating and water washing coupons found no residual removable contamination. Thus, whatever is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System (PBS) proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.

  14. Mixed Waste Salt Encapsulation Using Polysiloxane - Final Report

    SciTech Connect

    Miller, C.M.; Loomis, G.G.; Prewett, S.W.

    1997-11-01

    A proof-of-concept experimental study was performed to investigate the use of Orbit Technologies polysiloxane grouting material for encapsulation of U.S. Department of Energy mixed waste salts leading to a final waste form for disposal. Evaporator pond salt residues and other salt-like material contaminated with both radioactive isotopes and hazardous components are ubiquitous in the DOE complex and may exceed 250,000,000 kg of material. Current treatment involves mixing low waste percentages (less than 10% by mass salt) with cement or costly thermal treatment followed by cementation to the ash residue. The proposed technology involves simple mixing of the granular salt material (with relatively high waste loadings-greater than 50%) in a polysiloxane-based system that polymerizes to form a silicon-based polymer material. This study involved a mixing study to determine optimum waste loadings and compressive strengths of the resultant monoliths. Following the mixing study, durability testing was performed on promising waste forms. Leaching studies including the accelerated leach test and the toxicity characteristic leaching procedure were also performed on a high nitrate salt waste form. In addition to this testing, the waste form was examined by scanning electron microscope. Preliminary cost estimates for applying this technology to the DOE complex mixed waste salt problem is also given.

  15. Salt disposal of heat-generating nuclear waste.

    SciTech Connect

    Leigh, Christi D. (Sandia National Laboratories, Carlsbad, NM); 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.

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

    Microsoft Academic Search

    Langton

    1998-01-01

    The direct grout alternative is a viable option for treatment\\/stabilization and disposal of salt waste containing Cs-137 concentrations of 1-3 Ci\\/gal. The composition of the direct grout salt solution is higher in sodium salts and contains up to a few hundred ppm Cs-137 more than the current reference salt solution. However it is still similar to the composition of the

  17. Alternative methods of salt disposal at the seven salt sites for a nuclear waste repository

    SciTech Connect

    Not Available

    1987-02-01

    This study discusses the various alternative salt management techniques for the disposal of excess mined salt at seven potentially acceptable nuclear waste repository sites: Deaf Smith and Swisher Counties, Texas; Richton and Cypress Creek Domes, Mississippi; Vacherie Dome, Louisiana; and Davis and Lavender Canyons, Utah. Because the repository development involves the underground excavation of corridors and waste emplacement rooms, in either bedded or domed salt formations, excess salt will be mined and must be disposed of offsite. The salt disposal alternatives examined for all the sites include commercial use, ocean disposal, deep well injection, landfill disposal, and underground mine disposal. These alternatives (and other site-specific disposal methods) are reviewed, using estimated amounts of excavated, backfilled, and excess salt. Methods of transporting the excess salt are discussed, along with possible impacts of each disposal method and potential regulatory requirements. A preferred method of disposal is recommended for each potentially acceptable repository site. 14 refs., 5 tabs.

  18. Waste disposal in a German rock-salt mine

    Microsoft Academic Search

    1993-01-01

    A worked-out area of the operating Helibronn rock-salt mine is being used as a repository for fly-ash waste from incineration plants. The waste is packed in large bags, handled by fork-lifts, trucks, and cranes, and stacked 11-m-high. In addition insolubles from the re-saturation of brine for electrolysis using rock salt are stowed in bulk. Special care is taken to isolate

  19. Disposition of salt-waste from pyrochemical nuclear fuel processing

    Microsoft Academic Search

    Vance

    2007-01-01

    Waste salts from pyrochemical processing of nuclear fuel can be immobilised in sodalite if consolidated by hot isostatic pressing (HIP) at 750 deg. C\\/100 MPa in thick stainless steel 316 cans. Other canning materials for this purpose also look possible. Spodiosite-based waste forms do not look promising in terms of leach resistance and their incorporation of alkali ions and compatibility

  20. Molten salt treatment to minimize and optimize waste

    SciTech Connect

    Gat, U.; Crosley, S.M. [Oak Ridge National Lab., TN (United States); Gay, R.L. [Rockwell International Corp., Canoga Park, CA (United States)

    1993-07-01

    A combination molten salt oxidizer (MSO) and molten salt reactor (MSR) is described for treatment of waste. The MSO is proposed for contained oxidization of organic hazardous waste, for reduction of mass and volume of dilute waste by evaporation of the water. The NTSO residue is to be treated to optimize the waste in terms of its composition, chemical form, mixture, concentration, encapsulation, shape, size, and configuration. Accumulations and storage are minimized, shipments are sized for low risk. Actinides, fissile material, and long-lived isotopes are separated and completely burned or transmuted in an MSR. The MSR requires no fuel element fabrication, accepts the materials as salts in arbitrarily small quantities enhancing safety, security, and overall acceptability.

  1. Disposition of salt-waste from pyrochemical nuclear fuel processing

    SciTech Connect

    Vance, E.R. [Institute of Materials Science and Engineering, Australian Nuclear Science and Technology Organisation, Menai, NSW 2234 (Australia)

    2007-07-01

    Waste salts from pyrochemical processing of nuclear fuel can be immobilised in sodalite if consolidated by hot isostatic pressing (HIP) at {approx}750 deg. C/100 MPa in thick stainless steel 316 cans. Other canning materials for this purpose also look possible. Spodiosite-based waste forms do not look promising in terms of leach resistance and their incorporation of alkali ions and compatibility with other phases which could potentially accommodate fission products, such as NaZr{sub 2}(PO{sub 4}){sub 3} or alumino-phosphate glass. Chloro- or fluor-apatite-based waste forms however have been reported to successfully accommodate fission products and alkalis which would be derived from either chloride- or fluoride-based waste pyro-processing salts. The presence of 10 or 20 wt% of additional Whitlockite, Ca{sub 3}(PO{sub 4}){sub 2}, should allow chemical flexibility to maintain the same qualitative phase assemblage when there are variations in the waste feed and in the waste/precursor ratios. Experimental verification of incorporation of the full complement of waste salts and fission products is not yet complete however. Apatite-rich samples could likely be HIPed in Inconel 600 cans. Other candidate HIP canning materials such as Alloy 22 or Inconel 625 are under study by encapsulating them in the candidate waste form and studying their interaction or otherwise with the waste form. (author)

  2. Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

    SciTech Connect

    Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

    2003-02-25

    The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value.

  3. Molten salt processing of mixed wastes with offgas condensation

    SciTech Connect

    Cooper, J.F.; Brummond, W.; Celeste, J.; Farmer, J.; Hoenig, C.; Krikorian, O.H.; Upadhye, R. (Lawrence Livermore National Lab., CA (USA)); Gay, R.L.; Stewart, A.; Yosim, S. (Rockwell International Corp., Canoga Park, CA (USA). Energy Systems Group)

    1991-05-13

    We are developing an advanced process for treatment of mixed wastes in molten salt media at temperatures of 700--1000{degrees}C. Waste destruction has been demonstrated in a single stage oxidation process, with destruction efficiencies above 99.9999% for many waste categories. The molten salt provides a heat transfer medium, prevents thermal surges, and functions as an in situ scrubber to transform the acid-gas forming components of the waste into neutral salts and immobilizes potentially fugitive materials by a combination of particle wetting, encapsulation and chemical dissolution and solvation. Because the offgas is collected and assayed before release, and wastes containing toxic and radioactive materials are treated while immobilized in a condensed phase, the process avoids the problems sometimes associated with incineration processes. We are studying a potentially improved modification of this process, which treats oxidizable wastes in two stages: pyrolysis followed by catalyzed molten salt oxidation of the pyrolysis gases at ca. 700{degrees}C. 15 refs., 5 figs., 1 tab.

  4. Integrated demonstration of molten salt oxidation with salt recycle for mixed waste treatment

    SciTech Connect

    Hsu, P.C.

    1997-11-01

    Molten Salt Oxidation (MSO) is a thermal, nonflame process that has the inherent capability of completely destroying organic constituents of mixed wastes, hazardous wastes, and energetic materials while retaining inorganic and radioactive constituents in the salt. For this reason, MSO is considered a promising alternative to incineration for the treatment of a variety of organic wastes. Lawrence Livermore National Laboratory (LLNL) has prepared a facility and constructed an integrated pilot-scale MSO treatment system in which tests and demonstrations are performed under carefully controlled (experimental) conditions. The system consists of a MSO processor with dedicated off-gas treatment, a salt recycle system, feed preparation equipment, and equipment for preparing ceramic final waste forms. This integrated system was designed and engineered based on laboratory experience with a smaller engineering-scale reactor unit and extensive laboratory development on salt recycle and final forms preparation. In this paper we present design and engineering details of the system and discuss its capabilities as well as preliminary process demonstration data. A primary purpose of these demonstrations is identification of the most suitable waste streams and waste types for MSO treatment.

  5. Cerebral salt wasting after pituitary exploration and biopsy: case report.

    PubMed

    Andrews, B T; Fitzgerald, P A; Tyrell, J B; Wilson, C B

    1986-04-01

    We report a case of hyponatremia associated with volume depletion after pituitary exploration and biopsy. The presence of clinical dehydration precluded diagnosis of the syndrome of inappropriate secretion of antidiuretic hormone. The absence of a hypoadrenal state and the patient's response to volume reexpansion were consistent with a diagnosis of primary cerebral salt wasting. PMID:3703220

  6. Injector nozzle for molten salt destruction of energetic waste materials

    DOEpatents

    Brummond, William A. (Livermore, CA); Upadhye, Ravindra S. (Pleasanton, CA)

    1996-01-01

    An injector nozzle has been designed for safely injecting energetic waste materials, such as high explosives, propellants, and rocket fuels, into a molten salt reactor in a molten salt destruction process without premature detonation or back burn in the injection system. The energetic waste material is typically diluted to form a fluid fuel mixture that is injected rapidly into the reactor. A carrier gas used in the nozzle serves as a carrier for the fuel mixture, and further dilutes the energetic material and increases its injection velocity into the reactor. The injector nozzle is cooled to keep the fuel mixture below the decomposition temperature to prevent spontaneous detonation of the explosive materials before contact with the high-temperature molten salt bath.

  7. Novel waste printed circuit board recycling process with molten salt.

    PubMed

    Riedewald, Frank; Sousa-Gallagher, Maria

    2015-01-01

    The objective of the method was to prove the concept of a novel waste PCBs recycling process which uses inert, stable molten salts as the direct heat transfer fluid and, simultaneously, uses this molten salt to separate the metal products in either liquid (solder, zinc, tin, lead, etc.) or solid (copper, gold, steel, palladium, etc.) form at the operating temperatures of 450-470 °C. The PCB recovery reactor is essentially a U-shaped reactor with the molten salt providing a continuous fluid, allowing molten salt access from different depths for metal recovery. A laboratory scale batch reactor was constructed using 316L as suitable construction material. For safety reasons, the inert, stable LiCl-KCl molten salts were used as direct heat transfer fluid. Recovered materials were washed with hot water to remove residual salt before metal recovery assessment. The impact of this work was to show metal separation using molten salts in one single unit, by using this novel reactor methodology. •The reactor is a U-shaped reactor filled with a continuous liquid with a sloped bottom representing a novel reactor concept.•This method uses large PCB pieces instead of shredded PCBs as the reactor volume is 2.2 L.•The treated PCBs can be removed via leg B while the process is on-going. PMID:26150977

  8. Novel waste printed circuit board recycling process with molten salt

    PubMed Central

    Riedewald, Frank; Sousa-Gallagher, Maria

    2015-01-01

    The objective of the method was to prove the concept of a novel waste PCBs recycling process which uses inert, stable molten salts as the direct heat transfer fluid and, simultaneously, uses this molten salt to separate the metal products in either liquid (solder, zinc, tin, lead, etc.) or solid (copper, gold, steel, palladium, etc.) form at the operating temperatures of 450–470 °C. The PCB recovery reactor is essentially a U-shaped reactor with the molten salt providing a continuous fluid, allowing molten salt access from different depths for metal recovery. A laboratory scale batch reactor was constructed using 316L as suitable construction material. For safety reasons, the inert, stable LiCl–KCl molten salts were used as direct heat transfer fluid. Recovered materials were washed with hot water to remove residual salt before metal recovery assessment. The impact of this work was to show metal separation using molten salts in one single unit, by using this novel reactor methodology. • The reactor is a U-shaped reactor filled with a continuous liquid with a sloped bottom representing a novel reactor concept. • This method uses large PCB pieces instead of shredded PCBs as the reactor volume is 2.2 L. • The treated PCBs can be removed via leg B while the process is on-going.

  9. Salt-occluded zeolite waste forms: Crystal structures and transformability

    SciTech Connect

    Richardson, J.W. Jr. [Argonne National Lab., IL (United States). Intense Pulsed Neutron Source Div.

    1996-12-31

    Neutron diffraction studies of salt-occluded zeolite and zeolite/glass composite samples, simulating nuclear waste forms loaded with fission products, have revealed complex structures, with cations assuming the dual roles of charge compensation and occlusion (cluster formation). These clusters roughly fill the 6--8 {angstrom} diameter pores of the zeolites. Samples are prepared by equilibrating zeolite-A with complex molten Li, K, Cs, Sr, Ba, Y chloride salts, with compositions representative of anticipated waste systems. Samples prepared using zeolite 4A (which contains exclusively sodium cations) as starting material are observed to transform to sodalite, a denser aluminosilicate framework structure, while those prepared using zeolite 5A (sodium and calcium ions) more readily retain the zeolite-A structure. Because the sodalite framework pores are much smaller than those of zeolite-A, clusters are smaller and more rigorously confined, with a correspondingly lower capacity for waste containment. Details of the sodalite structures resulting from transformation of zeolite-A depend upon the precise composition of the original mixture. The enhanced resistance of salt-occluded zeolites prepared from zeolite 5A to sodalite transformation is thought to be related to differences in the complex chloride clusters present in these zeolite mixtures. Data relating processing conditions to resulting zeolite composition and structure can be used in the selection of processing parameters which lead to optimal waste forms.

  10. Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

    SciTech Connect

    Rempe, N.T.

    1993-12-01

    Mixed waste (i.e., waste that contains both chemically hazardous and radioactive components) poses a moral, political, and technical challenge to present and future generations. But an international consensus is emerging that harmful byproducts and residues can be permanently isolated from the biosphere in a safe and environmentally responsible manner by deep geologic disposal. To investigate and demonstrate such disposal for transuranic mixed waste, derived from defense-related activities, the US Department of Energy has prepared the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This research and development facility was excavated approximately at the center of a 600 m thick sequence of salt (halite) beds, 655 m below the surface. Proof of the long-term tectonic and hydrological stability of the region is supplied by the fact that these salt beds have remained essentially undisturbed since they were deposited during the Late Permian age, approximately 225 million years ago. Plutonium-239, the main radioactive component of transuranic mixed waste, has a half-life of 24,500 years. Even ten half-lives of this isotope - amounting to about a quarter million years, the time during which its activity will decline to background level represent only 0.11 percent of the history of the repository medium. Therefore, deep geologic disposal of transuranic mixed waste in Permian bedded salt appears eminently feasible.

  11. Paradoxical hypertension and salt wasting in Type II Bartter syndrome

    PubMed Central

    To, Ka Fai; Tong, Joanna H. M.; Law, Chi Wai

    2012-01-01

    Ante/neonatal Bartter syndrome (BS) is a rare hereditary disorder. It is characterized by renal salt wasting, hypokalaemic metabolic alkalosis, high renin and aldosterone but normal blood pressure. We report a low birth weight newborn baby who presented with repeated apnoea shortly after birth as well as hyponatraemia, hypochloraemia, hyperkalaemia and metabolic acidosis. Her biochemical features mimicked pseudohypoaldosteronism but with initial hypertension, which had not been described in BS. Her subsequent genetic study confirmed two novel heterozygous mutations in the Exon 5 of KCNJ1 compatible with Type II BS.

  12. Equipment evaluation for low density polyethylene encapsulated nitrate salt waste at the Rocky Flats Plant

    Microsoft Academic Search

    W. I. Yamada; A. M. Faucette; R. C. Jantzen; B. W. Logsdon; J. H. Oldham; D. M. Saiki; R. J. Yudnich

    1993-01-01

    Mixed wastes at the Rocky Flats Plant (RFP) are subject to regulation by the Resource Conservation and Recovery Act (RCRA). Polymer solidification is being developed as a final treatment technology for several of these mixed wastes, including nitrate salts. Encapsulation nitrate salts with low density polyethylene (LDPE) has been the preliminary focus of the RFP polymer solidification effort. Literature reviews,

  13. Method to synthesize dense crystallized sodalite pellet for immobilizing halide salt radioactive waste

    DOEpatents

    Koyama, T.

    1992-01-01

    This report describes a method for immobilizing waste chloride salts containing radionuclides such as cesium and strontium and hazardous materials such as barium. A sodalite intermediate is prepared by mixing appropriate amounts of silica, alumina and sodium hydroxide with respect to sodalite and heating the mixture to form the sodalite intermediate and water. Heating is continued to drive off the water to form a water-free intermediate. The water-free intermediate is mixed with either waste salt or waste salt which has been contacted with zeolite to concentrate the radionuclides and hazardous material. The waste salt-intermediate mixture is then compacted and heated under conditions of heat and pressure to form sodalite with the waste salt, radionuclides and hazardous material trapped within the sodalite cage structure. This provides a final product having excellent leach resistant capabilities.

  14. Electrodialysis-based separation process for salt recovery and recycling from waste water

    DOEpatents

    Tsai, S.P.

    1997-07-08

    A method for recovering salt from a process stream containing organic contaminants is provided, comprising directing the waste stream to a desalting electrodialysis unit so as to create a concentrated and purified salt permeate and an organic contaminants-containing stream, and contacting said concentrated salt permeate to a water-splitting electrodialysis unit so as to convert the salt to its corresponding base and acid. 6 figs.

  15. Electrodialysis-based separation process for salt recovery and recycling from waste water

    DOEpatents

    Tsai, Shih-Perng (Naperville, IL)

    1997-01-01

    A method for recovering salt from a process stream containing organic contaminants is provided, comprising directing the waste stream to a desalting electrodialysis unit so as to create a concentrated and purified salt permeate and an organic contaminants containing stream, and contacting said concentrated salt permeate to a water-splitting electrodialysis unit so as to convert the salt to its corresponding base and acid.

  16. Container materials for isolation of radioactive waste in salt

    SciTech Connect

    Streicher, M.A.; Andrews, A. (eds.)

    1987-10-01

    The workshop reviewed the extensive data on the corrosion resistance of low-carbon steel in simulated salt repository environments, determined whether these data were sufficient to recommend low-carbon steel for fabrication of the container, and assessed the suitability of other materials under consideration in the SRP. The panelists determined the need for testing and research programs, recommended experimental approaches, and recommended materials based on existing technology. On the first day of the workshop, presentations were made on waste package requirements; the expected corrosion environment; degradation processes, including a review of data from corrosion tests on carbon steel; and rationales for container design and materials, modeling studies, and planned future work. The second day was devoted to a panel caucus, presentation of workshop findings, and open discussion. 76 refs., 2 figs., 3 tabs.

  17. Preliminary technical and legal evaluation of disposing of nonhazardous oil field waste into salt caverns

    SciTech Connect

    Veil, J.; Elcock, D.; Raivel, M.; Caudle, D.; Ayers, R.C. Jr.; Grunewald, B.

    1996-06-01

    Caverns can be readily formed in salt formations through solution mining. The caverns may be formed incidentally, as a result of salt recovery, or intentionally to create an underground chamber that can be used for storing hydrocarbon products or compressed air or disposing of wastes. The purpose of this report is to evaluate the feasibility, suitability, and legality of disposing of nonhazardous oil and gas exploration, development, and production wastes (hereafter referred to as oil field wastes, unless otherwise noted) in salt caverns. Chapter 2 provides background information on: types and locations of US subsurface salt deposits; basic solution mining techniques used to create caverns; and ways in which salt caverns are used. Later chapters provide discussion of: federal and state regulatory requirements concerning disposal of oil field waste, including which wastes are considered eligible for cavern disposal; waste streams that are considered to be oil field waste; and an evaluation of technical issues concerning the suitability of using salt caverns for disposing of oil field waste. Separate chapters present: types of oil field wastes suitable for cavern disposal; cavern design and location; disposal operations; and closure and remediation. This report does not suggest specific numerical limits for such factors or variables as distance to neighboring activities, depths for casings, pressure testing, or size and shape of cavern. The intent is to raise issues and general approaches that will contribute to the growing body of information on this subject.

  18. Recovery of salt wastes in the production of propylene oxide

    SciTech Connect

    Zyablitseva, M.P.; Tyurin, B.K.; Kudinov, V.I.; Bukbulatov, I.K.; Mazanko, A.F.

    1983-02-01

    In the production of propylene oxide as much as 40 t dilute calcium chloride solution forms per ton of product in the step of saponification of propylene chlorhydrine with milk of lime. To create a zero-waste technology for production of propylene oxide, there is practical interest in saponification of propylene chlorhydrine with electrolysis brines with recovery of the resultant solution of sodium chloride after purification to remove organic impurities. The possibility of using an electrochemical method to purify wastewater from production of propylene oxide in using the purified solution as starting material for production of electrolysis brines was investigated. Experimental testing of processes of purification and recovery of wastewaters in a regime of industrial electrolysis confirmed the possibility of using purified wastewater from production of propylene oxide as brine for electrolysis. Incorporation of the developed method into industry will permit zero-waste production of propylene oxide with a closed salt cycle. The cost of purification of 1 m/sup 3/ wastewater is 1-1.5 rubles.

  19. Influence of temperature on strength of cemented surrogate nitrate salt waste

    SciTech Connect

    Not Available

    1993-03-01

    The Rocky Flats Plant (RFP) generates large volumes of a low level aqueous waste stream high in nitrate salts. The aqueous waste is concentrated by evaporation and then mixed with Portland cement prior to transport and disposal. Planned process upgrades include a new horizontal thin film evaporator. Temperature of brine at discharge end of the new evaporator will be near boiling point. Introduction of hot water to cement can degrade the monolithic waste form. However, the RFP salt waste contains high concentrations of compounds known to retard hydration. This paper discusses impact of introducing high temperature waste to cement. The study evaluated three waste compositions: (1) highest probable nitrate composition, (2) highest probable chloride composition, and (3) current composition. Results showed that compressive strength of final waste form increased with brine temperature, and waste forms from brine at the boiling point exhibited a near doubling of compressive strength when compared to waste forms from brine at room temperature.

  20. Expected near-field thermal performance for nuclear waste repositories at potential salt sites: Technical report

    SciTech Connect

    McNulty, E.G.

    1987-08-01

    Thermal analyses were made for the environmental assessments of seven potential salt sites for a nuclear waste repository. These analyses predicted that potential repository sites in domal salts located in the Gulf Coast will experience higher temperature than those in bedded salts of Paradox and Palo Duro Basins, mainly because of higher ambient temperatures at depth. The TEMPV5 code, a semi-analytical heat transfer code for finite line sources, calculated temperatures for commercial high-level waste (CHLW) and spent fuel from pressurized-water reactors (SFPWR). Benchmarks with HEATING6, THAC-SIP-3D, STEALTH, and SPECTROM-41 showed that TEMPV5 agreed closely in the very near field around the waste package and approximately in the near-field and far-field regions of the repository. The analyses used site-specific thermal conductivities that were increased by 40% to compensate for reductions caused by testing technique, salt impurities, and other heterogeneities, and sampling disturbance. Analyses showed peak salt temperatures of 236/sup 0/C (CHLW) and 134/sup 0/C (SFPWR) for the bedded salt and 296/sup 0/C (CHLW) and 180/sup 0/C (SFPWR) for the domal salt. Analyses with uncorrected laboratory thermal conductivities would increase peak salt temperatures by about 120/sup 0/C for CHLW and about 60/sup 0/C for SFPWR. These temperature increases would increase the thermally induced flow of brine and accelerate corrosion of the waste package. 30 refs., 35 figs., 48 tabs.

  1. Application of molten salt oxidation for the minimization and recovery of plutonium-238 contaminated wastes

    SciTech Connect

    Wishau, R.

    1998-05-01

    Molten salt oxidation (MSO) is proposed as a {sup 238}Pu waste treatment technology that should be developed for volume reduction and recovery of {sup 238}Pu and as an alternative to the transport and permanent disposal of {sup 238}Pu waste to the WIPP repository. In MSO technology, molten sodium carbonate salt at 800--900 C in a reaction vessel acts as a reaction media for wastes. The waste material is destroyed when injected into the molten salt, creating harmless carbon dioxide and steam and a small amount of ash in the spent salt. The spent salt can be treated using aqueous separation methods to reuse the salt and to recover 99.9% of the precious {sup 238}Pu that was in the waste. Tests of MSO technology have shown that the volume of combustible TRU waste can be reduced by a factor of at least twenty. Using this factor the present inventory of 574 TRU drums of {sup 238}Pu contaminated wastes is reduced to 30 drums. Further {sup 238}Pu waste costs of $22 million are avoided from not having to repackage 312 of the 574 drums to a drum total of more than 4,600 drums. MSO combined with aqueous processing of salts will recover approximately 1.7 kilograms of precious {sup 238}Pu valued at 4 million dollars (at $2,500/gram). Thus, installation and use of MSO technology at LANL will result in significant cost savings compared to present plans to transport and dispose {sup 238}Pu TRU waste to the WIPP site. Using a total net present value cost for the MSO project as $4.09 million over a five-year lifetime, the project can pay for itself after either recovery of 1.6 kg of Pu or through volume reduction of 818 drums or a combination of the two. These savings show a positive return on investment.

  2. Modified phosphate ceramics for stabilization and solidification of salt mixed wastes.

    SciTech Connect

    Singh, D.

    1998-06-26

    Novel chemically bonded phosphate ceramics have been investigated for stabilization and solidification of chloride and nitrate salt wastes. Using low-temperature processing, we stabilized and solidified chloride and nitrate surrogate salts (with hazardous metals) in magnesium potassium phosphate ceramics up to waste loadings of 70-80 wt.%. A variety of characterizations, including strength, microstructure, and leaching, were then conducted on the waste forms. Leaching tests show that all heavy metals in the leachant are well below the EPAs universal treatment standard limits. Long-term leaching tests, per ANS 16. 1 procedure, yields leachability index for nitrate ions > 12. Chloride ions are expected to have an even higher (i.e., better) leachability index. Structural performance of these final waste forms, as indicated by compression strength and durability in aqueous environments, satisfies the regulatory criteria. Thus, based on the results of this study, it seems that phosphate ceramics are viable option for containment of salt wastes.

  3. Study on a regeneration process of LiCl-KCl eutectic based waste salt generated from the pyrochemical process

    SciTech Connect

    Eun, H.C.; Cho, Y.Z.; Choi, J.H.; Kim, J.H.; Lee, T.K.; Park, H.S.; Kim, I.T.; Park, G.I. [Nuclear Fuel Cycle Waste Treatment Research Division, Korea Atomic Energy Research Institute, 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 3054-353 (Korea, Republic of)

    2013-07-01

    A regeneration process of LiCl-KCl eutectic waste salt generated from the pyrochemical process of spent nuclear fuel has been studied. This regeneration process is composed of a chemical conversion process and a vacuum distillation process. Through the regeneration process, a high efficiency of renewable salt recovery can be obtained from the waste salt and rare earth nuclides in the waste salt can be separated as oxide or phosphate forms. Thus, the regeneration process can contribute greatly to a reduction of the waste volume and a creation of durable final waste forms. (authors)

  4. Alternative Electrochemical Salt Waste Forms, Summary of FY/CY2011 Results

    SciTech Connect

    Riley, Brian J.; McCloy, John S.; Crum, Jarrod V.; Rodriguez, Carmen P.; Windisch, Charles F.; Lepry, William C.; Matyas, Josef; Westman, Matthew P.; Rieck, Bennett T.; Lang, Jesse B.; Pierce, David A.

    2011-12-01

    This report summarizes the 2011 fiscal+calendar year efforts for developing waste forms for a spent salt generated in reprocessing nuclear fuel with an electrochemical separations process. The two waste forms are tellurite (TeO2-based) glasses and sol-gel-derived high-halide mineral analogs to stable minerals found in nature.

  5. Test procedures for polyester immobilized salt-containing surrogate mixed wastes

    SciTech Connect

    Biyani, R.K.; Hendrickson, D.W.

    1997-07-18

    These test procedures are written to meet the procedural needs of the Test Plan for immobilization of salt containing surrogate mixed waste using polymer resins, HNF-SD-RE-TP-026 and to ensure adequacy of conduct and collection of samples and data. This testing will demonstrate the use of four different polyester vinyl ester resins in the solidification of surrogate liquid and dry wastes, similar to some mixed wastes generated by DOE operations.

  6. Treatment of waste by the Molten Salt Oxidation process at the Oak Ridge National Laboratory

    SciTech Connect

    Crosley, S.M.; Lorenzo, D.K.; Van Cleve, J.E. [Oak Ridge National Lab., TN (United States); Gay, R.L.; Barclay, K.M.; Newcomb, J.C.; Yosim, S.J. [Rockwell International Corp., Canoga Park, CA (United States)

    1993-03-01

    The Molten Salt Oxidation (MSO) process has been under development by the Energy Technology Engineering Center (ETEC) to treat hazardous, radioactive, and mixed waste. Testing of the system was done on a number of wastes to demonstrate the technical feasibility of the process. This testing included simulated intermediate level waste (ILW) from the Oak Ridge National Laboratory. The intermediate level waste stream consisted of a slurry of concentrated aqueous solutions of sodium hydroxide and sodium nitrate, with a small amount of miscellaneous combustible components (PVC, TBP, kerosene, and ion exchange resins). The purpose of these tests was to evaluate the destruction of the organics, evaporation of the water, and conversion of the hazardous salts (hydroxide and nitrate) to non-hazardous sodium carbonate. Results of the tests are discussed and analyzed, and the possibilities of applying the MSO process to different waste streams at ORNL in the future are explored.

  7. Conceptual waste package interim product specifications and data requirements for disposal of borosilicate glass defense high-level waste forms in salt geologic repositories

    SciTech Connect

    Not Available

    1983-06-01

    The conceptual waste package interim product specifications and data requirements presented are applicable specifically to the normal borosilicate glass product of the Defense Waste Processing Facility (DWPF). They provide preliminary numerical values for the defense high-level waste form parameters and properties identified in the waste form performance specification for geologic isolation in salt repositories. Subject areas treated include containment and isolation, operational period safety, criticality control, waste form/production canister identification, and waste package performance testing requirements. This document was generated for use in the development of conceptual waste package designs in salt. It will be revised as additional data, analyses, and regulatory requirements become available.

  8. Potential vertical movement of large heat-generating waste packages in salt.

    SciTech Connect

    Clayton, Daniel James; Martinez, Mario J.; Hardin, Ernest L.

    2013-05-01

    With renewed interest in disposal of heat-generating waste in bedded or domal salt formations, scoping analyses were conducted to estimate rates of waste package vertical movement. Vertical movement is found to result from thermal expansion, from upward creep or heave of the near-field salt, and from downward buoyant forces on the waste package. A two-pronged analysis approach was used, with thermal-mechanical creep modeling, and coupled thermal-viscous flow modeling. The thermal-mechanical approach used well-studied salt constitutive models, while the thermal-viscous approach represented the salt as a highly viscous fluid. The Sierra suite of coupled simulation codes was used for both approaches. The waste package in all simulations was a right-circular cylinder with the density of steel, in horizontal orientation. A time-decaying heat generation function was used to represent commercial spent fuel with typical burnup and 50-year age. Results from the thermal-mechanical base case showed approximately 27 cm initial uplift of the package, followed by gradual relaxation closely following the calculated temperature history. A similar displacement history was obtained with the package density set equal to that of salt. The slight difference in these runs is attributable to buoyant displacement (sinking) and is on the order of 1 mm in 2,000 years. Without heat generation the displacement stabilizes at a fraction of millimeter after a few hundred years. Results from thermal-viscous model were similar, except that the rate of sinking was constant after cooldown, at approximately 0.15 mm per 1,000 yr. In summary, all calculations showed vertical movement on the order of 1 mm or less in 2,000 yr, including calculations using well-established constitutive models for temperature-dependent salt deformation. Based on this finding, displacement of waste packages in a salt repository is not a significant repository performance issue.

  9. Modeling the influence of sinking anhydrite blocks on salt diapirs targeted for hazardous waste disposal

    NASA Astrophysics Data System (ADS)

    Koyi, Hemin A.

    2001-05-01

    Due to the low permeability and high ductility of rock salt, many salt diapirs, such as those in Germany and the Netherlands, are targeted as long-term repositories for disposal of high-level radioactive and chemical wastes. Geophysical and subsurface data show that the Gorleben salt diapir, which is one of the most extensively investigated diapirs in the world, and other salt diapirs of the Zechstein Formation in Germany contain large blocks (˜80 m thick) of high-density anhydrite inclusions. These blocks, which were carried upward by the rising salt, are considered to be detached segments of intercalated layers that initially were deposited with the salt. Results of physical and numerical models, presented here, show that such detached, high-density blocks, which were entrained and carried upward by the diapir at an earlier stage, tend to sink in the late stages of diapiric evolution when the rate of diapiric rise slows down. During their descent, these high- density competent blocks deform by folding and create shear zones at the immediate contact with the less competent salt. The descending blocks initiate a secondary internal flow within the salt diapirs they descend, and they may deform any repository built within such diapirs, which would otherwise be considered as tectonically inactive.

  10. Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results

    SciTech Connect

    Riley, Brian J.; Mccloy, John S.; Crum, Jarrod V.; Lepry, William C.; Rodriguez, Carmen P.; Windisch, Charles F.; Matyas, Josef; Westman, Matthew P.; Rieck, Bennett T.; Lang, Jesse B.; Olszta, Matthew J.; Pierce, David A.

    2014-03-26

    The Fuel Cycle Research and Development Program, sponsored by the U.S. Department of Energy Office of Nuclear Energy, is currently investigating alternative waste forms for wastes generated from nuclear fuel processing. One such waste results from an electrochemical separations process, called the “Echem” process. The Echem process utilizes a molten KCl-LiCl salt to dissolve the fuel. This process results in a spent salt containing alkali, alkaline earth, lanthanide halides and small quantities of actinide halides, where the primary halide is chloride with a minor iodide fraction. Pacific Northwest National Laboratory (PNNL) is concurrently investigating two candidate waste forms for the Echem spent-salt: high-halide minerals (i.e., sodalite and cancrinite) and tellurite (TeO2)-based glasses. Both of these candidates showed promise in fiscal year (FY) 2009 and FY2010 with a simplified nonradioactive simulant of the Echem waste. Further testing was performed on these waste forms in FY2011 and FY2012 to assess the possibility of their use in a sustainable fuel cycle. This report summarizes the combined results from FY2011 and FY2012 efforts.

  11. Caustic Recycle from Hanford Tank Waste Using NaSICON Ceramic Membrane Salt Splitting Process

    SciTech Connect

    Fountain, Matthew S.; Kurath, Dean E.; Sevigny, Gary J.; Poloski, Adam P.; Pendleton, J.; Balagopal, S.; Quist, M.; Clay, D.

    2009-02-20

    A family of inorganic ceramic materials, called sodium (Na) Super Ion Conductors (NaSICON), has been studied at Pacific Northwest National Laboratory (PNNL) to investigate their ability to separate sodium from radioactively contaminated sodium salt solutions for treating U.S. Department of Energy (DOE) tank wastes. Ceramatec Inc. developed and fabricated a membrane containing a proprietary NAS-GY material formulation that was electrochemically tested in a bench-scale apparatus with both a simulant and a radioactive tank-waste solution to determine the membrane performance when removing sodium from DOE tank wastes. Implementing this sodium separation process can result in significant cost savings by reducing the disposal volume of low-activity wastes and by producing a NaOH feedstock product for recycle into waste treatment processes such as sludge leaching, regenerating ion exchange resins, inhibiting corrosion in carbon-steel tanks, or retrieving tank wastes.

  12. Preliminary Technical and Legal Evaluation of Disposing of Nonhazardous Oil Field Waste into Salt Caverns

    SciTech Connect

    Ayers, Robert C.; Caudle, Dan; Elcock, Deborah; Raivel, Mary; Veil, John; and Grunewald, Ben

    1999-01-21

    This report presents an initial evaluation of the suitability, feasibility, and legality of using salt caverns for disposal of nonhazardous oil field wastes. Given the preliminary and general nature of this report, we recognize that some of our findings and conclusions maybe speculative and subject to change upon further research on this topic.

  13. Molten salt destruction as an alternative to open burning of energetic material wastes

    Microsoft Academic Search

    R. S. Upadhye; B. E. Watkins; C. O. Pruneda; W. A. Brummond

    1994-01-01

    LLNL has built a small-scale (about 1 kg\\/hr throughput unit to test the destruction of energetic materials using the Molten Salt Destruction (MSD) process. We have modified the unit described in the earlier references to inject energetic waste material continuously into the unit. In addition to the HMX, other explosives we have destroyed include RDX, PETN, ammonium picrate, TNT, nitroguanadine,

  14. Testing of low-temperature stabilization alternatives for salt containing mixed wastes -- Approach and results to date

    SciTech Connect

    Maio, V.; Loomis, G. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Spence, R.D. [Oak Ridge National Lab., TN (United States); Smith, G. [Pacific Northwest National Lab., Richland, WA (United States); Biyani, R.K. [SGN Eurisys Services Corp., Richland, WA (United States); Wagh, A. [Argonne National Lab., IL (United States)

    1998-05-01

    Through its annual process of identifying technology deficiencies associated with waste treatment, the Department of Energy`s (DOE) Mixed Waste Focus Area (MWFA) determined that the former DOE weapons complex lacks efficient mixed waste stabilization technologies for salt containing wastes. These wastes were generated as sludge and solid effluents from various primary nuclear processes involving acids and metal finishing; and well over 10,000 cubic meters exist at 6 sites. In addition, future volumes of these problematic wastes will be produced as other mixed waste treatment methods such as incineration and melting are deployed. The current method used to stabilize salt waste for compliant disposal is grouting with Portland cement. This method is inefficient since the highly soluble and reactive chloride, nitrate, and sulfate salts interfere with the hydration and setting processes associated with grouting. The inefficiency results from having to use low waste loadings to ensure a durable and leach resistant final waste form. The following five alternatives were selected for MWFA development funding in FY97 and FY98: phosphate bonded ceramics; sol-gel process; polysiloxane; polyester resin; and enhanced concrete. Comparable evaluations were planned for the stabilization development efforts. Under these evaluations each technology stabilized the same type of salt waste surrogates. Final waste form performance data such as compressive strength, waste loading, and leachability could then be equally compared. Selected preliminary test results are provided in this paper.

  15. New information on disposal of oil field wastes in salt caverns

    SciTech Connect

    Veil, J.A.

    1996-10-01

    Solution-mined salt caverns have been used for many years for storing hydrocarbon products. This paper summarizes an Argonne National Laboratory report that reviews the legality, technical suitability, and feasibility of disposing of nonhazardous oil and gas exploration and production wastes in salt caverns. An analysis of regulations indicated that there are no outright regulatory prohibitions on cavern disposal of oil field wastes at either the federal level or in the 11 oil-producing states that were studied. There is no actual field experience on the long-term impacts that might arise following closure of waste disposal caverns. Although research has found that pressures will build-up in a closed cavern, none has specifically addressed caverns filled with oil field wastes. More field research on pressure build-up in closed caverns is needed. On the basis of preliminary investigations, we believe that disposal of oil field wastes in salt caverns is legal and feasible. The technical suitability of the practice depends on whether the caverns are well-sited and well-designed, carefully operated, properly closed, and routinely monitored.

  16. The advantages of a salt/bentonite backfill for Waste Isolation Pilot Plant disposal rooms

    SciTech Connect

    Butcher, B.M.; Novak, C.F. (Sandia National Labs., Albuquerque, NM (United States)); Jercinovic, M. (New Mexico Univ., Albuquerque, NM (United States))

    1991-04-01

    A 70/30 wt% salt/bentonite mixture is shown to be preferable to pure crushed salt as backfill for disposal rooms in the Waste Isolation Pilot Plant (WIPP). This report discusses several selection criteria used to arrive at this conclusion: the need for low permeability and porosity after closure, chemical stability with the surroundings, adequate strength to avoid shear erosion from human intrusion, ease of emplacement, and sorption potential for brine and radionuclides. Both salt and salt/bentonite are expected to consolidate to a final state of impermeability (i.e., {le} 10{sup {minus}18}m{sup 2}) adequate for satisfying federal nuclear regulations. Any advantage of the salt/bentonite mixture is dependent upon bentonite's potential for sorbing brine and radionuclides. Estimates suggest that bentonite's sorption potential for water in brine is much less than for pure water. While no credit is presently taken for brine sorption in salt/bentonite backfill, the possibility that some amount of inflowing brine would be chemically bound is considered likely. Bentonite may also sorb much of the plutonium, americium, and neptunium within the disposal room inventory. Sorption would be effective only if a major portion of the backfill is in contact with radioactive brine. Brine flow from the waste out through highly localized channels in the backfill would negate sorption effectiveness. Although the sorption potentials of bentonite for both brine and radionuclides are not ideal, they are distinctly beneficial. Furthermore, no detrimental aspects of adding bentonite to the salt as a backfill have been identified. These two observations are the major reasons for selecting salt/bentonite as a backfill within the WIPP. 39 refs., 16 figs., 6 tabs.

  17. Recovery of plutonium and americium from chloride salt wastes by solvent extraction

    SciTech Connect

    Reichley-Yinger, L.; Vandegrift, G.F.

    1987-01-01

    Plutonium and americium can be recovered from aqueous waste solutions containing a mixture of HCl and chloride salt wastes by the coupling of two solvent extraction systems: tributyl phosphate (TBP) in tetrachloroethylene (TCE) and octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide (CMPO) in TCE. In the flowsheet developed, the salt wastes are dissolved in HCl, the Pu(III) is oxidized to the IV state with NaClO/sub 2/ and recovered in the TBP-TCE cycle, and the Am is then removed from the resultant raffinate by the CMPO-TCE cycle. The consequences of the feed solution composition and extraction behavior of these species on the process flowsheet design, the Pu-product purity, and the decontamination of the aqueous raffinate from transuranic elements are discussed. 16 refs., 6 figs.

  18. Molten salt oxidation of mixed waste: Preliminary bench-scale experiments without radioactivity

    SciTech Connect

    Haas, P.A.; Rudolph, J.C.; Bell, J.T.

    1994-06-01

    Molten salt oxidation (MSO) is a process in which organic wastes are oxidized by sparging them with air through a bed of molten sodium carbonate (bp 851 {degrees}C) at {ge} 900{degrees}C. This process is readily applicable to the mixed waste because acidic products from Cl, S, P, etc., in the waste, along with most metals and most radionuclides, are retained within the melt as oxides or salts. Rockwell International has studied the application of MSO to various wastes, including some mixed waste. A unit used by Rockwell to study the mixed waste treatment is presently in use at Oak Ridge National Laboratory (ORNL). ORNL`s studies to date have concentrated on chemical flowsheet questions. Concerns that were studied included carbon monoxide (CO) emissions, NO{sub x}, emissions, and metal retention under a variety of conditions. Initial experiments show that CO emissions increase with increasing NaCl content in the melt, increasing temperature, and increasing airflow. Carbon monoxide content is especially high (> 2000 ppm) with high chlorine content (> 10%). Thermal NO{sub x}, emissions are relatively low ( < 5 ppm) at temperatures < 1000{degrees}C. However, most (85--100%) of the nitrogen in the feed as organic nitrate or amine was released as NO{sub x}, The metal contents of the melt and of knockout pot samples of condensed salt show high volatilities of Cs as CsCl. Average condensed salt concentrations were 60% for barium and 100% for strontium and cobalt. The cerium disappeared -- perhaps from deposition on the alumina reactor walls.

  19. Molten salt destruction of energetic material wastes as an alternative to open burning. Revision 1

    SciTech Connect

    Upadhye, R.S.; Brummond, W.A.; Pruneda, C.O.; Watkins, B.E. [Lawrence Livermore National Lab., CA (United States). Energetic Materials Center

    1994-11-02

    As a result of the end of the Cold War and the shift in emphasis to a smaller stockpile, many munitions, both conventional and nuclear, are scheduled for retirement and rapid dismantlement and demilitarization. Major components of these munitions are the explosives and propellants, or energetic materials. The Molten Salt Destruction (MSD) Process has been demonstrated for the destruction of HE and HE-containing wastes. MSD converts the organic constituents of the waste into non-hazardous substances such as carbon dioxide, nitrogen and water. Any inorganic constituents of the waste, such as binders and metallic particles, are retained in the molten salt. LLNL has built a small-scale (about 1 kg/hr throughput) unit to test the destruction of HE using the MSD process. The authors have demonstrated that HE`s and liquid propellants can be safely and fully destroyed using the molten salt destruction process. The authors are currently working on a number of improvements to the process. They are modifying the design of unit to obtain more throughput without any increase in salt entrainment. They are implementing an advanced nozzle design for injection of larger particles. They are defining operating envelopes for a number of high explosives and formulations. They are developing models to study the temperature profile of a top-feed nozzle for feeding larger particles into the unit.

  20. Subsurface geology of a potential waste emplacement site, Salt Valley Anticline, Grand County, Utah

    USGS Publications Warehouse

    Hite, R.J.

    1977-01-01

    The Salt Valley anticline, which is located about 32 km northeast of Moab, Utah, is perhaps one of the most favorable waste emplacement sites in the Paradox basin. The site, which includes about 7.8 km 2, is highly accessible and is adjacent to a railroad. The anticline is one of a series of northwest-trending salt anticlines lying along the northeast edge of the Paradox basin. These anticlines are cored by evaporites of the Paradox Member of the Hermosa Formation of Middle Pennsylvanian age. The central core of the Salt Valley anticline forms a ridgelike mass of evaporites that has an estimated amplitude of 3,600 m. The evaporite core consists of about 87 percent halite rock, which includes some potash deposits; the remainder is black shale, silty dolomite, and anhydrite. The latter three lithologies are referred to as 'marker beds.' Using geophysical logs from drill holes on the anticline, it is possible to demonstrate that the marker beds are complexly folded and faulted. Available data concerning the geothermal gradient and heatflow at the site indicate that heat from emplaced wastes should be rapidly dissipated. Potentially exploitable resources of potash and petroleum are present at Salt Valley. Development of these resources may conflict with use of the site for waste emplacement.

  1. Hydrous mineral dehydration around heat-generating nuclear waste in bedded salt formations.

    PubMed

    Jordan, Amy B; Boukhalfa, Hakim; Caporuscio, Florie A; Robinson, Bruce A; Stauffer, Philip H

    2015-06-01

    Heat-generating nuclear waste disposal in bedded salt during the first two years after waste emplacement is explored using numerical simulations tied to experiments of hydrous mineral dehydration. Heating impure salt samples to temperatures of 265 °C can release over 20% by mass of hydrous minerals as water. Three steps in a series of dehydration reactions are measured (65, 110, and 265 °C), and water loss associated with each step is averaged from experimental data into a water source model. Simulations using this dehydration model are used to predict temperature, moisture, and porosity after heating by 750-W waste canisters, assuming hydrous mineral mass fractions from 0 to 10%. The formation of a three-phase heat pipe (with counter-circulation of vapor and brine) occurs as water vapor is driven away from the heat source, condenses, and flows back toward the heat source, leading to changes in porosity, permeability, temperature, saturation, and thermal conductivity of the backfill salt surrounding the waste canisters. Heat pipe formation depends on temperature, moisture availability, and mobility. In certain cases, dehydration of hydrous minerals provides sufficient extra moisture to push the system into a sustained heat pipe, where simulations neglecting this process do not. PMID:25965632

  2. DNA extraction conditions from Porphyra perforata using LiCl

    Microsoft Academic Search

    Yong-Ki Hong; Sang-Dal Kim; Miriam Polne-Fuller; Aharon Gibor

    1995-01-01

    A rapid and economical method of DNA extraction from a red seaweedPorphyra perforata J. Agardh has been developed by the use of lithium chloride. This paper describes the optimization of extraction conditions. Heat treatment of tissues in a solution (0.8 M LiCl, 0.6% Sarkosyl, 10 mM EDTA, 0.2% PVPP, 5% ß-mercaptoethanol, pH 9.0) at 55 °C for 10 min extracts

  3. Conditioning matrices from high level waste resulting from pyrochemical processing in fluorine salt

    SciTech Connect

    Grandjean, Agnes; Advocat, Thierry; Bousquet, Nicolas [SCDV - Service de Confinement des Dechets et Vitrification - Laboratoire d'Etudes de Base sur les Verres, CEA Valrho, Centre de Marcoule, 30207 Bagnols sur Ceze (France); Jegou, Christophe [SECM - Service d'Etude du Confinement et Materiaux - Laboratoire des Materiaux et Procedes Actifs - CEA Valrho, Centre de Marcoule, 30207 Bagnols sur Ceze (France)

    2007-07-01

    Separating the actinides from the fission products through reductive extraction by aluminium in a LiF/AlF{sub 3} medium is a process investigated for pyrometallurgical reprocessing of spent fuel. The process involves separation by reductive salt-metal extraction. After dissolving the fuel or the transmutation target in a salt bath, the noble metal fission products are first extracted by contacting them with a slightly reducing metal. After extracting the metal fission products, then the actinides are selectively separated from the remaining fission products. In this hypothesis, all the unrecoverable fission products would be conditioned as fluorides. Therefore, this process will generate first a metallic waste containing the 'reducible' fission products (Pd, Mo, Ru, Rh, Tc, etc.) and a fluorine waste containing alkali-metal, alkaline-earth and rare earth fission products. Immobilization of these wastes in classical borosilicate glasses is not feasible due to the very low solubility of noble metals, and of fluoride in these hosts. Alternative candidates have therefore been developed including silicate glass/ceramic system for fluoride fission products and metallic ones for noble metal fission products. These waste-forms were evaluated for their confinement properties like homogeneity, waste loading, volatility during the elaboration process, chemical durability, etc. using appropriate techniques. (authors)

  4. [A case of renal salt-wasting syndrome during chemotherapy for advanced gastric cancer].

    PubMed

    Yasuhara, Hisae; Imagawa, Atsushi; Koike, Nao; Ueta, Eijiro; Matsumi, Akihiro; Terasawa, Hiroyuki; Sakae, Hiroyuki; Takeuchi, Keiko; Fujihara, Manabu; Endo, Hitomi; Jinno, Hideki; Moriya, Akio; Hata, Hidenori; Nakatsu, Morihito; Ando, Masaharu

    2015-02-01

    A 66-year-old woman was admitted to our hospital with heartburn and liver dysfunction. She was diagnosed with advanced gastric cancer. After the initiation of chemotherapy with trastuzumab, capecitabine, and cisplatin, she developed hyponatremia and renal failure with renal salt-wasting syndrome (RSWS). She recovered from these conditions after infusion of hypertonic saline. A diagnosis of RSWS should be considered in patients with hyponatremia who receive cisplatin-based chemotherapy. PMID:25743144

  5. Aspects of the thermal and transport properties of crystalline salt in designing radioactive waste storages in halogen formations

    SciTech Connect

    Nikitin, A. N., E-mail: nikitin@nf.jinr.ru; Pocheptsova, O. A.; Matthies, S. [Joint Institute for Nuclear Research, Frank Laboratory of Nuclear Physics (Russian Federation)

    2010-05-15

    Some of the properties of natural rock salt are described. This rock is of great practical interest, because, along with its conventional applications in the chemical and food industries, it is promising for use in engineering underground radioactive waste storages and natural gas reservoirs. The results of structural and texture studies of rock salt by neutron diffraction are discussed. The nature of the salt permeability under temperature and stress gradients is theoretically estimated.

  6. USING MINED SPACE FOR LONG-TERM RETENTION OF NONRADIOACTIVE HAZARDOUS WASTE. VOLUME 2. SOLUTION MINED SALT CAVERNS

    EPA Science Inventory

    This two-volume report assesses the current status of using mined-space for long-term retention of nonradioactive hazardous waste. Volume 2 expands the definition of mined space to include that created by solution mining of salt. This report examines the extent of salt deposits i...

  7. Molten Salt Oxidation of Mixed Wastes: Separation of Radioactive Materials and Resource Conservation and Recovery Act (RCRA) Materials

    Microsoft Academic Search

    J. T. Bell; P. A. Haas; J. C. Rudolph

    1995-01-01

    The Oak Ridge National Laboratory (ORNL) is participating in a program to apply a molten salt oxidation (MSO) process to treatment of mixed (radioactive and RCRA) wastes. The salt residues from the MSO treatment will require further separations or other processing to prepare them for final disposal. A bench-scale MSO apparatus is being installed at ORNL and will be operated

  8. RESULTS OF THE EXTRACTION-SCRUB-STRIP TESTING USING AN IMPROVED SOLVENT FORMULATION AND SALT WASTE PROCESSING FACILITY SIMULATED WASTE

    SciTech Connect

    Peters, T.; Washington, A.; Fink, S.

    2012-01-09

    The Office of Waste Processing, within the Office of Technology Innovation and Development, is funding the development of an enhanced solvent - also known as the next generation solvent (NGS) - for deployment at the Savannah River Site to remove cesium from High Level Waste. The technical effort is a collaborative effort between Oak Ridge National Laboratory (ORNL) and Savannah River National Laboratory (SRNL). As part of the program, the Savannah River National Laboratory (SRNL) has performed a number of Extraction-Scrub-Strip (ESS) tests. These batch contact tests serve as first indicators of the cesium mass transfer solvent performance with actual or simulated waste. The test detailed in this report used simulated Tank 49H material, with the addition of extra potassium. The potassium was added at 1677 mg/L, the maximum projected (i.e., a worst case feed scenario) value for the Salt Waste Processing Facility (SWPF). The results of the test gave favorable results given that the potassium concentration was elevated (1677 mg/L compared to the current 513 mg/L). The cesium distribution value, DCs, for extraction was 57.1. As a comparison, a typical D{sub Cs} in an ESS test, using the baseline solvent formulation and the typical waste feed, is {approx}15. The Modular Caustic Side Solvent Extraction Unit (MCU) uses the Caustic-Side Solvent Extraction (CSSX) process to remove cesium (Cs) from alkaline waste. This process involves the use of an organic extractant, BoBCalixC6, in an organic matrix to selectively remove cesium from the caustic waste. The organic solvent mixture flows counter-current to the caustic aqueous waste stream within centrifugal contactors. After extracting the cesium, the loaded solvent is stripped of cesium by contact with dilute nitric acid and the cesium concentrate is transferred to the Defense Waste Processing Facility (DWPF), while the organic solvent is cleaned and recycled for further use. The Salt Waste Processing Facility (SWPF), under construction, will use the same process chemistry. The Office of Waste Processing (EM-31) expressed an interest in investigating the further optimization of the organic solvent by replacing the BoBCalixC6 extractant with a more efficient extractant. This replacement should yield dividends in improving cesium removal from the caustic waste stream, and in the rate at which the caustic waste can be processed. To that end, EM-31 provided funding for both the Savannah River National Laboratory (SRNL) and the Oak Ridge National Laboratory (ORNL). SRNL wrote a Task Technical Quality and Assurance Plan for this work. As part of the envisioned testing regime, it was decided to perform an ESS test using a simulated waste that simulated a typical envisioned SWPF feed, but with added potassium to make the waste more challenging. Potassium interferes in the cesium removal, and its concentration is limited in the feed to <1950 mg/L. The feed to MCU has typically contained <500 mg/L of potassium.

  9. Transport of contaminants in geologic media: Radioactive waste in salt, corrosion of copper, and colloid migration

    NASA Astrophysics Data System (ADS)

    Hwang, Yong Soo

    Analytical and numerical models on mass transfer of radionuclides from a waste package to surrounding rock are analyzed. Based on developed models corresponding computer programs are developed. These models would be used to evaluate possible hazardous radionuclide release rates into the surrounding rock/biosphere. Specifically the following fields are studied. (1) Analysis on the possible copper canister pitting corrosion by sulfide intrusion is performed to predict the canister lifetime. The study includes both steady-state and time-dependent cases. (2) Analysis on the brine migration in a salt repository is studied. Brine was traditionally thought to be the major factor on radionuclide migration in salt. But results given in this dissertation provide that the brine migration velocity is small enough to be neglected. Two analyses are developed for open bore hole as well as consolidated salt cases. (3) Analysis on the radionuclide migration in a salt repository is carried out. After proving that the diffusion is a dominant migration mechanism, the time-dependent diffusive mass transfer theory is used to predict fractional release rates of low-soluble as well as highly-soluble nuclides. Also the steady-state radionuclide migration through interbeds is analyzed based on the potential flow theory. Finally assuming no advective flow inside interbeds the transient radionuclide migration into interbeds is studied. Results show that salt is a good host rock for a future high-level waste repository. (4) Analysis on the radiocolloid migration through the porous media with filtration effect is performed. Results show that due to the strong filtration radiocolloid would not migrate significant distance in geologic media. Cylindrical geometry is used. For this analysis due to the complexity of the prescribed problem the numerical analysis based on upwind scheme is developed. (5) Analysis on the radiocolloid migration through fractures with solute matrix diffusion into surrounding rock matrix is studied with and without filtration. Interaction between colloid and solute accelerates the radiocolloid migration in fractures.

  10. NRC Monitoring of Salt Waste Disposal at the Savannah River Site - 13147

    SciTech Connect

    Pinkston, Karen E.; Ridge, A. Christianne; Alexander, George W.; Barr, Cynthia S.; Devaser, Nishka J.; Felsher, Harry D. [U.S. Nuclear Regulatory Commission (United States)] [U.S. Nuclear Regulatory Commission (United States)

    2013-07-01

    As part of monitoring required under Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 (NDAA), the NRC staff reviewed an updated DOE performance assessment (PA) for salt waste disposal at the Saltstone Disposal Facility (SDF). The NRC staff concluded that it has reasonable assurance that waste disposal at the SDF meets the 10 CFR 61 performance objectives for protection of individuals against intrusion (chap.61.42), protection of individuals during operations (chap.61.43), and site stability (chap.61.44). However, based on its evaluation of DOE's results and independent sensitivity analyses conducted with DOE's models, the NRC staff concluded that it did not have reasonable assurance that DOE's disposal activities at the SDF meet the performance objective for protection of the general population from releases of radioactivity (chap.61.41) evaluated at a dose limit of 0.25 mSv/yr (25 mrem/yr) total effective dose equivalent (TEDE). NRC staff also concluded that the potential dose to a member of the public is expected to be limited (i.e., is expected to be similar to or less than the public dose limit in chap.20.1301 of 1 mSv/yr [100 mrem/yr] TEDE) and is expected to occur many years after site closure. The NRC staff used risk insights gained from review of the SDF PA, its experience monitoring DOE disposal actions at the SDF over the last 5 years, as well as independent analysis and modeling to identify factors that are important to assessing whether DOE's disposal actions meet the performance objectives. Many of these factors are similar to factors identified in the NRC staff's 2005 review of salt waste disposal at the SDF. Key areas of interest continue to be waste form and disposal unit degradation, the effectiveness of infiltration and erosion controls, and estimation of the radiological inventory. Based on these factors, NRC is revising its plan for monitoring salt waste disposal at the SDF in coordination with South Carolina Department of Health and Environmental Control (SCDHEC). DOE has completed or begun additional work related to salt waste disposal to address these factors. NRC staff continues to evaluate information related to the performance of the SDF and has been working with DOE and SCDHEC to resolve NRC staff's technical concerns. (authors)

  11. Harvesting capacitive carbon by carbonization of waste biomass in molten salts.

    PubMed

    Yin, Huayi; Lu, Beihu; Xu, Yin; Tang, Diyong; Mao, Xuhui; Xiao, Wei; Wang, Dihua; Alshawabkeh, Akram N

    2014-07-15

    Conversion of waste biomass to value-added carbon is an environmentally benign utilization of waste biomass to reduce greenhouse gas emissions and air pollution caused by open burning. In this study, various waste biomasses are converted to capacitive carbon by a single-step molten salt carbonization (MSC) process. The as-prepared carbon materials are amorphous with oxygen-containing functional groups on the surface. For the same type of waste biomass, the carbon materials obtained in Na2CO3-K2CO3 melt have the highest Brunauer-Emmett-Teller (BET) surface area and specific capacitance. The carbon yield decreases with increasing reaction temperature, while the surface area increases with increasing carbonization temperature. A working temperature above 700 °C is required for producing capacitive carbon. The good dissolving ability of alkaline carbonate molten decreases the yield of carbon from waste biomasses, but helps to produce high surface area carbon. The specific capacitance data confirm that Na2CO3-K2CO3 melt is the best for producing capacitive carbon. The specific capacitance of carbon derived from peanut shell is as high as 160 F g(-1) and 40 ?F cm(-2), and retains 95% after 10,000 cycles at a rate of 1 A g(-1). MSC offers a simple and environmentally sound way for transforming waste biomass to highly capacitive carbon as well as an effective carbon sequestration method. PMID:24983414

  12. Disposal of NORM-contaminated oil field wastes in salt caverns -- Legality, technical feasibility, economics, and risk

    SciTech Connect

    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 approaching 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.

  13. Permian salt dissolution, alkaline lake basins, and nuclear-waste storage, Southern High Plains, Texas and New Mexico

    SciTech Connect

    Reeves, C.C. Jr.; Temple, J.M.

    1986-11-01

    Areas of Permian salt dissolution associated with 15 large alkaline lake basins on and adjacent to the Southern High Plains of west Texas and eastern New Mexico suggest formation of the basins by collapse of strata over the dissolution cavities. However, data from 6 other alkaline basins reveal no evidence of underlying salt dissolution. Thus, whether the basins were initiated by subsidence over the salt dissolution areas or whether the salt dissolution was caused by infiltration of overlying lake water is conjectural. However, the fact that the lacustrine fill in Mound Lake greatly exceeds the amount of salt dissolution and subsidence of overlying beds indicates that at least Mound Lake basin was antecedent to the salt dissolution. The association of topography, structure, and dissolution in areas well removed from zones of shallow burial emphasizes the susceptibility of Permian salt-bed dissolution throughout the west Texas-eastern New Mexico area. Such evidence, combined with previous studies documenting salt-bed dissolution in areas surrounding a proposed high-level nuclear-waste repository site in Deaf Smith County, Texas, leads to serious questions about the rationale of using salt beds for nuclear-waste storage.

  14. DEGRADED TBP SOLVENT REGENERATION TECHNOLOGY USING BUTYLAMINE AS A SOLVENT WASHING TO REDUCE SOLID SALT WASTE

    SciTech Connect

    Asakura, T.; Itoh, Y.; Hotoku, S.; Morita, Y.; Uchiyama, G.

    2003-02-27

    Normal butylamine compounds are studied as salt-free wash reagents for degraded solvent used in PUREX process in spent fuel reprocessing. The solvent wash tests were carried out with two types of butylamine compounds, n-butylamine oxalate and n-butylamine bicarbonate, by counter-current mode using a small size mixer-settler composed of two 4-stage wash steps. Di-n-butyl phosphoric acid (HDBP), the main degradation product from TBP, was removed from real degraded solvent with decontamination factor of 2.5 {approx} 7.9. The study on electrolytic decomposition of butylamine compounds was also conducted for waste treatment.

  15. The source term and waste optimization of molten salt reactors with processing

    SciTech Connect

    Gat, U. [Oak Ridge National Lab., TN (United States); Dodds, H.L. [Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering

    1993-07-01

    The source term of a molten salt reactor (MSR) with fuel processing is reduced by the ratio of processing time to refueling time as compared to solid fuel reactors. The reduction, which can be one to two orders of magnitude, is due to removal of the long-lived fission products. The waste from MSRs can be optimized with respect to its chemical composition, concentration, mixture, shape, and size. The actinides and long-lived isotopes can be separated out and returned to the reactor for transmutation. These features make MSRs more acceptable and simpler in operation and handling.

  16. [A case of acute limbic encephalitis with cerebral salt wasting syndrome].

    PubMed

    Nishio, Motonobu; Nishitani, Nobuyuki; Tanaka, Keiko

    2014-01-01

    A 37-year-old woman presented with psychiatric symptoms. Cerebrospinal fluid analysis revealed pleocytosis and increased protein. The patient was diagnosed with limbic encephalitis on the basis of the clinical course. However, remarkable hyponatremia was noted throughout the clinical course, leading to a diagnosis of cerebral salt wasting syndrome (CSWS). The hyponatremia was alleviated by supplementation with sodium and water. The findings seen in this case indicate that differentiation between syndrome of inappropriate of antidiuretic hormone and CSWS is important in cases of hyponatremia accompanied by central nervous system disease. PMID:25142538

  17. Independent Assessment of the Savannah River Site High-Level Waste Salt Disposition Alternatives Evaluation

    SciTech Connect

    J. T. Case (DOE-ID); M. L. Renfro (INEEL)

    1998-12-01

    This report presents the results of the Independent Project Evaluation (IPE) Team assessment of the Westinghouse Savannah River Company High-Level Waste Salt Disposition Systems Engineering (SE) Team's deliberations, evaluations, and selections. The Westinghouse Savannah River Company concluded in early 1998 that production goals and safety requirements for processing SRS HLW salt to remove Cs-137 could not be met in the existing In-Tank Precipitation Facility as currently configured for precipitation of cesium tetraphenylborate. The SE Team was chartered to evaluate and recommend an alternative(s) for processing the existing HLW salt to remove Cs-137. To replace the In-Tank Precipitation process, the Savannah River Site HLW Salt Disposition SE Team downselected (October 1998) 140 candidate separation technologies to two alternatives: Small-Tank Tetraphenylborate (TPB) Precipitation (primary alternative) and Crystalline Silicotitanate (CST) Nonelutable Ion Exchange (backup alternative). The IPE Team, commissioned by the Department of Energy, concurs that both alternatives are technically feasible and should meet all salt disposition requirements. But the IPE Team judges that the SE Team's qualitative criteria and judgments used in their downselection to a primary and a backup alternative do not clearly discriminate between the two alternatives. To properly choose between Small-Tank TPB and CST Ion Exchange for the primary alternative, the IPE Team suggests the following path forward: Complete all essential R and D activities for both alternatives and formulate an appropriate set of quantitative decision criteria that will be rigorously applied at the end of the R and D activities. Concurrent conceptual design activities should be limited to common elements of the alternatives.

  18. A Retrospective Analysis of the Growth Pattern in Patients with Salt-wasting 21-Hydroxylase Deficiency.

    PubMed

    Kawano, Atsuko; Kohno, Hitoshi; Miyako, Kenichi

    2014-04-01

    The objective of this study was to investigate the growth pattern of children with the salt-wasting form of congenital adrenal hyperplasia caused by 21-hydroxylase deficiency (21-OHD). We reviewed the medical records of 13 patients in whom salt-wasting 21-OHD was diagnosed during the first 2 mo of life at our hospital from 1980 through 2008. Six reached adult height. Growth patterns, bone age, biochemical data, and the hydrocortisone dose at each growth stage were analyzed retrospectively. The mean adult height was 155.1 ± 6.5 cm (mean ± SD) in females and 158.1 ± 7.1 cm in males. Although length at birth was normal or longer than the national mean in almost all patients, the mean height SD score of both boys and girls decreased to below 0 SD during infancy. Subsequently, both boys and girls transiently showed growth acceleration and reached their peak growth velocity at 3-10 yr of age. In conclusion, in addition to suppression of growth during infancy, there was inappropriate growth acceleration during childhood. Especially from 3 mo to 3 yr of age, decreasing the hydrocortisone dose in patients who exhibit slower growth may lead to satisfactory height outcomes. Also, strict adjustment of the hydrocortisone dose to avoid accelerated growth from childhood to adolescence might improve adult height outcomes of patients with 21-OHD. PMID:24790384

  19. A Retrospective Analysis of the Growth Pattern in Patients with Salt-wasting 21-Hydroxylase Deficiency

    PubMed Central

    Kawano, Atsuko; Kohno, Hitoshi; Miyako, Kenichi

    2014-01-01

    Abstract The objective of this study was to investigate the growth pattern of children with the salt-wasting form of congenital adrenal hyperplasia caused by 21-hydroxylase deficiency (21-OHD). We reviewed the medical records of 13 patients in whom salt-wasting 21-OHD was diagnosed during the first 2 mo of life at our hospital from 1980 through 2008. Six reached adult height. Growth patterns, bone age, biochemical data, and the hydrocortisone dose at each growth stage were analyzed retrospectively. The mean adult height was 155.1 ± 6.5 cm (mean ± SD) in females and 158.1 ± 7.1 cm in males. Although length at birth was normal or longer than the national mean in almost all patients, the mean height SD score of both boys and girls decreased to below 0 SD during infancy. Subsequently, both boys and girls transiently showed growth acceleration and reached their peak growth velocity at 3–10 yr of age. In conclusion, in addition to suppression of growth during infancy, there was inappropriate growth acceleration during childhood. Especially from 3 mo to 3 yr of age, decreasing the hydrocortisone dose in patients who exhibit slower growth may lead to satisfactory height outcomes. Also, strict adjustment of the hydrocortisone dose to avoid accelerated growth from childhood to adolescence might improve adult height outcomes of patients with 21-OHD. PMID:24790384

  20. A Lithium Amide Protected Against Protonation in the Gas Phase: Unexpected Effect of LiCl.

    PubMed

    Lesage, Denis; Barozzino-Consiglio, Gabriella; Duwald, Romain; Fressigné, Catherine; Harrison-Marchand, Anne; Faull, Kym F; Maddaluno, Jacques; Gimbert, Yves

    2015-06-19

    In cold THF and in the presence of LiCl, a lithium pyrrolidinylamide forms a 1:1 mixed aggregate, which is observed directly by ESI-MS. Gas-phase protonation of this species leads to selective transfer of H(+) to the chlorine, suggesting that LiCl shields the amide nitrogen and prevents its direct protonation. PMID:25997158

  1. Removal of salt from high-level waste tanks by density-driven circulation or mechanical agitation

    SciTech Connect

    Kiser, D.L.

    1981-01-01

    Twenty-two high-level waste storage tanks at the Savannah River Plant are to be retired in the tank replacement/waste transfer program. The salt-removal portion of this program requires dissolution of about 19 million liters of salt cake. Steam circulation jets were originally proposed to dissolve the salt cake. However, the jets heated the waste tank to 80 to 90/sup 0/C. This high temperature required a long cooldown period before transfer of the supernate by jet, and increased the risk of stress-corrosion cracking in these older tanks. A bench-scale investigation at the Savannah River Laboratory developed two alternatives to steam-jet circulation. One technique was density-driven circulation, which in bench tests dissolved salt at the same rate as a simulated steam circulation jet but at a lower temperature. The other technique was mechanical agitation, which dissolved the salt cake faster and required less fresh water than either density-driven circulation or the simulated steam circulation jet. Tests in an actual waste tank verified bench-scale results and demonstrated the superiority of mechanical agitation.

  2. Expected environments in high-level nuclear waste and spent fuel repositories in salt

    SciTech Connect

    Claiborne, H.C.; Rickertsen, L.D., Graham, R.F.

    1980-08-01

    The purpose of this report is to describe the expected environments associated with high-level waste (HLW) and spent fuel (SF) repositories in salt formations. These environments include the thermal, fluid, pressure, brine chemistry, and radiation fields predicted for the repository conceptual designs. In this study, it is assumed that the repository will be a room and pillar mine in a rock-salt formation, with the disposal horizon located approx. 2000 ft (610 m) below the surface of the earth. Canistered waste packages containing HLW in a solid matrix or SF elements are emplaced in vertical holes in the floor of the rooms. The emplacement holes are backfilled with crushed salt or other material and sealed at some later time. Sensitivity studies are presented to show the effect of changing the areal heat load, the canister heat load, the barrier material and thickness, ventilation of the storage room, and adding a second row to the emplacement configuration. The calculated thermal environment is used as input for brine migration calculations. The vapor and gas pressure will gradually attain the lithostatic pressure in a sealed repository. In the unlikely event that an emplacement hole will become sealed in relatively early years, the vapor space pressure was calculated for three scenarios (i.e., no hole closure - no backfill, no hole closure - backfill, and hole closure - no backfill). It was assumed that the gas in the system consisted of air and water vapor in equilibrium with brine. A computer code (REPRESS) was developed assuming that these changes occur slowly (equilibrium conditions). The brine chemical environment is outlined in terms of brine chemistry, corrosion, and compositions. The nuclear radiation environment emphasized in this report is the stored energy that can be released as a result of radiation damage or crystal dislocations within crystal lattices.

  3. Radioactive waste isolation in salt: Peer review of the Golder Associates draft test plan for in situ testing in an exploratory shaft in salt

    SciTech Connect

    Hambley, D.F.; Mraz, D.Z.; Unterberter, R.R.; Stormont, J.C.; Neuman, S.P.; Russell, J.E.; Jacoby, C.H.; Hull, A.B.; Brady, B.H.G.; Ditmars, J.D.

    1987-01-01

    This report documents the peer review conducted by Argonne National Laboratory of a document entitled ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared for Battelle Memorial Institute's Office of Nuclear Waste Isolation by Golder Associates, Inc. In general, the peer review panelists found the test plan to be technically sound, although some deficiencies were identified. Recommendations for improving the test plan are presented in this review report. A microfiche copy of the following unpublished report is attached to the inside back cover of this report: ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared by Golder Associates, Inc., for Office of Nuclear Waste Isolation, Battelle Memorial Institute, Columbus, Ohio (March 1985).

  4. Dechlorination and stabilization of radioactive chloride salt waste in a molten state

    SciTech Connect

    In-Tae Kim; Hwan-Seo Park; Yong-Jun Cho; Hwan-Young Kim; Seong-Won Park; Eung-Ho Kim [Korea Atomic Energy Research Institute, 150 Deokjin-dong, Yuseong, Daejeon, 305-353 (Korea, Republic of)

    2007-07-01

    This study suggests a new method to stabilize the molten salt wastes generated from he pyro-processing of a LWR spent fuel. Using a conventional sol-gel process, an inorganic material (SiO{sub 2}-Al{sub 2}O{sub 3}-P{sub 2}O{sub 5}, SAP) reactive to metal chlorides was prepared. In this paper, the reactivity of the SAP on the metal chlorides at 650-850 deg. C, the thermal stability of the reaction products and their leach-resistance under the PCT-A leach test were investigated. In the SAP, three different kinds of chains are available; Si-O-Si (main chain), Si-O-Al (side chain) and Al-O-P/P-O-P (reactive chain). Alkali metal chlorides were converted into metal aluminosilicate (Li{sub x}Al{sub x}Si{sub 1-x}O{sub 2-x}) and metal phosphate(Li{sub 3}PO{sub 4} and Cs{sub 2}AlP{sub 3}O{sub 10}) while the alkaline earth and rare earth chlorides were changed into only metal phosphates (Sr{sub 5}(PO{sub 4}){sub 3}Cl and CePO{sub 4}). The conversion rate was about 96% at a salt waste/SAP weight ratio of 0.5 and a weight loss up to 1100 deg. C measured by the thermo-gravimetric analysis was below 1 Wt%. The leach rates of Cs and Sr under the PCT-A leaching condition were about 10{sup -2} and 10{sup -4} g/m{sup 3}.day, respectively. From these results, it could be concluded that the SAP developed in this study can be considered as an effective stabilizer for metal chlorides and the method of using the SAP could provide a chance to minimize the final waste volume to be disposed off. (authors)

  5. A thermodynamic approach on vapor-condensation of corrosive salts from flue gas on boiler tubes in waste incinerators

    Microsoft Academic Search

    Nobuo Otsuka

    2008-01-01

    Thermodynamic equilibrium calculation was conducted to understand the effects of tube wall temperature, flue gas temperature, and waste chemistry on the type and amount of vapor-condensed “corrosive” salts from flue gas on superheater and waterwall tubes in waste incinerators. The amount of vapor-condensed compounds from flue gases at 650–950°C on tube walls at 350–850°C was calculated, upon combustion of 100g

  6. Technetium removal column flow testing with alkaline, high salt, radioactive tank waste

    SciTech Connect

    Blanchard, D.L. Jr.; Kurath, D.E.; Golcar, G.R. [Pacific Northwest National Lab., Richland, WA (United States); Conradson, S.D. [Los Alamos National Lab., NM (United States)

    1996-09-30

    This report describes two bench-scale column tests conducted to demonstrate the removal of Tc-99 from actual alkaline high salt radioactive waste. The waste used as feed for these tests was obtained from the Hanford double shell tank AW-101, which contains double shell slurry feed (DSSF). The tank sample was diluted to approximately 5 M Na with water, and most of the Cs-137 was removed using crystalline silicotitanates. The tests were conducted with two small columns connected in series, containing, 10 mL of either a sorbent, ABEC 5000 (Eichrom Industries, Inc.), or an anion exchanger Reillex{trademark}-HPQ (Reilly Industries, Inc.). Both materials are selective for pertechnetate anion (TcO{sub 4}{sup -}). The process steps generally followed those expected in a full-scale process and included (1) resin conditioning, (2) loading, (3) caustic wash to remove residual feed and prevent the precipitation of Al(OH){sub 3}, and (4) elution. A small amount of Tc-99m tracer was added as ammonium pertechnetate to the feed and a portable GEA counter was used to closely monitor the process. Analyses of the Tc-99 in the waste was performed using ICP-MS with spot checks using radiochemical analysis. Technetium x-ray absorption spectroscopy (XAS) spectra of 6 samples were also collected to determine the prevalence of non-pertechnetate species [e.g. Tc(IV)].

  7. Splicing mutation in CYP21 associated with delayed presentation of salt-wasting congenital adrenal hyperplasia

    SciTech Connect

    Kohn, B.; Patel, S.V.; Pelczar, J.V. [North Shore Univ. Hospital, Manhasset, NY (United States)] [and others

    1995-07-03

    Patients with salt-wasting congenital adrenal hyperplasia (SW-CAH) most commonly carry an A-G transition at nucleotide 656 (nt 656 A{r_arrow}G), causing abnormal splicing of exons 2 and 3 in CYP21, the gene encoding active steroid 21-hydroxylase. Affected infants are severely deficient in cortisol and aldosterone, and usually come to medical attention during the neonatal period. We report on 2 affected boys, homozygous for the nt 656 mutation, who thrived in early infancy, but suffered salt-wasting crises unusually late in infancy, at 3.5 and 5.5 months, respectively. Laboratory studies at presentation showed hyponatremia, hyperkalemia, dehydration, and acidosis; serum aldosterone was low in spite of markedly elevated plasma renin activity. Basal 17-hydroxyprogesterone levels were only moderately elevated, yet the stimulated levels were more typical of severe, classic CAH due to 21-hydroxylase deficiency. Genomic DNA from the patients was analyzed. Southern blot showed no major deletions or rearrangements. CYP21-specific amplification by polymerase chain reaction, coupled with allele-specific hybridization using wild-type and mutant probes at each of 9 sites for recognized disease-causing mutations, revealed a single, homozygous mutation in each patient: nt 656 A{r_arrow}G. These results were confirmed by sequence analysis. We conclude that the common nt 656 A{r_arrow}G mutation is sometimes associated with delayed phenotypic expression of SW-CAH. We speculate that variable splicing of the mutant CYP21 may modify the clinical manifestation of this disease. 22 refs., 1 fig., 1 tab.

  8. Modeling of the T S D E Heater Test to Investigate Crushed Salt Reconsolidation and Rock Salt Creep for the Underground Disposal of High-Level Nuclear Waste

    NASA Astrophysics Data System (ADS)

    Blanco Martin, L.; Rutqvist, J.; Birkholzer, J. T.; Wolters, R.; Lux, K. H.

    2014-12-01

    Rock salt is a potential medium for the underground disposal of nuclear waste because it has several assets, in particular its water and gas tightness in the undisturbed state, its ability to heal induced fractures and its high thermal conductivity as compared to other shallow-crustal rocks. In addition, the run-of-mine, granular salt, may be used to backfill the mined open spaces. We present simulation results associated with coupled thermal, hydraulic and mechanical processes in the TSDE (Thermal Simulation for Drift Emplacement) experiment, conducted in the Asse salt mine in Germany [1]. During this unique test, conceived to simulate reference repository conditions for spent nuclear fuel, a significant amount of data (temperature, stress changes and displacements, among others) was measured at 20 cross-sections, distributed in two drifts in which a total of six electrical heaters were emplaced. The drifts were subsequently backfilled with crushed salt. This test has been modeled in three-dimensions, using two sequential simulators for flow (mass and heat) and geomechanics, TOUGH-FLAC and FLAC-TOUGH [2]. These simulators have recently been updated to accommodate large strains and time-dependent rheology. The numerical predictions obtained by the two simulators are compared within the framework of an international benchmark exercise, and also with experimental data. Subsequently, a re-calibration of some parameters has been performed. Modeling coupled processes in saliniferous media for nuclear waste disposal is a novel approach, and in this study it has led to the determination of some creep parameters that are very difficult to assess at the laboratory-scale because they require extremely low strain rates. Moreover, the results from the benchmark are very satisfactory and validate the capabilities of the two simulators used to study coupled thermal, mechanical and hydraulic (multi-component, multi-phase) processes relative to the underground disposal of high-level nuclear waste in rock salt. References: [1] Bechthold et al., 1999. BAMBUS-I Project. Euratom, Report EUR19124-EN. [2] Blanco Martín et al., 2014. Comparison of two sequential simulators to investigate thermal-hydraulic-mechanical processes related to nuclear waste isolation in saliniferous formations. In preparation.

  9. Conceptual design of retrieval systems for emplaced transuranic waste containers in a salt bed depository. Final report

    SciTech Connect

    Fogleman, S.F.

    1980-04-01

    The US Department of Energy and the Nuclear Regulatory Commission have jurisdiction over the nuclear waste management program. Design studies were previously made of proposed repository site configurations for the receiving, processing, and storage of nuclear wastes. However, these studies did not provide operational designs that were suitable for highly reliable TRU retrieval in the deep geologic salt environment for the required 60-year period. The purpose of this report is to develop a conceptual design of a baseline retrieval system for emplaced transuranic waste containers in a salt bed depository. The conceptual design is to serve as a working model for the analysis of the performance available from the current state-of-the-art equipment and systems. Suggested regulations would be based upon the results of the performance analyses.

  10. SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING

    SciTech Connect

    Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

    2011-01-12

    This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be released. Installation requirements were also determined for a transfer pump which will remove tank contents, and which is also required to not disturb sludge. Testing techniques and test results for both types of pumps are presented.

  11. Radioactive waste isolation in salt: special advisory report on the status of the Office of Nuclear Waste Isolation's plans for repository performance assessment

    SciTech Connect

    Ditmars, J.D.; Walbridge, E.W.; Rote, D.M.; Harrison, W.; Herzenberg, C.L.

    1983-10-01

    Repository performance assessment is analysis that identifies events and processes that might affect a repository system for isolation of radioactive waste, examines their effects on barriers to waste migration, and estimates the probabilities of their occurrence and their consequences. In 1983 Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) prepared two plans - one for performance assessment for a waste repository in salt and one for verification and validation of performance assessment technology. At the request of the US Department of Energy's Salt Repository Project Office (SRPO), Argonne National Laboratory reviewed those plans and prepared this report to advise SRPO of specific areas where ONWI's plans for performance assessment might be improved. This report presents a framework for repository performance assessment that clearly identifies the relationships among the disposal problems, the processes underlying the problems, the tools for assessment (computer codes), and the data. In particular, the relationships among important processes and 26 model codes available to ONWI are indicated. A common suggestion for computer code verification and validation is the need for specific and unambiguous documentation of the results of performance assessment activities. A major portion of this report consists of status summaries of 27 model codes indicated as potentially useful by ONWI. The code summaries focus on three main areas: (1) the code's purpose, capabilities, and limitations; (2) status of the elements of documentation and review essential for code verification and validation; and (3) proposed application of the code for performance assessment of salt repository systems. 15 references, 6 figures, 4 tables.

  12. New Design for an HLW Repository (for Spent Fuel and Waste from Reprocessing) in a Salt Formation in Germany - 12213

    SciTech Connect

    Bollingerfehr, Wilhelm; Filbert, Wolfgang; Lerch, Christian; Mueller-Hoeppe, Nina [DBE TECHNOLOGY GmbH, Peine (Germany); Charlier, Frank [International nuclear safety engineering GmbH, Aachen (Germany)

    2012-07-01

    In autumn 2010, after a 10-year moratorium, exploration was resumed in Gorleben, the potential site for a German HLW repository. At the same time, the Federal Government launched a two-year preliminary safety analysis to assess whether the salt dome at Gorleben is suitable to host all heat-generating radioactive waste generated by German NPPs based on the waste amounts expected at that time. The revised Atomic Energy Act of June 2011 now stipulates a gradual phase-out of nuclear energy production by 2022, which is 13 years earlier than expected in 2010. A repository design was developed which took into account an updated set of data on the amounts and types of expected heat-generating waste, the documented results of the exploration of the Gorleben salt dome, and the new 'Safety Requirements Governing the Final Disposal of Heat-Generating Radioactive Waste' of 30 September, 2010. The latter has a strong influence on the conceptual designs as it requires that retrievability of all waste containers is possible within the repository lifetime. One design considered that all waste containers will be disposed of in horizontal drifts of a geologic repository, while the other design considered that all waste containers will be disposed of in deep vertical boreholes. For both options (emplacement in drifts/emplacement in vertical boreholes), the respective design includes a selection of waste containers, the layout of drifts, respectively lined boreholes, a description of emplacement fields, and backfilling and sealing measures. The design results were described and displayed and the differences between the two main concepts were elaborated and discussed. For the first time in both repository designs the requirement was implemented to retrieve waste canisters during the operational phase. The measures to fulfill this requirement and eventually the consequences were highlighted. It was pointed out that there arises the need to keep transport- and storage casks in adequate numbers and interim storage facilities available until the repository is closed. (authors)

  13. Costs for off-site disposal of nonhazardous oil field wastes: Salt caverns versus other disposal methods

    SciTech Connect

    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.

  14. Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on an issues hierarchy and data needs for site characterization

    SciTech Connect

    Harrison, W.; Fenster, D.F.; Ditmars, J.D.; Paddock, R.A.; Rote, D.M.; Hambley, D.F.; Seitz, M.G.; Hull, A.B.

    1986-12-01

    At the request of the Salt Repository Project (SRPO), Argonne National Laboratory conducted an independent peer review of a report by the Battelle Office of Nuclear Waste Isolation entitled ''Salt Repository Project Issues Hierarchy and Data Needs for Site Characterization (Draft).'' This report provided a logical structure for evaluating the outstanding questions (issues) related to selection and licensing of a site as a high-level waste repository. It also provided a first estimate of the information and data necessary to answer or resolve those questions. As such, this report is the first step in developing a strategy for site characterization. Microfiche copies of ''Draft Issues Hierarchy, Resolution Strategy, and Information Needs for Site Characterization and Environmental/Socioeconomic Evaluation - July, 1986'' and ''Issues Hierarchy and Data Needs for Site Characterization - February, 1985'' are included in the back pocket of this report.

  15. Highlights of the Salt Extraction Process

    NASA Astrophysics Data System (ADS)

    Abbasalizadeh, Aida; Seetharaman, Seshadri; Teng, Lidong; Sridhar, Seetharaman; Grinder, Olle; Izumi, Yukari; Barati, Mansoor

    2013-11-01

    This article presents the salient features of a new process for the recovery of metal values from secondary sources and waste materials such as slag and flue dusts. It is also feasible in extracting metals such as nickel and cobalt from ores that normally are difficult to enrich and process metallurgically. The salt extraction process is based on extraction of the metals from the raw materials by a molten salt bath consisting of NaCl, LiCl, and KCl corresponding to the eutectic composition with AlCl3 as the chlorinating agent. The process is operated in the temperature range 973 K (700°C) to 1173 K (900°C). The process was shown to be successful in extracting Cr and Fe from electric arc furnace (EAF) slag. Electrolytic copper could be produced from copper concentrate based on chalcopyrite in a single step. Conducting the process in oxygen-free atmosphere, sulfur could be captured in the elemental form. The method proved to be successful in extracting lead from spent cathode ray tubes. In order to prevent the loss of AlCl3 in the vapor form and also chlorine gas emission at the cathode during the electrolysis, liquid aluminum was used. The process was shown to be successful in extracting Nd and Dy from magnetic scrap. The method is a highly promising process route for the recovery of strategic metals. It also has the added advantage of being environmentally friendly.

  16. An optimal method for phosphorylation of rare earth chlorides in LiCl-KCl eutectic based waste salt

    NASA Astrophysics Data System (ADS)

    Eun, H. C.; Kim, J. H.; Cho, Y. Z.; Choi, J. H.; Lee, T. K.; Park, H. S.; Park, G. I.

    2013-11-01

    A study on an optimal method for the phosphorylation of rare earth chlorides in LiCl-KCl eutectic waste salt generated the pyrochemical process of spent nuclear fuel was performed. A reactor with a pitched four blade impeller was designed to create a homogeneous mixing zone in LiCl-KCl eutectic salt. A phosphorylation test of NdCl3 in the salt was carried out by changing the operation conditions (operation temperature, stirring rate, agent injection amount). Based on the results of the test, a proper operation condition (450 °C, 300 rpm, 1 eq. of phosphorylation agent) for over a 0.99 conversion ratio of NdCl3 to NdPO4 was determined. Under this condition, multi-component rare earth (La, Ce, Pr, Nd, Sm, Eu, Gd, Y) chlorides were effectively converted into phosphate forms. It was confirmed that the existing regeneration process of LiCl-KCl eutectic waste salt can be greatly improved and simplified through these phosphorylation test results.

  17. Syndrome of Inappropriate Antidiuretic Hormone Secretion and Cerebral/Renal Salt Wasting Syndrome: Similarities and Differences

    PubMed Central

    Oh, Ji Young; Shin, Jae Il

    2015-01-01

    Hyponatremia (sodium levels of <135?mEq/L) is one of the most common electrolyte imbalances in clinical practice, especially in patients with neurologic diseases. Hyponatremia can cause cerebral edema and brain herniation; therefore, prompt diagnosis and proper treatment is important in preventing morbidity and mortality. Among various causes of hyponatremia, diagnosing syndrome of inappropriate antidiuretic hormone secretion (SIADH) and cerebral/renal salt wasting syndrome (C/RSW) is difficult due to many similarities. SIADH is caused by excess of renal water reabsorption through inappropriate antidiuretic hormone secretion, and fluid restriction is the treatment of choice. On the other hand, C/RSW is caused by natriuresis, which is followed by volume depletion and negative sodium balance and replacement of water and sodium is the mainstay of treatment. Determinating volume status in hyponatremic patients is the key point in differential between SIADH and C/RSW. However, in most situations, differential diagnosis of these two diseases is difficult because they overlap in many clinical and laboratory aspects, especially to assess differences in volume status of these patients. Although distinction between the SIADH and C/RSW is difficult, improvement of hypouricemia and an increased fractional excretion of uric acid after the correction of hyponatremia in SIADH, not in C/RSW, may be one of the helpful points in discriminating the two diseases. In this review, we compare these two diseases regarding the pathophysiologic mechanisms, diagnosis, and therapeutic point of view. PMID:25657991

  18. Autosomal Dominant Pseudohypoaldosteronism Type 1 in an Infant with Salt Wasting Crisis Associated with Urinary Tract Infection and Obstructive Uropathy

    PubMed Central

    Bowden, Sasigarn A.; Cozzi, Corin; Hickey, Scott E.; Thrush, Devon Lamb; Astbury, Caroline; Nuthakki, Sushma

    2013-01-01

    Type 1 pseudohypoaldosteronism (PHA1) is a salt wasting syndrome caused by renal resistance to aldosterone. Primary renal PHA1 or autosomal dominant PHA1 is caused by mutations in mineralocorticoids receptor gene (NR3C2), while secondary PHA1 is frequently associated with urinary tract infection (UTI) and/or urinary tract malformations (UTM). We report a 14-day-old male infant presenting with severe hyperkalemia, hyponatremic dehydration, metabolic acidosis, and markedly elevated serum aldosterone level, initially thought to have secondary PHA1 due to the associated UTI and posterior urethral valves. His serum aldosterone remained elevated at 5 months of age, despite resolution of salt wasting symptoms. Chromosomal microarray analysis revealed a deletion of exons 3–5 in NR3C2 in the patient and his asymptomatic mother who also had elevated serum aldosterone level, confirming that he had primary or autosomal dominant PHA1. Our case raises the possibility that some patients with secondary PHA1 attributed to UTI and/or UTM may instead have primary autosomal dominant PHA1, for which genetic testing should be considered to identify the cause, determine future recurrence risk, and possibly prevent the life-threatening salt wasting in a subsequent family member. Future clinical research is needed to investigate the potential overlapping between secondary PHA1 and primary autosomal dominant PHA1. PMID:24455331

  19. Alternative methods to manage waste salt from repository excavation in the Deaf Smith County and Swisher County locations, Texas: A scoping study: Technical report. [Salt and salt-laden material

    SciTech Connect

    Not Available

    1987-01-01

    This report describes and qualitatively evaluates eight options for managing the large volumes of salt and salt-laden rock that would result from the excavation of a high-level radioactive waste repository in Deaf Smith County or Swisher County, Texas. The options are: distribution for commercial use; ocean disposal; deep-well injection; disposal in multilevel mines on the site; disposal in abandoned salt mines off the site; disposal off the site in abandoned mines developed for minerals other than salt; disposal in excavated landfills; and surface disposal on alkali flats. The main features of each option are described, as well as the associated environmental and economic impacts, and regulatory constraints. The options are evaluated in terms of 11 factors that jointly constitute a test of relative suitability. The results of the evaluation and implications for further study are indicated. This document does not consider or include the actual numbers, findings, or conclusions contained in the final Deaf Smith County Environmental Assessment (DOE, 1986). 43 refs., 8 tabs.

  20. Waste Stream Generated and Waste Disposal Plans for Molten Salt Reactor Experiment at Oak Ridge National Laboratory

    SciTech Connect

    Haghighi, M. H.; Szozda, R. M.; Jugan, M. R.

    2002-02-26

    The Molten Salt Reactor Experiment (MSRE) site is located in Tennessee, on the U.S. Department of Energy (DOE) Oak Ridge Reservation (ORR), south of the Oak Ridge National Laboratory (ORNL) main plant across Haw Ridge in Melton Valley. The MSRE was run by ORNL to demonstrate the desirable features of the molten-salt concept in a practical reactor that could be operated safely and reliably. It introduced the idea of a homogeneous reactor using fuel salt media and graphite moderation for power and breeder reactors. The MSRE reactor and associated components are located in cells beneath the floor in the high-bay area of Building 7503 (Figure 1). The reactor was operated from June 1965 to December 1969. When the reactor was shut down, fuel salt was drained from the reactor circuit to two drain tanks. A ''clean'' salt was then circulated through the reactor as a decontamination measure and drained to a third drain tank. When operations ceased, the fuel and flush salts were allowed t o cool and solidify in the drain tanks. At shutdown, the MSRE facility complex was placed in a surveillance and maintenance program. As a result of the S&M program, it was discovered in 1994 that gaseous uranium (233U/232U) hexafluoride (UF6) had moved throughout the MSRE process systems. The UF6 was generated when radiolysis of the fluorine salts caused the individual constituents to dissociate to their component atoms, including free fluorine.Some of the free fluorine combined with uranium fluorides (UF4) in the salt to form UF6. UF6 is gaseous at slightly above ambient temperatures; thus, periodic heating of the fuel salts (which was intended to remedy the radiolysis problems) and simple diffusion had allowed the UF6 to move out of the salt and into the process systems of MSRE.

  1. Measurement of unsaturated hydraulic properties of salt cake simulant relevant to hanford and SRS high-level waste tanks using a pilot-scale setup

    Microsoft Academic Search

    G. Tachiev; G. Yaari; S. Long; R. Srivastava; D. Roelant

    2007-01-01

    Closure of the remaining tanks and final disposition of the radioactive waste is a high priority task at both Savannah River Site (SRS) and Hanford. The radioactive waste in the tanks are generally found in layers: supernate (on top) containing soluble fission products, and salt-cake and sludge (on the bottom of the tank) containing insoluble actinides. One strategy for minimizing

  2. An analysis of salt and moisture deposition on the air sampling probes in the exhaust shaft of the waste isolation pilot plant 

    E-print Network

    Weaver, Gregg Shelton

    1996-01-01

    A study was performed to determine the source of moist salt formations on air sampling , probes at the top of the exhaust shaft used in ventilating the waste repository at the Waste Isolation Pilot Plant (WIPP). An earlier study by Texas A&M Univ...

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

    DOEpatents

    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.

  4. Preservation of artifacts in salt mines as a natural analog for the storage of transuranic wastes at the WIPP repository

    SciTech Connect

    Martell, M.A.; Hansen, F.; Weiner, R.

    1998-10-01

    Use of nature`s laboratory for scientific analysis of complex systems is a largely untapped resource for understanding long-term disposal of hazardous materials. The Waste Isolation Pilot Plant (WIPP) in the US is a facility designed and approved for storage of transuranic waste in a salt medium. Isolation from the biosphere must be ensured for 10,000 years. Natural analogs provide a means to interpret the evolution of the underground disposal setting. Investigations of ancient sites where manmade materials have experienced mechanical and chemical processes over millennia provide scientific information unattainable by conventional laboratory methods. This paper presents examples of these pertinent natural analogs, provides examples of features relating to the WIPP application, and identifies potential avenues of future investigations. This paper cites examples of analogical information pertaining to the Hallstatt salt mine in Austria and Wieliczka salt mine in Poland. This paper intends to develop an appreciation for the applicability of natural analogs to the science and engineering of a long-term disposal facility in geomedia.

  5. Recovery of soluble chloride salts from the wastewater generated during the washing process of municipal solid wastes incineration fly ash.

    PubMed

    Tang, Hailong; Erzat, Aris; Liu, Yangsheng

    2014-01-01

    Water washing is widely used as the pretreatment method to treat municipal solid waste incineration fly ash, which facilitates the further solidification/stabilization treatment or resource recovery of the fly ash. The wastewater generated during the washing process is a kind of hydrosaline solution, usually containing high concentrations of alkali chlorides and sulphates, which cause serious pollution to environment. However, these salts can be recycled as resources instead of discharge. This paper explored an effective and practical recovery method to separate sodium chloride, potassium chloride, and calcium chloride salts individually from the hydrosaline water. In laboratory experiments, a simulating hydrosaline solution was prepared according to composition of the waste washing water. First, in the three-step evaporation-crystallization process, pure sodium chloride and solid mixture of sodium and potassium chlorides were obtained separately, and the remaining solution contained potassium and calcium chlorides (solution A). And then, the solid mixture was fully dissolved into water (solution B obtained). Finally, ethanol was added into solutions A and B to change the solubility of sodium, potassium, and calcium chlorides within the mixed solvent of water and ethanol. During the ethanol-adding precipitation process, each salt was separated individually, and the purity of the raw production in laboratory experiments reached about 90%. The ethanol can be recycled by distillation and reused as the solvent. Therefore, this technology may bring both environmental and economic benefits. PMID:25176491

  6. Results of screening activities in salt states prior to the enactment of the Nationall Waste Policy Act

    SciTech Connect

    Carbiener, W.A.

    1983-01-01

    The identification of potential sites for a nuclear waste repository through screening procedures in the salt states is a well-established, deliberate process. This screening process has made it possible to carry out detailed studies of many of the most promising potential sites, and general studies of all the sites, in anticipation of the siting guidelines specified in the Nuclear Waste Policy Act. The screening work completed prior to the passage of the Act allowed the Secretary of Energy to identify seven salt sites as potentially acceptable under the provisions of Section 116(a) of the Act. These sites were formally identified by letters from Secretary Hodel to the states of Texas, Utah, Mississippi, and Louisiana on February 2, 1983. The potentially acceptable salt sites were in Deaf Smith and Swisher Counties in Texas; Davis and Lavender Canyons in the Gibson Dome location in Utah; Richton and Cypress Creek Domes in Mississippi; and Vacherie Dome in Louisiana. Further screening will include comparison of each potentially acceptable site against disqualification factors and selection of a preferred site in each of the three geohydrologic settings from those remaining, in accordance with the siting guidelines. These steps will be documented in statutory Environmental Assessments prepared for each site to be nominated for detailed characterization. 9 references.

  7. Emissions from energetic material waste during the Molten Salt Destruction process

    SciTech Connect

    Watkins, B.E.; Upadhye, R.S.; Pruneda, C.O.; Brummond, W.A.

    1994-07-05

    The Molten Salt Destruction (MSD) process is an alternative to open burn/open detonation for destroying energetic materials; MSD has inherently low gaseous emissions, and the salt bath can scrub both acidic gases and particulates. It was demonstrated that high explosives and a liquid propellant can be safely and completely destroyed using MSD. Gaseous emissions of NOx and CO are very low. Nitrate builds up in the salt bath when nitrate-rich materials are destroyed, but addition fuel reduces the nitrate to NO. A program has been begun to add catalytic materials to the bed to further reduce emissions; a small molten salt bath has been constructed for chemical kinetic studies.

  8. Radioactive waste isolation in salt: Peer review of the Fluor Technology, Inc. , report and position paper concerning waste emplacement mode and its effect on repository conceptual design

    SciTech Connect

    Hambley, D.F.; Russell, J.E.; Whitfield, R.G.; McGinnis, L.D.; Harrison, W.; Jacoby, C.H.; Bump, T.R.; Mraz, D.Z.; Busch, J.S.; Fischer, L.E.

    1987-02-01

    Recommendations for revising the Fluor Technology, Inc., draft position paper entitled Evaluation of Waste Emplacement Mode and the final report entitled Waste Package/Repository Impact Study include: reevaluate the relative rankings for the various emplacement modes; delete the following want objectives: maximize ability to locate the package horizon because sufficient flexibility exists to locate rooms in the relatively clean San Andres Unit 4 Salt and maximize far-field geologic integrity during retrieval because by definition the far field will be unaffected by thermal and stress perturbations caused by remining; give greater emphasis to want objectives regarding cost and use of present technology; delete the following statements from pages 1-1 and 1-2 of the draft position paper: ''No thought or study was given to the impacts of this configuration (vertical emplacement) on repository construction or short and long-term performance of the site'' and ''Subsequent salt repository designs adopted the vertical emplacement configuration as the accepted method without further evaluation.''; delete App. E and lines 8-17 of page 1-4 of the draft position paper because they are inappropriate; adopt a formal decision-analysis procedure for the 17 identified emplacement modes; revise App. F of the impact study to more accurately reflect current technology; consider designing the underground layout to take advantage of stress-relief techniques; consider eliminating reference to fuel assemblies <10 yr ''out-of-reactor''; model the temperature distribution, assuming that the repository is constructed in an infinitely large salt body; state that the results of creep analyses must be considered tentative until they can be validated by in situ measurements; and reevaluate the peak radial stresses on the waste package so that the calculated stress conditions more closely approximate expected in situ conditions.

  9. Melting of the precipitated ice IV in LiCl aqueous solution and polyamorphism of water.

    PubMed

    Mishima, Osamu

    2011-12-01

    Melting of the precipitated ice IV in supercooled LiCl-H(2)O solution was studied in the range of 0-0.6 MPa and 160-270 K. Emulsified solution was used to detect this metastable transition. Ice IV was precipitated from the aqueous solution of 2.0 mol % LiCl (or 4.8 mol % LiCl) in each emulsion particle at low-temperature and high-pressure conditions, and the emulsion was decompressed at different temperatures. The melting of ice IV was detected from the temperature change of the emulsified sample during the decompression. There was an apparently sudden change in the slope of the ice IV melting curve (liquidus) in the pressure-temperature diagram. At the high-pressure and high-temperature side of the change, the solute-induced freezing point depression was observed. At the low-pressure and low-temperature side, ice IV transformed into ice Ih on the decompression, and the transition was almost unrelated to the concentration of LiCl. These experimental results were roughly explained by the presumed existence of two kinds of liquid water (low-density liquid water and high-density liquid water), or polyamorphism in water, and by the simple assumption that LiCl dissolved maily in high-density liquid water. PMID:21736291

  10. IR spectroscopy of aqueous alkali halide solutions: Pure salt-solvated water spectra and hydration numbers

    Microsoft Academic Search

    Jean-Joseph Max; Camille Chapados

    2001-01-01

    Extrapolation techniques were used to obtain pure salt-solvated water spectra from the attenuated total reflection infrared spectra (ATR-IR) of aqueous solutions of the nine alkali halide salts LiCl, NaCl, KCl, CsCl, NaBr, KBr, NaI, KI, and CsI and the alkaline-earth chloride salt MgCl2. These salts ionize completely in water. The ions by themselves do not absorb in the IR, but

  11. Water uptake by salts during the electrolyte processing for thermal batteries

    Microsoft Academic Search

    Patrick Masset; Jean-Yves Poinso; Jean-Claude Poignet

    2004-01-01

    Water uptake of single salts and electrolytes were measured in industrial conditions (dry-room). The water uptake rate ? (gh?1cm?2) was expressed with respect to the apparent area of contact of the salt with atmosphere of the dry room. The water uptake by potassium-based salts was very low. LiF and LiCl salts were found to behave similarly. For LiBr- and LiI-based

  12. Quantum Theoretical Study of KCl and LiCl Clusters

    NASA Astrophysics Data System (ADS)

    Koetter, Ted; Hira, Ajit; Salazar, Justin; Jaramillo, Danelle

    2014-03-01

    This research focuses on the theoretical study of molecular clusters to examine the chemical properties of small KnClnandLinCln clusters (n = 2 - 20). The potentially important role of these molecular species in biochemical and medicinal processes is well known. This work applies the hybrid ab initio methods of quantum chemistry to derive the different alkali-halide (MnHn) geometries. Of particular interest is the competition between hexagonal ring geometries and rock salt structures. Electronic energies, rotational constants, dipole moments, and vibrational frequencies for these geometries are calculated. Magic numbers for cluster stability are identified and are related to the property of cluster compactness. Mapping of the singlet, triplet, and quintet, potential energy surfaces is performed. Calculations were performed to examine the interactions of these clusters with some atoms and molecules of biological interest, including O, O2, and Fe. Potential design of new medicinal drugs is explored.

  13. Salton Sea Geothermal Field, California, as a near-field natural analog of a radioactive waste repository in salt

    SciTech Connect

    Elders, W.A.; Cohen, L.H.

    1983-11-01

    Since high concentrations of radionuclides and high temperatures are not normally encountered in salt domes or beds, finding an exact geologic analog of expected near-field conditions in a mined nuclear waste repository in salt will be difficult. The Salton Sea Geothermal Field, however, provides an opportunity to investigate the migration and retardation of naturally occurring U, Th, Ra, Cs, Sr and other elements in hot brines which have been moving through clay-rich sedimentary rocks for up to 100,000 years. The more than thirty deep wells drilled in this field to produce steam for electrical generation penetrate sedimentary rocks containing concentrated brines where temperatures reach 365/sup 0/C at only 2 km depth. The brines are primarily Na, K, Ca chlorides with up to 25% of total dissolved solids; they also contain high concentrations of metals such as Fe, Mn, Li, Zn, and Pb. This report describes the geology, geophysics and geochemistry of this system as a prelude to a study of the mobility of naturally occurring radionuclides and radionuclide analogs within it. The aim of this study is to provide data to assist in validating quantitative models of repository behavior and to use in designing and evaluating waste packages and engineered barriers. 128 references, 33 figures, 13 tables.

  14. Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation

    SciTech Connect

    Sridharan, Kumar [Univ. of Wisconsin, Madison, WI (United States); Allen, Todd [Univ. of Wisconsin, Madison, WI (United States); Anderson, Mark [Univ. of Wisconsin, Madison, WI (United States); Simpson, Mike [Idaho National Lab., (United States)

    2012-11-30

    This project addresses both practical and fundamental scientific issues of direct relevance to operational challenges of the molten LiCl-KCl salt pyrochemical process, while providing avenues for improvements in the process. In order to understand the effects of the continually changing composition of the molten salt bath during the process, the project team will systematically vary the concentrations of rare earth surrogate elements, lanthanum, cerium, praseodymium, and neodymium, which will be added to the molten LiCl-KCl salt. They will also perform a limited number of focused experiments by the dissolution of depleted uranium. All experiments will be performed at 500 deg C. The project consists of the following tasks. Researchers will measure density of the molten salts using an instrument specifically designed for this purpose, and will determine the melting points with a differential scanning calorimeter. Knowledge of these properties is essential for salt mass accounting and taking the necessary steps to prevent melt freezing. The team will use cyclic voltammetry studies to determine redox potentials of the rare earth cations, as well as their diffusion coefficients and activities in the molten LiCl-KCl salt. In addition, the team will perform anodic stripping voltammetry to determine the concentration of the rare earth elements and their solubilities, and to develop the scientific basis for an on-line diagnostic system for in situ monitoring of the cation species concentration (rare earths in this case). Solubility and activity of the cation species are critically important for the prediction of the salt's useful lifetime and disposal.

  15. Separation of CsCl from a Ternary CsCl-LiCl-KCl Salt via a Melt Crystallization Technique for Pyroprocessing Waste Minimization

    SciTech Connect

    Ammon Williams; Supathorn Phongikaroon; Michael Simpson

    2013-02-01

    A parametric study has been conducted to identify the effects of several parameters on the separation of CsCl from molten LiCl-KCl salt via a melt crystallization process. A reverse vertical Bridgman technique was used to grow the salt crystals. The investigated parameters were: (1) the advancement rate, (2) the crucible lid configuration, (3) the amount of salt mixture, (4) the initial composition of CsCl, and (5) the temperature difference between the high and low furnace zones. From each grown crystal, samples were taken axially and analyzed using inductively coupled plasma mass spectrometry (ICP-MS). Results show that CsCl concentrations at the top of the crystals were low and increased to a maximum at the bottom of the salt. Salt (LiCl-KCl) recycle percentages for the experiments ranged from 50% to 75% and the CsCl composition in the waste salt was low. To increase the recycle percentage and the concentration of CsCl in the waste form, the possibility of using multiple crystallization stages was explored to further optimize the process. Results show that multiple crystallization stages are practical and the optimal experimental conditions should be operated at 5.0 mm/hr rate with a lid configuration and temperature difference of 200 °C for a total of five crystallization stages. Under these conditions, up to 88% of the salt can be recycled.

  16. Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation of Sodium Salts

    Microsoft Academic Search

    Bruce A. Moyer; Gregg J. Lumetta; Alan P. Marchand

    2002-01-01

    The overall goal of this research conducted under the auspices of the USDOE Environmental Management Science Program (EMSP) is to provide a scientific foundation upon which the feasibility of new liquid-liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated. Disposal of high-level nuclear waste is horrendously expensive, in large part because the

  17. Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation of Sodium Salts

    Microsoft Academic Search

    Bruce A Moyer; Gregg J. Lumetta; Alan P. Marchand

    2003-01-01

    The overall goal of this research conducted under the auspices of the USDOE Environmental Management Science Program (EMSP) is to provide a scientific foundation upon which the feasibility of new liquid- liquid extraction chemistry applicable to the bulk reduction of the volume of tank waste can be evaluated. Disposal of high- level nuclear waste is horrendously expensive, in large part

  18. Molten salt destruction of energetic material wastes as an alternative to open burning. Revision 1

    Microsoft Academic Search

    R. S. Upadhye; W. A. Brummond; C. O. Pruneda; B. E. Watkins

    1994-01-01

    As a result of the end of the Cold War and the shift in emphasis to a smaller stockpile, many munitions, both conventional and nuclear, are scheduled for retirement and rapid dismantlement and demilitarization. Major components of these munitions are the explosives and propellants, or energetic materials. The Molten Salt Destruction (MSD) Process has been demonstrated for the destruction of

  19. Technetium in alkaline, high-salt, radioactive tank waste supernate: Preliminary characterization and removal

    SciTech Connect

    Blanchard, D.L. Jr.; Brown, G.N.; Conradson, S.D. [and others

    1997-01-01

    This report describes the initial work conducted at Pacific Northwest National Laboratory to study technetium (Tc) removal from Hanford tank waste supernates and Tc oxidation state in the supernates. Filtered supernate samples from four tanks were studied: a composite double shell slurry feed (DSSF) consisting of 70% from Tank AW-101, 20% from AP-106, and 10% from AP-102; and three complexant concentrate (CC) wastes (Tanks AN-107, SY-101, ANS SY-103) that are distinguished by having a high concentration of organic complexants. The work included batch contacts of these waste samples with Reillex{trademark}-HPQ (anion exchanger from Reilly Industries) and ABEC 5000 (a sorbent from Eichrom Industries), materials designed to effectively remove Tc as pertechnetate from tank wastes. A short study of Tc analysis methods was completed. A preliminary identification of the oxidation state of non-pertechnetate species in the supernates was made by analyzing the technetium x-ray absorption spectra of four CC waste samples. Molybdenum (Mo) and rhenium (Re) spiked test solutions and simulants were tested with electrospray ionization-mass spectrometry to evaluate the feasibility of the technique for identifying Tc species in waste samples.

  20. The low frequency phonons dynamics in supercooled LiCl, 6H2O

    Microsoft Academic Search

    M. E. Gallina; L. Bove; C. Dreyfus; A. Polian; B. Bonello; R. Cucini; A. Taschin; R. Torre; R. M. Pick

    2009-01-01

    We report the results of a series of ultrasound, Brillouin scattering, and optical heterodyne detected transient grating experiments performed on a LiCl, 6H2O solution from room temperature down to the vicinity of its liquid-glass transition, Tg~138 K. Down to T~215 K, the supercooled liquid has a behavior similar to what is expected for supercooled water: its zero frequency sound velocity,

  1. Molten Salt Oxidation: A Thermal Technology for Waste Treatment and Demilitarization

    SciTech Connect

    Hsu, P C; Watkins, B; Pruneda, C; Kwak, S

    2001-08-23

    MSO is a good alternative to incineration for the treatment of a variety of organic wastes including obsolete explosives, low-level mixed waste streams, PCB contaminated oils, spent resins and carbon. The Lawrence Livermore National Laboratory (LLNL) has demonstrated the MSO process for the effective destruction of explosives, explosives-contaminated materials, and other wastes on a 1.5 kg/hr bench-scale unit and in an integrated MSO facility capable of treating 8 kg/hr of low-level radioactive mixed wastes. LLNL, under the direction and support of the Joint Demilitarization Technology (JDT) program, is currently building an integrated MSO plant for destroying explosives, explosives-contaminated sludge and explosives-contaminated activated charcoal. In a parallel effort, LLNL also provides technical support to DOE for the implementation of the MSO technology at industrial scale at Richland, Washington. Over 30 waste streams have been demonstrated with LLNL-built MSO systems. In this paper we will present our latest experimental data, our operational experience with MSO and also discuss its process capabilities.

  2. Ion Recognition Approach to Volume Reduction of Alkaline Tank Waste by Separation of Sodium Salts

    Microsoft Academic Search

    Bruce A. Moyer; Alan P. Marchand; Gregg J. Lumetta

    2004-01-01

    In this project, now completing its third year of its second renewal period, a collaborative project involving Oak Ridge National Laboratory, Pacific Northwest National Laboratory, and the University of North Texas has been addressing outstanding questions regarding the separation of the bulk sodium constituents of alkaline tank waste. The principal potential benefit of this research is a major reduction in

  3. Technetium in alkaline, high-salt, radioactive tank waste supernate: Preliminary characterization and removal

    Microsoft Academic Search

    D. L. Jr. Blanchard; G. N. Brown; S. D. Conradson

    1997-01-01

    This report describes the initial work conducted at Pacific Northwest National Laboratory to study technetium (Tc) removal from Hanford tank waste supernates and Tc oxidation state in the supernates. Filtered supernate samples from four tanks were studied: a composite double shell slurry feed (DSSF) consisting of 70% from Tank AW-101, 20% from AP-106, and 10% from AP-102; and three complexant

  4. Properties of salt-saturated concrete and grout after six years in situ at the Waste Isolation Pilot Plant

    SciTech Connect

    Wakeley, L.D.; Harrington, P.T.; Weiss, C.A. Jr. [Army Engineer Waterways Experiment Station, Vicksburg, MS (United States). Structures Lab.

    1993-06-01

    Samples of concrete and grout were recovered from short boreholes in the repository floor at the Waste Isolation Pilot Plant more than six years after the concrete and grout were placed. Plugs from the Plug Test Matrix of the Plugging and Sealing Program of Sandia National Laboratories were overcored to include a shell of host rock. The cores were analyzed at the Waterways Experiment Station to assess their condition after six years of service, having potentially been exposed to those aspects of their service environment (salt, brine, fracturing, anhydrite, etc.) that could cause deterioration. Measured values of compressive strength and pulse velocity of both the grout and the concrete equaled or exceeded values from tests performed on laboratory-tested samples of the same mixtures at ages of one month to one year after casting. The phase assemblages had changed very little. Materials performed as intended and showed virtually no chemical or physical evidence of deterioration. The lowest values for strength and pulse velocity were measured for samples taken from the Disturbed Rock Zone, indicating the influence of cracking in this zone on the properties of enclosed seal materials. There was evidence of movement of brine in the system. Crystalline phases containing magnesium, potassium, sulfate, and other ions had been deposited on free surfaces in fractures and pilot holes. There was a reaction rim in the anhydrite immediately surrounding each recovered borehole plug, suggesting interaction between grout or concrete and host rock. However, the chemical changes apparent in this reaction rim were not reflected in the chemical composition of the adjacent concrete or grout. The grout and concrete studied here showed no signs of the deterioration found to have occurred in some parts of the concrete liner of the Waste Isolation Pilot Plant waste handling shaft.

  5. Pseudohypoaldosteronism without nephropathy masking salt-wasting congenital adrenal hyperplasia genetically confirmed

    PubMed Central

    Balcells, Carla; Gili, Teresa; Pérez, Jacobo; Corripio, Raquel

    2013-01-01

    Salt-losing crisis with hypoglycaemia and shock are the main manifestations of congenital adrenal hyperplasia (CAH) during the first weeks of life, while hyponatremia and hyperpotassemia alone are seen on mineralocorticoid deficiency or resistance. During the neonatal period, high blood levels of adrenal steroids may lead to confusing laboratory tests not being able to identify the real level of each hormone. A 33-day-old male baby was admitted at the emergency department with severe salt-losing crisis (Na+ 99?mEq/l and K+ 9.4?mEq/l) and mild acidosis. No hypoglycaemia or hypotension was seen. Urinary tract infection was excluded. Despite treatment with hydrocortisone and fludrocortisone, hyperpotassemia was hard to control. Laboratory tests could not differentiate between pseudohypoaldosteronism and CAH as both the aldosterone (2454?pg/ml) and 17-OH-progesterone (656.6?ng/ml) levels were high. Diagnosis was made, thanks to the genetic study that proved classical mutations in both alleles of the 21-hydroxylase gene. PMID:23370958

  6. Recycling of aluminum salt cake

    Microsoft Academic Search

    B. J. Jody; E. J. Daniels; P. V. Bonsignore; D. E. Karvelas

    1991-01-01

    The secondary aluminum industry generates more than 110 à 10³ tons of salt-cake waste every year. This waste stream contains about 3--5% aluminum, 15--30% aluminum oxide, 30--40% sodium chloride, and 20--30% potassium chloride. As much as 50% of the content of this waste is combined salt (sodium and potassium chlorides). Salt-cake waste is currently disposed of in conventional landfills. In

  7. Effects of resource activities upon repository siting and waste containment with reference to bedded salt

    SciTech Connect

    Ashby, J.; Rowe, J.

    1980-02-01

    The primary consideration for the suitability of a nuclear waste repository site is the overall ability of the repository to safely contain radioactive waste. This report is a discussion of the past, present, and future effects of resource activities on waste containment. Past and present resource activities which provide release pathways (i.e., leaky boreholes, adjacent mines) will receive initial evaluation during the early stages of any repository site study. However, other resource activities which may have subtle effects on containment (e.g., long-term pumping causing increased groundwater gradients, invasion of saline water causing lower retardation) and all potential future resource activities must also be considered during the site evaluation process. Resource activities will affect both the siting and the designing of repositories. Ideally, sites should be located in areas of low resource activity and low potential for future activity, and repository design should seek to eliminate or minimize the adverse effects of any resource activity. Buffer zones should be created to provide areas in which resource activities that might adversely affect containment can be restricted or curtailed. This could mean removing large areas of land from resource development. The impact of these frozen assets should be assessed in terms of their economic value and of their effect upon resource reserves. This step could require a major effort in data acquisition and analysis followed by extensive numerical modeling of regional fluid flow and mass transport. Numerical models should be used to assess the effects of resource activity upon containment and should include the cumulative effects of different resource activities. Analysis by other methods is probably not possible except for relatively simple cases.

  8. Repository environmental parameters and models/methodologies relevant to assessing the performance of high-level waste packages in basalt, tuff, and salt

    SciTech Connect

    Claiborne, H.C.; Croff, A.G.; Griess, J.C.; Smith, F.J.

    1987-09-01

    This document provides specifications for models/methodologies that could be employed in determining postclosure repository environmental parameters relevant to the performance of high-level waste packages for the Basalt Waste Isolation Project (BWIP) at Richland, Washington, the tuff at Yucca Mountain by the Nevada Test Site, and the bedded salt in Deaf Smith County, Texas. Guidance is provided on the identify of the relevant repository environmental parameters; the models/methodologies employed to determine the parameters, and the input data base for the models/methodologies. Supporting studies included are an analysis of potential waste package failure modes leading to identification of the relevant repository environmental parameters, an evaluation of the credible range of the repository environmental parameters, and a summary of the review of existing models/methodologies currently employed in determining repository environmental parameters relevant to waste package performance. 327 refs., 26 figs., 19 tabs.

  9. Conversion Reactions of Metal Chlorides into Oxides with Boric Acid Applicability to the Vitrification of Molten Salt Wastes Generated in Pyro-reprocessing Process

    Microsoft Academic Search

    Yasuhisa IKEDA; Yoichi TAKASHIMA; Hiroaki KOBAYASHI; Hiroshi IGARASHI

    1995-01-01

    Conversion reactions of metal chlorides into oxides with boric acid (H3BO3) were studied to develop the method for vitrification of radioactive molten salt wastes generated in the pyro- reprocessing process. Mixtures of metal chlorides and H3BO3 with appropriate compositions in Pt crucible were heated at 1,000°C for 1h in an electric furnace, followed by rapid cooling to room temperature. The

  10. Stepwise Splitting of Ribosomal Proteins from Yeast Ribosomes by LiCl

    PubMed Central

    Piir, Kerli; Tamm, Tiina; Kisly, Ivan; Tammsalu, Triin; Remme, Jaanus

    2014-01-01

    Structural studies have revealed that the core of the ribosome structure is conserved among ribosomes of all kingdoms. Kingdom-specific ribosomal proteins (r-proteins) are located in peripheral parts of the ribosome. In this work, the interactions between rRNA and r-proteins of eukaryote Saccharomyces cerevisiae ribosome were investigated applying LiCl induced splitting and quantitative mass spectrometry. R-proteins were divided into four groups according to their binding properties to the rRNA. Most yeast r-proteins are removed from rRNA by 0.5–1 M LiCl. Eukaryote-specific r-proteins are among the first to dissociate. The majority of the strong binders are known to be required for the early ribosome assembly events. As compared to the bacterial ribosome, yeast r-proteins are dissociated from rRNA at lower ionic strength. Our results demonstrate that the nature of protein-RNA interactions in the ribosome is not conserved between different kingdoms. PMID:24991888

  11. Worth its salt?

    NASA Astrophysics Data System (ADS)

    The idea that all underground salt deposits can serve as storage sites for toxic and nuclear waste does not always hold water—literally. According to Daniel Ronen and Brian Berkowitz of Israel's Weizmann Institute of Science and Yoseph Yechieli of the Geological Survey of Israel, some buried salt layers are in fact highly conductive of liquids, suggesting that wastes buried in their confines could easily leech into groundwater and nearby soil.When drilling three wells into a 10,000-year-old salt layer near the Dead Sea, the researchers found that groundwater had seeped into the layer and had absorbed some of its salt.

  12. Cation co-tolerance phenomenon in cell cultures of Oryza sativa adapted to LiCl and NaCl

    Microsoft Academic Search

    Safdar Hussain Shah; Satoshi Tobita; Mariko Shono

    2002-01-01

    Cell lines of Oryza sativa L. (cv. Taipei-309) were adapted to 30 mM LiCl and 150 mM NaCl. Both adapted lines were considerably more tolerant than non adapted line when grown on 200, 250 and 300 mM NaCl and 30 mM LiCl stresses. The tolerance of LiCl-adapted line to NaCl (150 to 300 mM) and the tolerance of NaCl-adapted cells

  13. Recommended new criteria for the selection of nuclear waste repository sites in Columbia River basalt and US Gulf Coast domed salt

    SciTech Connect

    Steinborn, T.L.; Wagoner, J.L.; Qualheim, B.; Fitts, C.R.; Stetkar, R.E.; Turnbull, R.W.

    1980-06-16

    Screening criteria and specifications are recommended to aid in the evaluation of sites proposed for nuclear waste disposal in basalt and domed salt. The recommended new criteria proposed in this report are intended to supplement existing repository-related criteria for nuclear waste disposal. The existing criteria are contained in 10 CFR 60 sections which define siting criteria of the Nuclear Regulatory Commission (NRC), and ONWI 33(2) which defines siting criteria of the Office of Nuclear Waste Isolation (ONWI) for the Department of Energy. The specifications are conditions or parameter values that the authors recommend be applied in site acceptance evaluations. The siting concerns covered in this report include repository depth, host rock extent, seismic setting, structural and tectonic conditions, groundwater and rock geochemistry, volcanism, surface and subsurface hydrology, and socioeconomic issues, such as natural resources, land use, and population distribution.

  14. Ceramicrete stabilization of radioactive-salt-containing liquid waste and sludge water. Final CRADA report.

    SciTech Connect

    Ehst, D.; Nuclear Engineering Division

    2010-08-04

    It was found that the Ceramicrete Specimens incorporated the Streams 1 and 2 sludges with the adjusted loading about 41.6 and 31.6%, respectively, have a high solidity. The visible cracks in the matrix materials and around the anionite AV-17 granules included could not obtain. The granules mentioned above fixed by Ceramicrete matrix very strongly. Consequently, we can conclude that irradiation of Ceramecrete matrix, goes from the high radioactive elements, not result the structural degradation. Based on the chemical analysis of specimens No.462 and No.461 used it was shown that these matrix included the formation elements (P, K, Mg, O), but in the different samples their correlations are different. These ratios of the content of elements included are about {+-} 10%. This information shows a great homogeneity of matrix prepared. In the list of the elements founded, expect the matrix formation elements, we detected also Ca and Si (from the wollastonite - the necessary for Ceramicrete compound); Na, Al, S, O, Cl, Fe, Ni also have been detected in the Specimen No.642 from the waste forms: NaCl, Al(OH){sub 3}, Na{sub 2}SO{sub 4}. Fe(OH){sub 3}, nickel ferrocyanide and Ni(NO{sub 3})2. The unintelligible results also were found from analysis of an AV-17 granules, in which we obtain the great amount of K. The X-ray radiographs of the Ceramicrete specimens with loading 41.4 % of Stream 1 and 31.6% of Stream 2, respectively showed that the realization of the advance technology, created at GEOHKI, leads to formation of excellent ceramic matrix with high amount of radioactive streams up to 40% and more. Really, during the interaction with start compounds MgO and KH{sub 2}PO{sub 4} with the present of H{sub 3}BO{sub 3} and Wollastonite this process run with high speed under the controlled regimes. That fact that the Ceramicrete matrix with 30-40% of Streams 1 and 2 have a crystalline form, not amorphous matter, allows to permit that these matrix should be very stable, reliable for incorporation of a radionuclides.

  15. Particle-shape control of molten salt synthesized lead titanate

    Microsoft Academic Search

    Y. Ito; B. Jadidian; M. Allahverdi; A. Safari

    2000-01-01

    Lead titanate PbTiO3 (PT) powders with different morphologies were synthesized using a molten salt method. Amorphous PT powder was prepared from an aqueous nitrate solution, mixed with a eutectic of NaCl-KCl, and then heated at 850°C for 1 h. The effect of additives such as LiF, NaF and LiCl on the particle morphology and size of the derived PT was

  16. Chemistry of brines in salt from the Waste Isolation Pilot Plant (WIPP), southeastern New Mexico: a preliminary investigation

    SciTech Connect

    Stein, C.L.; Krumhansl, J.L.

    1986-03-01

    We present here analyses of macro- and microscopic (intracrystalline) brines observed within the WIPP facility and in the surrounding halite, with interpretations regarding the origin and history of these fluids and their potential effect(s) on long-term waste storage. During excavation, several large fluid inclusions were recovered from an area of highly recrystallized halite in a thick salt bed at the repository horizon (2150 ft below ground level). In addition, 52 samples of brine ''weeps'' were collected from walls of recently excavated drifts at the same stratigraphic horizon from which the fluid inclusion samples are assumed to have been taken. Analyses of these fluids show that they differ substantially in composition from the inclusion fluids and cannot be explained by mixing of the fluid inclusion populations. Finally, holes in the facility floor that filled with brine were sampled but with no stratographic control; therefore it is not possible to interpret the compositions of these brines with any accuracy, except insofar as they resemble the weep compositions but with greater variation in both K/Mg and Na/Cl ratios. However, the Ca and SO/sub 4/ values for the floor holes are relatively close to the gypsum saturation curve, suggesting that brines filling floor holes have been modified by the presence of gypsum or anhydrite, possibly even originating in one or more of the laterally continuous anhydrite units referred to in the WIPP literature as marker beds. In conclusion, the wide compositional variety of fluids found in the WIPP workings suggest that (1) an interconnected hydrologic system which could effectively transport radonuclides away from the repository does not exist; (2) brine migration studies and experiments must consider the mobility of intergranular fluids as well as those in inclusions; and (3) near- and far-field radionuclide migration testing programs need to consider a wide range of brine compositions rather than a few reference brines.

  17. The low frequency phonons dynamics in supercooled LiCl, 6H2O

    NASA Astrophysics Data System (ADS)

    Gallina, M. E.; Bove, L.; Dreyfus, C.; Polian, A.; Bonello, B.; Cucini, R.; Taschin, A.; Torre, R.; Pick, R. M.

    2009-09-01

    We report the results of a series of ultrasound, Brillouin scattering, and optical heterodyne detected transient grating experiments performed on a LiCl, 6H2O solution from room temperature down to the vicinity of its liquid-glass transition, Tg˜138 K. Down to T ˜215 K, the supercooled liquid has a behavior similar to what is expected for supercooled water: its zero frequency sound velocity, C0, continuously decreases while the corresponding infinite frequency velocity, C?, sharply increases, reflecting the increasing importance of H bonding when temperature is lowered. Below 215 K, specific aspects of the solution, presumably related to the role of the Li+ and Cl- ions, modify the thermal behavior of C0, while a ? relaxation process also appears and couples to the sound propagation. The origin of those two effects is briefly discussed.

  18. Effect of salts on growth and pectinase production by halotolerant yeast, Debaryomyces nepalensis NCYC 3413.

    PubMed

    Gummadi, Sathyanarayana N; Kumar, Sawan; Aneesh, C N A

    2007-06-01

    In this study, Debaryomyces nepalensis NCYC 3413 isolated from rotten apple was studied for its halotolerance and its growth was compared with that of Saccharomyces cerevisiae in high salt medium. The specific growth rate of D. nepalensis was not affected by KCl even up to a concentration of 1 M: , whereas NaCl and LiCl affected the growth of D. nepalensis. Among all tested salts, LiCl showed maximum inhibition on growth. At all conditions, halotolerance of D. nepalensis was much higher than that of S. cerevisiae. D. nepalensis showed maximum viability (80-100%) when grown in KCl, which was higher than with NaCl and LiCl. Pectinase production by D. nepalensis was noted at all high salt concentrations, namely, 2 M NaCl, 2 M KCl, and 0.5 M LiCl, and the maximum specific activity was observed when the strain was grown in 2 M NaCl. PMID:17487528

  19. Expected near-field thermal environments in a sequentially loaded spent-fuel or high-level waste repository in salt

    SciTech Connect

    Rickertsen, L.D.; Arbital, J.G.; Claiborne, H.C.

    1982-01-01

    This report describes the effect of realistic waste emplacement schedules on repository thermal environments. Virtually all estimates to date have been based on instantaneous loading of wastes having uniform properties throughout the repository. However, more realistic scenarios involving sequential emplacement of wastes reflect the gradual filling of the repository over its lifetime. These cases provide temperatures that can be less extreme than with the simple approximation. At isolated locations in the repository, the temperatures approach the instantaneous-loading limit. However, for most of the repository, temperature rises in the near-field are 10 to 40 years behind the conservative estimates depending on the waste type and the location in the repository. Results are presented for both spent-fuel and high-level reprocessing waste repositories in salt, for a regional repository concept, and for a single national repository concept. The national repository is filled sooner and therefore more closely approximates the instantaneously loaded repository. However, temperatures in the near-field are still 20/sup 0/C or more below the values in the simple model for 40 years after startup of repository emplacement operations. The results suggest that current repository design concepts based on the instantaneous-loading predictions are very conservative. Therefore, experiments to monitor temperatures in a test and evaluation facility, for example, will need to take into account the reduced temperatures in order to provide data used in predicting repository performance.

  20. Numerical simulation of hydrothermal salt separation process and analysis and cost estimating of shipboard liquid waste disposal

    E-print Network

    Hunt, Andrew Robert

    2007-01-01

    Due to environmental regulations, waste water disposal for US Navy ships has become a requirement which impacts both operations and the US Navy's budget. In 2006, the cost for waste water disposal Navy-wide was 54 million ...

  1. Hyponatremia in traumatic brain injury patients: Syndrome of Inappropriate Antidiuretic Hormone (SIADH) versus Cerebral Salt Wasting Syndrome(CSWS)

    PubMed Central

    Sepehri, Parandoush; Abbasi, Zahra; Mohammadi, Najaf Seid; Bagheri, Seyedreza; Fattahian, Reza

    2012-01-01

    Abstract: Background: Two common dysfunctions among traumatic brain injury (TBI) are hyponatremia secondary to the syndrome of inappropriate antidiuretic hormone secretion (SIADH) and cerebral salt wasting syndrome (CSWS).The present study was aimed to define real incidence and most common cause of this problem. Differentiation between these two syndromes is difficult because of overlapping signs, symptoms and specially laboratory data. Distinction between the two syndromes is based on patient's volume state. The present study aims to develop an alternative diagnosis strategy for defining the type of post-TBI hyponatremia. Methods: This was a single-center retrospective study conducted on TBI diagnosed patients referred to intensive care unit (ICU) of Taleghani Hospital (Kermanshah, Iran). Hyponatremia condition is diagnosed when sodium level reaches the values of less than 135 meq/lit. Basic criterion for diagnosing the hyponatremia type was only urine volume. Urine volume was compared with previous days and fluid intake. If the volume showed a reduction, then the patient was classified in SIADH group, and the prescribed treatment was only fluid intake restriction. In cases of CSWS that have polyuric state and hyponatremia, treatment is sodium and fluid replacement. CBC, Na, K, FBS, BUN, Cr and urine 24-hour volume were measured daily, while during the treatment, it was performed twice or more. Results: A total of 881 patients were referred to ICU during January 2011 to March 2012, of them, 678 patients had head trauma with and/or without other body injury. Out of all patients, 216 (%32) showed hyponatremia. Based on our diagnosis and treatment strategies, all of patient had lower urine output than previous day and were classified in the SIADH group and treated with only fluid restriction. None of patients were classified in CSWS group. All patients well recovered from hyponatremia with simple fluid restriction. In a clinical examination after a follow up period, the outcomes of all patients were acceptable with no adverse effects. Conclusions: Although CSWS was reported in many previous studies, the findings of the present study demonstrate that this procedure can be questioned and presence of CSWS following TBI is a rare condition, since it is probably an unpredictable response of kidney to stressor hormones. Keywords: Hyponatremia, SIADH, CSWS, TBI

  2. Estimated inventory of chemicals added to underground waste tanks, 1944--1975. [Analysis of sludges and salt cakes

    Microsoft Academic Search

    1976-01-01

    The five major chemical processes, the Bismuth Phosphate process, the Uranium Recovery process, the Redox process, the Purex process, and the Waste Fractionization process have each contributed to give the total Hanford waste chemicals. Each of these processes is studied to determine the total estimated chemicals stored in underground waste tanks. The chemical contents are derived mainly from flowsheet compositions

  3. Electrodialysis technology for salt recovery from aluminum salt cake

    SciTech Connect

    Hryn, J. N.; Krumdick, G.; Graziano, D.; Sreenivasarao, K.

    2000-02-02

    Electrodialysis technology for recovering salt from aluminum salt cake is being developed at Argonne National Laboratory. Salt cake, a slag-like aluminum-industry waste stream, contains aluminum metal, salt (NaCl and KCl), and nonmetallics (primarily aluminum oxide). Salt cake can be recycled by digesting with water and filtering to recover the metal and oxide values. A major obstacle to widespread salt cake recycling is the cost of recovering salt from the process brine. Electrodialysis technology developed at Argonne appears to be a cost-effective approach to handling the salt brines, compared to evaporation or disposal. In Argonne's technology, the salt brine is concentrated until salt crystals are precipitated in the electrodialysis stack; the crystals are recovered downstream. The technology is being evaluated on the pilot scale using Eurodia's EUR 40-76-5 stack.

  4. Long-term cement corrosion in chloride-rich solutions relevant to radioactive waste disposal in rock salt - Leaching experiments and thermodynamic simulations

    NASA Astrophysics Data System (ADS)

    Bube, C.; Metz, V.; Bohnert, E.; Garbev, K.; Schild, D.; Kienzler, B.

    Low- and intermediate-level radioactive wastes are frequently solidified in a cement matrix. In a potential repository for nuclear wastes, the cementitious matrix is altered upon contact with solution and the resulting secondary phases may provide for significant retention of the radionuclides incorporated in the wastes. In order to assess the secondary phases formed upon corrosion in chloride-rich solutions, which are relevant for nuclear waste disposal in rock salt, leaching experiments were performed. Conventional laboratory batch experiments using powdered hardened cement paste in MgCl2-rich solutions were left to equilibrate for up to three years and full-scale cemented waste products were exposed to NaCl-rich and MgCl2-rich solutions for more than twenty years, respectively. Solid phase analyses revealed that corrosion of hardened cement in MgCl2-rich solutions advanced faster than in NaCl-rich solutions due to the extensive exchange of Mg from solution against Ca from the cementitious solid. Thermodynamic equilibrium simulations compared well to results at the final stages of the respective experiments indicating that close to equilibrium conditions were reached. At high cement product to brine ratios (>0.65 g mL-1), the solution composition in the laboratory-scale experiments was close to that of the full-scale experiments (cement to brine ratio of 2.5 g mL-1) in the MgCl2 systems. The present study demonstrates the applicability of thermodynamic methods used in this approach to adequately describe full-scale long-term experiments with cemented waste simulates.

  5. Radiation damage measurements on rock salt and other minerals for waste disposal applications. Quarterly report, January 1, 1980-March 31, 1980

    SciTech Connect

    Swyler, K J; Loman, J M; Teutonico, L J; Elgort, G E; Levy, P W

    1980-04-10

    Different aspects of radiation damage in both synthetic NaCl crystals and various natural rock salt samples as well as granite, basalt and other minerals which will be important for radioactive waste disposal applications are being investigated. The principal means of measuring radiation damage is the determination of F-center concentrations, and the concentration and size of sodium metal colloid particles. Formation of these and other defects during irradiation and the annealing of defects and characterization of other processes occurring after irradiation are being studied as a function of dose rate, total dose, sample temperature during irradiation, strain applied prior to and during irradiation, etc. Measurements are being made on synthetic NaCl and natural rock salt samples from different geological locations, including some potential repository sites. It will be necessary to determine if radiation damage in the minerals from different localities is similar. If non-negligible differences are observed a detailed study must be made for each locality under consideration. Almost all current studies are being made on rock salt but other minerals particularly granite and basalt are being phased into the program. It is now established that radiation damage formation in both natural and synthetic rock salt is strongly dependent on strain. The strain related effects strongly indicate that the damage formation processes and in particular the colloid nucleation processes are related to the strain induced disolcations. A temporary theoretical effort has been started to determine which dislocation related effects are important for radiation damage processes and, most importantly, what dislocation interactions are most likely to create nucleation sites for colloid particles. If these preliminary studies indicate that additional theoretical studies will be useful an effort will be made to have them extended.

  6. Synthesis and reactions of the first room temperature stable Li/Cl phosphinidenoid complex.

    PubMed

    Nesterov, Vitaly; Schnakenburg, Gregor; Espinosa, Arturo; Streubel, Rainer

    2012-11-19

    P-Trityl substituted Li/Cl phosphinidenoid tungsten(0) complex (OC)5W{Ph3CP(Li/12-crown-4)Cl} (3) was prepared via chlorine/lithium exchange in complex (OC)5W{Ph3CPCl2} (2) using (t)BuLi in the presence of 12-crown-4 in tetrahydrofuran (THF) at low temperature; complex 3 possesses significantly increased thermal stability in contrast to previously reported analogue derivatives. Terminal phosphinidene-like reactivity of 3 was used in reactions with benzaldehyde and isopropyl alcohol as oxaphosphirane complex (OC)5W{Ph3CPC(Ph)O} (5) and phosphinite complex (OC)5W{Ph3CP(H)O(i)Pr} (6) were obtained selectively. Reaction of 3 with phosgene allowed to obtain the first kinetically stabilized chloroformylphosphane complex (OC)5W{Ph3CP(Cl)C(O)Cl} (4). Density functional theory (DFT) calculations revealed remarkable differences in the degree of P-Li bond dissociation 3a-d: using a continuum model 3 displays a covalent character of P-Li bond (COSMO (THF)) (a), which becomes elongated if 12-crown-4 is coordinated to lithium (b) and is cleaved if a dimethylether unit is additionally coordinated to lithium (c). A similar result was obtained for the case of 3(thf)4 in which also a solvent-separated ion pair structure is present (d). All products were unambiguously characterized by various spectroscopic means and, in the case of 2 and 4-6, by single-crystal X-ray diffraction analysis. In all structures very long P-C bonds were determined being in the range from 1.896 to 1.955 Å. PMID:23134468

  7. Enhanced tolerance to NaCl and LiCl stresses by over-expressing Caragana korshinskii sodium/proton exchanger 1 (CkNHX1) and the hydrophilic C terminus is required for the activity of CkNHX1 in Atsos3-1 mutant and yeast

    SciTech Connect

    Yang, Da-Hai, E-mail: gresea_young@hotmail.com [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China) [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China); Department of Plant Physiology, Institute of General Botany and Plant Physiology, Friedrich-Schiller-University, Dornburger Strasse 159, 07743 Jena (Germany); Song, Li-Ying, E-mail: lysong@genetics.ac.cn [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China)] [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China); Hu, Jun, E-mail: jhu@genetics.ac.cn [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China)] [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China); Yin, Wei-Bo, E-mail: wbyin@genetics.ac.cn [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China)] [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China); Li, Zhi-Guo, E-mail: gzhi@genetics.ac.cn [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China)] [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China); Chen, Yu-Hong, E-mail: yhchen@genetics.ac.cn [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China)] [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China); Su, Xiao-Hua, E-mail: suxh@caf.ac.cn [Research Institute of Forestry, Chinese Academy of Forestry, Beijing 100091 (China)] [Research Institute of Forestry, Chinese Academy of Forestry, Beijing 100091 (China); Wang, Richard R.-C., E-mail: Richard.Wang@ARS.USDA.GOV [USDA-ARS, FRRL, Utah State University, Logan, UT 84322-6300 (United States); Hu, Zan-Min, E-mail: zmhu@genetics.ac.cn [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China)] [Institute of Genetics and Developmental Biology, Chinese Academy of Sciences, Beijing 100101 (China)

    2012-01-13

    Highlights: Black-Right-Pointing-Pointer CkNHX1 was isolated from Caragana korshinskii. Black-Right-Pointing-Pointer CkNHX1 was expressed mainly in roots, and significantly induced by NaCl in stems. Black-Right-Pointing-Pointer Expression of CkNHX1 enhanced the resistance to NaCl and LiCl in yeast and Atsos3-1. Black-Right-Pointing-Pointer Expression of CkNHX1-{Delta}C had little effect on NaCl/LiCl tolerance in Atsos3-1. Black-Right-Pointing-Pointer C-terminal region of CkNHX1 is required for its Na{sup +} and Li{sup +} transporting activity. -- Abstract: Sodium/proton exchangers (NHX antiporters) play important roles in plant responses to salt stress. Previous research showed that hydrophilic C-terminal region of Arabidopsis AtNHX1 negatively regulates the Na{sup +}/H{sup +} transporting activity. In this study, CkNHX1 were isolated from Caragana korshinskii, a pea shrub with high tolerance to salt, drought, and cold stresses. Transcripts of CkNHX1 were detected predominantly in roots, and were significantly induced by NaCl stress in stems. Transgenic yeast and Arabidopsisthalianasos3-1 (Atsos3-1) mutant over-expressing CkNHX1 and its hydrophilic C terminus-truncated derivative, CkNHX1-{Delta}C, were generated and subjected to NaCl and LiCl stresses. Expression of CkNHX1 significantly enhanced the resistance to NaCl and LiCl stresses in yeast and Atsos3-1 mutant. Whereas, compared with expression of CkNHX1, the expression of CkNHX1-{Delta}C had much less effect on NaCl tolerance in Atsos3-1 and LiCl tolerance in yeast and Atsos3-1. All together, these results suggest that the predominant expression of CkNHX1 in roots might contribute to keep C. korshinskii adapting to the high salt condition in this plant's living environment; CkNHX1 could recover the phenotype of Atsos3-1 mutant; and the hydrophilic C-terminal region of CkNHX1 should be required for Na{sup +}/H{sup +} and Li{sup +}/H{sup +} exchanging activity of CkNHX1.

  8. Water uptake by salts during the electrolyte processing for thermal batteries

    NASA Astrophysics Data System (ADS)

    Masset, Patrick; Poinso, Jean-Yves; Poignet, Jean-Claude

    Water uptake of single salts and electrolytes were measured in industrial conditions (dry-room). The water uptake rate ? (g h -1 cm -2) was expressed with respect to the apparent area of contact of the salt with atmosphere of the dry room. The water uptake by potassium-based salts was very low. LiF and LiCl salts were found to behave similarly. For LiBr- and LiI-based salts and mixtures, we pointed out a linear relationship between the water uptake and the elapsed time. Water uptake by magnesium oxide reached a limit after 200 h. This work provides a set of data concerning the rate of water uptake by single salts, salt mixtures and magnesia used in thermal battery electrolytes.

  9. Actinide removal from spent salts

    DOEpatents

    Hsu, Peter C. (Pleasanton, CA); von Holtz, Erica H. (Livermore, CA); Hipple, David L. (Livermore, CA); Summers, Leslie J. (Livermore, CA); Adamson, Martyn G. (Danville, CA)

    2002-01-01

    A method for removing actinide contaminants (uranium and thorium) from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents are added to precipitate the thorium as thorium oxide and/or the uranium as either uranium oxide or as a diuranate salt. The precipitated materials are filtered, dried and packaged for disposal as radioactive waste. About 90% of the thorium and/or uranium present is removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 0.1 ppm of thorium or uranium.

  10. Metals removal from spent salts

    DOEpatents

    Hsu, Peter C. (Pleasanton, CA); Von Holtz, Erica H. (Livermore, CA); Hipple, David L. (Livermore, CA); Summers, Leslie J. (Livermore, CA); Brummond, William A. (Livermore, CA); Adamson, Martyn G. (Danville, CA)

    2002-01-01

    A method and apparatus for removing metal contaminants from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents may be added to precipitate the metal oxide and/or the metal as either metal oxide, metal hydroxide, or as a salt. The precipitated materials are filtered, dried and packaged for disposal as waste or can be immobilized as ceramic pellets. More than about 90% of the metals and mineral residues (ashes) present are removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be spray-dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 1.0 ppm of contaminants.

  11. Recycling of aluminum salt cake

    SciTech Connect

    Jody, B.J.; Daniels, E.J.; Bonsignore, P.V.; Karvelas, D.E.

    1991-12-01

    The secondary aluminum industry generates more than 110 {times} 10{sup 3} tons of salt-cake waste every year. This waste stream contains about 3--5% aluminum, 15--30% aluminum oxide, 30--40% sodium chloride, and 20--30% potassium chloride. As much as 50% of the content of this waste is combined salt (sodium and potassium chlorides). Salt-cake waste is currently disposed of in conventional landfills. In addition, over 50 {times} 10{sup 3} tons of black dross that is not economical to reprocess a rotary furnace for aluminum recovery ends up in landfills. The composition of the dross is similar to that of salt cake, except that it contains higher concentrations of aluminum (up to 20%) and correspondingly lower amounts of salts. Because of the high solubility of the salts in water, these residues, when put in landfills, represent a potential source of pollution to surface-water and groundwater supplies. The increasing number of environmental regulations on the generation and disposal of industrial wastes are likely to restrict the disposal of these salt-containing wastes in conventional landfills. Processes exist that employ the dissolution and recovery of the salts from the waste stream. These wet-processing methods are economical only when the aluminum concentration in that waste exceeds about 10%. Argonne National Laboratory (ANL) conducted a study in which existing technologies were reviewed and new concepts that are potentially more cost-effective than existing processes were developed and evaluated. These include freeze crystallization, solvent/antisolvent extraction, common-ion effect, high-pressure/high-temperature process, and capillary-effect systems. This paper presents some of the technical and economic results of the aforementioned ANL study.

  12. Rock-salt mine saw

    SciTech Connect

    Staller, G.E.; Wilson, W.C.; Smith, A.R.

    1985-06-01

    A saw has been developed for cutting rock salt at the Waste Isolation Pilot Plant near Carlsbad, NM. This saw uses commercially available hardware in conjuction with Sandia-designed equipment. It has been used to cut rock salt in situ as well as samples removed from the mine.

  13. A theoretical investigation of gadolinium (III) solvation in molten salts

    NASA Astrophysics Data System (ADS)

    Hazebroucq, Sandrine; Picard, Gérard S.; Adamo, Carlo

    2005-06-01

    The solvation of lanthanides [here Gd(III)] in molten LiCl and KCl has been studied using a classical solvation approach, based on clusters of increasing size. In particular, density-functional calculations have been carried out on charged and neutral clusters, containing up to 35 chlorine halide molecules. A number of properties have been then evaluated and analyzed, including structural, vibrational, and thermochemical data. Special attention has also been devoted to the analysis of the local structure of the solvent surrounding the Gd3+ cation, a problem deeply investigated by experimentalists. Our results show that the charged clusters are not suitable to model the first solvation shell in such species, since their structures are strongly affected by the large electrostatic contribution. In contrast, more reliable simulations are obtained using the neutral clusters. In the latter, the coordination of Gd(III) in molten salts is computed to be 8 or 6, according to the salt LiCl or KCl. Furthermore, a good agreement is found with the experimental structural data and Raman spectra. Finally, preliminary results of potential interest for the estimation of solvation thermodynamics, a key parameter for exploiting molten salt chemistry, are reported for neutral clusters.

  14. Ab initio Hartree-Fock Born effective charges of LiH, LiF, LiCl, NaF, and NaCl

    NASA Astrophysics Data System (ADS)

    Shukla, Alok

    2000-05-01

    We use the Berry-phase-based theory of macroscopic polarization of dielectric crystals formulated in terms of Wannier functions, and state-of-the-art Gaussian basis functions, to obtain benchmark ab initio Hartree-Fock values of the Born effective charges of ionic compounds LiH, LiF, LiCl, NaF, and NaCl. We find excellent agreement with the experimental values for all the compounds except LiCl and NaCl, for which the disagreement with the experiments is close to 10% and 16%, respectively. This may imply the importance of many-body effects in those systems.

  15. Modeling and Field Test Planning Activities in Support of Disposal of Heat-Generating Waste in Salt

    SciTech Connect

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

    2014-09-26

    The modeling efforts in support of the field test planning conducted at LBNL leverage on recent developments of tools for modeling coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. 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. These are modeling capabilities that will be suitable for assisting in the design of field experiment, especially related to multiphase flow processes coupled with mechanical deformations, at high temperature. In this report, we first examine previous generic repository modeling results, focusing on the first 20 years to investigate the expected evolution of the different processes that could be monitored in a full-scale heater experiment, and then present new results from ongoing modeling of the Thermal Simulation for Drift Emplacement (TSDE) experiment, a heater experiment on the in-drift emplacement concept at the Asse Mine, Germany, and provide an update on the ongoing model developments for modeling brine migration. LBNL also supported field test planning activities via contributions to and technical review of framework documents and test plans, as well as participation in workshops associated with field test planning.

  16. The role of salt melts on the corrosion of steels and nickel-based alloys in waste incineration plants

    SciTech Connect

    Spiegel, M. [Max-Planck-Inst. fuer Eisenforschung GmbH, Duesseldorf (Germany)

    1999-11-01

    Laboratory experiments were carried out to study the corrosion behavior of steels and nickel-based alloys beneath heavy-metal-rich chloride and sulfate melts. Exposure tests on low- and high alloy steels in (Ca, K, Na, Pb, Zn)-sulfate mixtures in N{sub 2} - 5 vol.% O{sub 2} at 600 C have shown accelerated corrosion after addition of PbSO{sub 4} and ZnSO{sub 4}. The corrosion products were identified as (Fe, Ni)-oxide precipitates in contact with the gas phase and chromium-rich corrosion products close to the metal. Thermogravimetric investigations in He-5 vol.% O{sub 2} with the 2.25Cr-1Mo steel and also Alloy 625 have shown that severe corrosion occurred in the presence of a 50 wt.% ZnCl{sub 2}-50wt.% KCl salt mixture in the temperature range from 300 to 500 C. The corrosion products on 2.25Cr-1Mo were found to be Zn-rich iron-oxide precipitates in contact with the gas phase and a Fe{sub 2}O{sub 3} layer underneath. In contact with the metal, a mixture of iron-chlorides and Fe{sub 2}O{sub 3} was detected, together with variable amounts of K and Zn. A thick scale has formed on Alloy 625, consisting of nickel- and chromium-oxides with some dissolved Mo.

  17. [Bio-oil production from biomass pyrolysis in molten salt].

    PubMed

    Ji, Dengxiang; Cai, Tengyue; Ai, Ning; Yu, Fengwen; Jiang, Hongtao; Ji, Jianbing

    2011-03-01

    In order to investigate the effects of pyrolysis conditions on bio-oil production from biomass in molten salt, experiments of biomass pyrolysis were carried out in a self-designed reactor in which the molten salt ZnCl2-KCl (with mole ratio 7/6) was selected as heat carrier, catalyst and dispersion agent. The effects of metal salt added into ZnCl2-KCl and biomass material on biomass pyrolysis were discussed, and the main compositions of bio-oil were determined by GC-MS. Metal salt added into molten salt could affect pyrolysis production yields remarkably. Lanthanon salt could enhance bio-oil yield and decrease water content in bio-oil, when mole fraction of 5.0% LaCl3 was added, bio-oil yield could reach up to 32.0%, and water content of bio-oil could reduce to 61.5%. The bio-oil and char yields were higher when rice straw was pyrolysed, while gas yield was higher when rice husk was used. Metal salts showed great selectivity on compositions of bio-oil. LiCl and FeCl2 promoted biomass to pyrolyse into smaller molecular weight compounds. CrCl3, CaCl2 and LaCl3 could restrain second pyrolysis of bio-oil. The research provided a scientific reference for production of bio-oil from biomass pyrolysis in molten salt. PMID:21650030

  18. Crushed Salt Constitutive Model

    SciTech Connect

    Callahan, G.D.

    1999-02-01

    The constitutive model used to describe the deformation of crushed salt is presented in this report. Two mechanisms -- dislocation creep and grain boundary diffusional pressure solution -- are combined to form the basis for the constitutive model governing the deformation of crushed salt. The constitutive model is generalized to represent three-dimensional states of stress. Upon complete consolidation, the crushed-salt model reproduces the Multimechanism Deformation (M-D) model typically used for the Waste Isolation Pilot Plant (WIPP) host geological formation salt. New shear consolidation tests are combined with an existing database that includes hydrostatic consolidation and shear consolidation tests conducted on WIPP and southeastern New Mexico salt. Nonlinear least-squares model fitting to the database produced two sets of material parameter values for the model -- one for the shear consolidation tests and one for a combination of the shear and hydrostatic consolidation tests. Using the parameter values determined from the fitted database, the constitutive model is validated against constant strain-rate tests. Shaft seal problems are analyzed to demonstrate model-predicted consolidation of the shaft seal crushed-salt component. Based on the fitting statistics, the ability of the model to predict the test data, and the ability of the model to predict load paths and test data outside of the fitted database, the model appears to capture the creep consolidation behavior of crushed salt reasonably well.

  19. Substitution effects on the formation of T-shaped palladium carbene and thioketone complexes from Li/Cl carbenoids.

    PubMed

    Molitor, Sebastian; Feichtner, Kai-Stephan; Kupper, Claudia; Gessner, Viktoria H

    2014-08-18

    The preparation of palladium thioketone and T-shaped carbene complexes by treatment of thiophosphoryl substituted Li/Cl carbenoids with a Pd(0) precursor is reported. Depending on the steric demand, the anion-stabilizing ability of the silyl moiety (by negative hyperconjugation effects) and the remaining negative charge at the carbenic carbon atom, isolation of a three-coordinate, T-shaped palladium carbene complex is possible. In contrast, insufficient charge stabilization results in the transfer of the sulfur of the thiophosphoryl moiety and thus in the formation of a thioketone complex. While the thioketones are stable compounds the carbene complexes are revealed to be highly reactive and decompose under elimination of Pd metal. Computational studies revealed that both complexes are formed by a substitution mechanism. While the ketone turned out to be the thermodynamically favored product, the carbene is kinetically favored and thus preferentially formed at low reaction temperatures. PMID:24664573

  20. Analysis of Cracking in Rock Salt

    Microsoft Academic Search

    V. G. Silberschmidt; V. V. Silberschmidt

    2000-01-01

    Summary  ¶The use of underground mines in salt-rock formations for waste repositories makes the precise analysis of isolation properties\\u000a of rock salt very important. One of the main mechanisms responsible for a degradation of isolation ability of the rock salt\\u000a is the generation and development of cracks under influence of mining processes. Various aspects of cracking in salt rocks\\u000a are studied

  1. Application of lithium in molten-salt reduction processes.

    SciTech Connect

    Gourishankar, K. V.

    1998-11-11

    Metallothermic reductions have been extensively studied in the field of extractive metallurgy. At Argonne National Laboratory (ANL), we have developed a molten-salt based reduction process using lithium. This process was originally developed to reduce actinide oxides present in spent nuclear fuel. Preliminary thermodynamic considerations indicate that this process has the potential to be adapted for the extraction of other metals. The reduction is carried out at 650 C in a molten-salt (LiCl) medium. Lithium oxide (Li{sub 2}O), produced during the reduction of the actinide oxides, dissolves in the molten salt. At the end of the reduction step, the lithium is regenerated from the salt by an electrowinning process. The lithium and the salt from the electrowinning are then reused for reduction of the next batch of oxide fuel. The process cycle has been successfully demonstrated on an engineering scale in a specially designed pyroprocessing facility. This paper discusses the applicability of lithium in molten-salt reduction processes with specific reference to our process. Results are presented from our work on actinide oxides to highlight the role of lithium and its effect on process variables in these molten-salt based reduction processes.

  2. Bath Salts

    MedlinePLUS

    Synthetic cathinones, often called “bath salts,” are powerful, illegal, and can cause hallucinations and violent behavior, among other dangerous effects. Twitter Facebook RSS 582 Exposures Jan. 1, ...

  3. Salts & Solubility

    NSDL National Science Digital Library

    2012-12-27

    In this online interactive simulation, learners will add different salts to water and then watch the salts dissolve and achieve a dynamic equilibrium with solid precipitate. Learners will also compare the number of ions in NaCl to other slightly soluble salts, and they will relate the charges on ions to the number of ions in the formula of a salt. Learners will also learn how to calculate Ksp values. This activity includes an online simulation, sample learning goals, a teacher's guide, and translations in over 20 languages.

  4. The Combination Effects of LiCl and the Active Leflunomide Metabolite, A771726, on Viral-Induced Interleukin 6 Production and EV-A71 Replication

    PubMed Central

    Hung, Hui-Chen; Shih, Shin-Ru; Chang, Teng-Yuan; Fang, Ming-Yu; Hsu, John T.-A.

    2014-01-01

    Enterovirus 71 (EV-A71) is a neurotropic virus that can cause severe complications involving the central nervous system. No effective antiviral therapeutics are available for treating EV-A71 infection and drug discovery efforts are rarely focused to target this disease. Thus, the main goal of this study was to discover existing drugs with novel indications that may effectively inhibit EV-A71 replication and the inflammatory cytokines elevation. In this study, we showed that LiCl, a GSK3? inhibitor, effectively suppressed EV-A71 replication, apoptosis and inflammatory cytokines production (Interleukin 6, Interleukin-1?) in infected cells. Furthermore, LiCl and an immunomodular agent were shown to strongly synergize with each other in suppressing EV-A71 replication. The results highlighted potential new treatment regimens in suppressing sequelae caused by EV-A71 replication. PMID:25412347

  5. Pseudo-binary electrolyte, LiBH4-LiCl, for bulk-type all-solid-state lithium-sulfur battery.

    PubMed

    Unemoto, Atsushi; Chen, ChunLin; Wang, Zhongchang; Matsuo, Motoaki; Ikeshoji, Tamio; Orimo, Shin-Ichi

    2015-06-26

    The ionic conduction and electrochemical and thermal stabilities of the LiBH4-LiCl solid-state electrolyte were investigated for use in bulk-type all-solid-state lithium-sulfur batteries. The LiBH4-LiCl solid-state electrolyte exhibiting a lithium ionic conductivity of [Formula: see text] at 373 K, forms a reversible interface with a lithium metal electrode and has a wide electrochemical potential window up to 5 V. By means of the high-energy mechanical ball-milling technique, we prepared a composite powder consisting of elemental sulfur and mixed conductive additive, i.e., Ketjen black and Maxsorb. In that composite powder, homogeneous dispersion of the materials is achieved on a nanometer scale, and thereby a high concentration of the interface among them is induced. Such nanometer-scale dispersals of both elemental sulfur and carbon materials play an important role in enhancing the electrochemical reaction of elemental sulfur. The highly deformable LiBH4-LiCl electrolyte assists in the formation of a high concentration of tight interfaces with the sulfur-carbon composite powder. The LiBH4-LiCl electrolyte also allows the formation of the interface between the positive electrode and the electrolyte layers, and thus the Li-ion transport paths are established at that interface. As a result, our battery exhibits high discharge capacities of 1377, 856, and 636 mAh g(-1) for the 1st, 2nd, and 5th discharges, respectively, at 373 K. These results imply that complex hydride-based solid-state electrolytes that contain Cl-ions in the crystal would be integrated into rechargeable batteries. PMID:26041380

  6. The nuclear quadrupole moment of Li: Refined calculations of electric field gradients in LiH, LiF, and LiCl

    NASA Astrophysics Data System (ADS)

    Urban, Miroslav; Sadlej, Andrzej J.

    1990-10-01

    A series of high-level correlated calculations of the electric field gradient at the Li nucleus have been performed for LiH, LiF, and LiCl. The present results lead to a refined "molecular" value of the nuclear quadrupole moment of 7Li, Q( 7Li)=-4.01 e fm 2 which is an excellent agreement with the most recent result (-4.03±0.06 e fm 2) derived from the nuclear scattering data.

  7. Pseudo-binary electrolyte, LiBH4–LiCl, for bulk-type all-solid-state lithium-sulfur battery

    NASA Astrophysics Data System (ADS)

    Unemoto, Atsushi; Chen, ChunLin; Wang, Zhongchang; Matsuo, Motoaki; Ikeshoji, Tamio; Orimo, Shin-ichi

    2015-06-01

    The ionic conduction and electrochemical and thermal stabilities of the LiBH4–LiCl solid-state electrolyte were investigated for use in bulk-type all-solid-state lithium-sulfur batteries. The LiBH4–LiCl solid-state electrolyte exhibiting a lithium ionic conductivity of log ?ft( ? /S c{{m}-1} \\right)=-3.3 at 373 K, forms a reversible interface with a lithium metal electrode and has a wide electrochemical potential window up to 5 V. By means of the high-energy mechanical ball-milling technique, we prepared a composite powder consisting of elemental sulfur and mixed conductive additive, i.e., Ketjen black and Maxsorb. In that composite powder, homogeneous dispersion of the materials is achieved on a nanometer scale, and thereby a high concentration of the interface among them is induced. Such nanometer-scale dispersals of both elemental sulfur and carbon materials play an important role in enhancing the electrochemical reaction of elemental sulfur. The highly deformable LiBH4–LiCl electrolyte assists in the formation of a high concentration of tight interfaces with the sulfur-carbon composite powder. The LiBH4–LiCl electrolyte also allows the formation of the interface between the positive electrode and the electrolyte layers, and thus the Li-ion transport paths are established at that interface. As a result, our battery exhibits high discharge capacities of 1377, 856, and 636 mAh g–1 for the 1st, 2nd, and 5th discharges, respectively, at 373 K. These results imply that complex hydride-based solid-state electrolytes that contain Cl-ions in the crystal would be integrated into rechargeable batteries.

  8. Salt Painting

    NSDL National Science Digital Library

    2012-06-26

    In this art meets chemistry activity, early learners discover the almost magical absorbent properties of salt while creating ethereal watercolor paintings. Learners first use watercolor to paint an image. Then, they sprinkle salt on the wet paint and observe. Use the provided discussion questions to encourage reflection.

  9. Conversion of carboxylate salts to carboxylic acids via reactive distillation 

    E-print Network

    Williamson, Shelly Ann

    2000-01-01

    , municipal solid wastes, sewage sludge, and industrial biosludge. Using a proprietary technology owned by Texas A&M University the wastes are first treated with lime to enhance reactivity. Then they are converted to calcium carboxylate salts using a mixed...

  10. Thermophysical properties of reconsolidating crushed salt.

    SciTech Connect

    Bauer, Stephen J.; Urquhart, Alexander

    2014-03-01

    Reconsolidated crushed salt is being considered as a backfilling material placed upon nuclear waste within a salt repository environment. In-depth knowledge of thermal and mechanical properties of the crushed salt as it reconsolidates is critical to thermal/mechanical modeling of the reconsolidation process. An experimental study was completed to quantitatively evaluate the thermal conductivity of reconsolidated crushed salt as a function of porosity and temperature. The crushed salt for this study came from the Waste Isolation Pilot Plant (WIPP). In this work the thermal conductivity of crushed salt with porosity ranging from 1% to 40% was determined from room temperature up to 300oC, using two different experimental methods. Thermal properties (including thermal conductivity, thermal diffusivity and specific heat) of single-crystal salt were determined for the same temperature range. The salt was observed to dewater during heating; weight loss from the dewatering was quantified. The thermal conductivity of reconsolidated crushed salt decreases with increasing porosity; conversely, thermal conductivity increases as the salt consolidates. The thermal conductivity of reconsolidated crushed salt for a given porosity decreases with increasing temperature. A simple mixture theory model is presented to predict and compare to the data developed in this study.

  11. Salt-specific effects observed in calorimetric studies of alkali and tetraalkylammonium salt solutions of poly(thiophen-3-ylacetic acid).

    PubMed

    Hostnik, Gregor; Vlachy, Vojko; Bondarev, Dmitrij; Vohlídal, Jir Combining Breve Í; Cerar, Janez

    2015-01-28

    The enthalpies of dilution ?Hdil of aqueous solutions of a conjugated polyelectrolyte, poly(thiophen-3-ylacetic acid), neutralized by lithium, sodium, cesium, tetramethyl-, tetraethyl-, tetrapropyl-, and tetrabutylammonium hydroxides, were determined in the concentration range from cp = 2 × 10(-3) to 1 × 10(-1) monomol dm(-3) and for T = 278.15, 298.15, and 318.15 K. At low concentrations the dilution of the alkali PTAA salts yields an endothermic effect, which is in part a consequence of the hydrolysis. An exception is PTALi at 278.15 K, where ?Hdil < 0. In the case of tetraalkylammonium salts the enthalpies of dilution increase in the order TBA < TPA < TEA < TMA. Only the TBA salt of PTAA yields an exothermic effect upon dilution in the whole temperature range. In the second part of the study we measured the enthalpies of mixing, ?Hmix, of various salts of poly(thiophen-3-ylacetic acid) with LiCl, NaCl, KCl, and CsCl solutions in water. When lithium salt of PTAA is mixed with LiCl ?Hmix is positive. For mixing experiments with other alkali chlorides the effect is exothermic. In addition, the enthalpies of mixing of PTALi with tetramethyl-, tetraethyl-, tetrapropyl-, and tetrabutylammonium chloride were measured at T = 278.15 K, 298.15 K, and 318.15 K. Popular polyelectrolyte theories, such as Manning's limiting law, predict for the heat to be released upon dilution, and consumed upon mixing; the agreement between this purely electrostatic theory and experiments is at best qualitative. The ?Hmix values are correlated with the enthalpies of hydration of the cations of the low molecular mass salts added to the solution. PMID:25491322

  12. 238Pu recovery and salt disposition from the molten salt oxidation process

    NASA Astrophysics Data System (ADS)

    Remerowski, M. L.; Stimmel, Jay J.; Wong, Amy S.; Ramsey, Kevin B.

    2000-07-01

    We have begun designing and optimizing our recovery and recycling processes by experimenting with samples of "spent salt" produced by MSO treatment of surrogate waste in the reaction vessel at the Naval Surface Warfare Center-Indian Head. One salt was produced by treating surrogate waste containing pyrolysis ash spiked with cerium. The other salt contains residues from MSO treatment of materials similar to those used in 238Pu processing, e.g., Tygon tubing, PVC bagout bags, HDPE bottles. Using these two salt samples, we will present results from our investigations.

  13. Complete neglect of differential overlap study of the binding of salts to N-methyl acetamide.

    PubMed Central

    Abdulnur, S F; Laki, K

    1979-01-01

    The complete neglect of differential overlap method is used to investigate the binding of LiF, LiCl, NaF, and NaCl to N-methyl acetamide (NMA) as a model for these ions binding to a peptide moiety. The cation (formula: see text) anion interaction is shown to result in a net residual charge on NMA, which becomes less positive as the difference in electronegativity between the anion and cation of the salt present increases. A residual charge of smaller magnitude is also found on a water molecule in the analogous system cation (formula: see text) anion, which displays this same dependence. PMID:263633

  14. Process to separate transuranic elements from nuclear waste

    DOEpatents

    Johnson, Terry R. (Wheaton, IL); Ackerman, John P. (Downers Grove, IL); Tomczuk, Zygmunt (Orland Park, IL); Fischer, Donald F. (Glen Ellyn, IL)

    1989-01-01

    A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).

  15. Mercury separation from aqueous wastes

    Microsoft Academic Search

    P. A. Taylor; K. T. Klasson; S. L. Corder

    1995-01-01

    This project is providing an assessment of new sorbents for removing mercury from wastes at US Department of Energy sites. Four aqueous wastes were chosen for lab-scale testing; a high-salt, acidic waste currently stored at Idaho National Engineering Laboratory (INEL); a high-salt, alkaline waste stored at the Savannah River Site (SRS); a dilute lithium hydroxide solution stored at the Oak

  16. SOLUTION MINING IN SALT DOMES OF THE GULF COAST EMBAYMENT

    SciTech Connect

    Griswold, G. B.

    1981-02-01

    Following a description of salt resources in the salt domes of the gulf coast embayment, mining, particularly solution mining, is described. A scenario is constructed which could lead to release of radioactive waste stored in a salt dome via inadvertent solution mining and the consequences of this scenario are analyzed.

  17. ANALYSIS OF THE SALT FEED TANK CORE SAMPLE

    Microsoft Academic Search

    M. Reigel; W. Cheng

    2012-01-01

    The Saltstone Production Facility (SPF) immobilizes and disposes of low-level radioactive and hazardous liquid waste (salt solution) remaining from the processing of radioactive material at the Savannah River Site (SRS). Low-level waste (LLW) streams from processes at SRS are stored in Tank 50 until the LLW can be transferred to the SPF for treatment and disposal. The Salt Feed Tank

  18. Anomalous ion effects on rupture and lifetime of aqueous foam films from monovalent salt solutions up to saturation concentration

    NASA Astrophysics Data System (ADS)

    Karakashev, S. I.; Nguyen, P. T.; Tsekov, R.; Hampton, M. A.; Nguyen, A. V.

    2008-09-01

    We report the effects of ions on rupture and lifetime of aqueous foam films formed from sodium chloride (NaCl), lithium chloride (LiCl), sodium acetate (NaAc), and sodium chlorate (NaClO 3) using microinterferometry. In the case of NaCl and LiCl, the foam films prepared from the salt solutions below 0.1 M were unstable they thinned until rupturing. The film lifetime measured from the first interferogram (appearing at a film thickness on the order of 500 nm) until the film rupture was only a second or so. However, relatively long lasting and nondraining films prepared from salt solutions above 0.1 M were observed. The film lifetime was significantly longer by 1 to 2 orders of magnitude, i.e., from 10 to 100 s. Importantly, both the film lifetime and the (average) thickness of the nondraining films increased with increasing salt concentration. This effect has not been observed with foam films stabilized by surfactants. The film lifetime and thickness also increased with increasing film radius. The films exhibited significant surface corrugations. The films with large radii often contained standing dimples. There was a critical film radius below which the films thinned until rupturing. In the cases of NaAc and NaClO 3, the films were unstable at all radii and salt concentrations they thinned until rupturing, ruling out the effect of solution viscosity on stabilizing the films.

  19. Salt Marsh

    NSDL National Science Digital Library

    High school level and higher description of Spartina salt marshes with pictures. Page is full of fantastic photographs most featuring a descriptive caption. Topics discussed include zonation, succession, and the intertidal zone. The habitat's associated flora and fauna are discussed. Organisms of particular interest include: Spartina alterniflora, Spartina patens, Geukenzia demissa, Mytilus edulis, Distichlis spicata, Salicornia, Melampus bidentatus, Ilyanassa obsoleta, and Hydrobia totteni.

  20. [Pharmacokinetics and general pharmacological actions of lithium salts administered singly or repeatedly].

    PubMed

    Ozawa, H; Nozu, T; Aihara, H; Akiyama, F; Sasajima, M

    1976-05-01

    Absorption, distribution and excretion after oral administration of lithium carbonate (Li2CO3) and/or lithium chloride (LiCl) were studied in Wistar rats and beagle dogs. The maximum level of concentration in the blood was seen within 4 hr after administration of Li2CO3, and a greater part of the orally dosed Li2CO3 was excreted into the urine. The blood and urine Li levels after the administration of LiCl were similar to those seen with Li2CO3. In dogs, Li2CO3 was more slowly excreted into the urine than it was in rats. Li was selectively incorporated into the thyroid and pituitary a short time after administration, and was not detected in any organ 7 days after cessation of repeated dosing for 19 days. The movement of Li into the brain was slow and relatively low levels were achieved after a single administration, but high and constant levels were shown after repeated administration. Effects of Li salts on behavior of ddy mice with repeated administration were investigated. The spontaneous motor activity was suppressed with Li2CO3 more strongly than with LiCl. The high dose of Li2CO3 suppressed not only the stimulating actions of methamphetamine and cocaine, but the ptotic and hypothermic action of reserpine. From these results, it is concluded that the repeated administration of Li salts reveals higher levels of Li ion in the brain than does a single administration, and also more responsive action on the central nervous system. PMID:987975

  1. A new compound heterozygous frameshift mutation in the type II 3{beta}-hydroxysteroid dehydrogenase 3{beta}-HSD gene causes salt-wasting 3{beta}-HSD deficiency congenital adrenal hyperplasia

    SciTech Connect

    Zhang, L.; Sakkal-Alkaddour, S.; Chang, Ying T.; Yang, Xiaojiang; Songya Pang [Univ. of Illinois, Chicago, IL (United States)] [Univ. of Illinois, Chicago, IL (United States)

    1996-01-01

    We report a new compound heterozygous frameshift mutation in the type II 3{Beta}-hydroxysteroid dehydrogenase (3{beta}-HSD) gene in a Pakistanian female child with the salt-wasting form of 3{Beta}-HSD deficiency congenital adrenal hyperplasia. The etiology for her congenital adrenal hyperplasia was not defined. Although the family history suggested possible 3{beta}-HSd deficiency disorder, suppressed adrenal function caused by excess glucocorticoid therapy in this child at 7 yr of age did not allow hormonal diagnosis. To confirm 3{beta}-HSD deficiency, we sequenced the type II 3{beta}-HSD gene in the patient, her family, and the parents of her deceased paternal cousins. The type II 3{beta}-HSD gene region of a putative promotor, exons I, II, III, and IV, and exon-intron boundaries were amplified by PCR and sequenced in all subjects. The DNA sequence of the child revealed a single nucleotide deletion at codon 318 [ACA(Thr){r_arrow}AA] in exon IV in one allele, and two nucleotide deletions at codon 273 [AAA(Lys){r_arrow}A] in exon IV in the other allele. The remaining gene sequences were normal. The codon 318 mutation was found in one allele from the father, brother, and parents of the deceased paternal cousins. The codon 273 mutation was found in one allele of the mother and a sister. These findings confirmed inherited 3{beta}-HSD deficiency in the child caused by the compound heterozygous type II 3{beta}-HSD gene mutation. Both codons at codons 279 and 367, respectively, are predicted to result in an altered and truncated type II 3{beta}-HSD protein, thereby causing salt-wasting 3{beta}-HSD deficiency in the patient. 21 refs., 2 figs., 1 tab.

  2. Kinetic analysis of E. coli inactivation by high hydrostatic pressure with salts.

    PubMed

    Ueno, Shigeaki; Shigematsu, Toru; Hasegawa, Toshimi; Higashi, Jun; Anzai, Mayumi; Hayashi, Mayumi; Fujii, Tomoyuki

    2011-01-01

    Inactivation of E. coli by high hydrostatic pressure (250 to 400 MPa) with salts was investigated based on kinetic analysis. At concentrations from 0.074 to 0.145 M and from 0.240 to 0.290 M, both the absolute activation volumes and the preexponential factors were similar in KCl, NaCl, and LiCl solutions, suggesting that pressure inactivation is not salt-specific. On the other hand, in the intermediate salt-concentration range of 0.145 to 0.240 M, inactivation kinetics in the presence of the Na(+) and K(+) differed significantly from those in the presence of Li(+) (P < 0.05). In this concentration range, effect of salt stress and osmotic stress differed significantly from those in concentrations below 0.145 M or above 0.240 M. The cellular response to pressure varies with salt type and salt concentration. These novel findings provide important clues to distinguish between salt stress and osmotic stress in the inactivation of E. coli. PMID:21535693

  3. Site characterization plan: Gulf Coast salt domes

    SciTech Connect

    Not Available

    1983-12-01

    The National Waste Terminal Storage (NWTS) program of the US Department of Energy (DOE) is responsible for developing technology and providing facilities for safe, environmentally acceptable, permanent disposal of high-level nuclear waste. The Office of Nuclear Waste Isolation has been intensively investigating Gulf Coast Salt Dome Basin salt domes and bedded salt in Texas and Utah since 1978. In the Gulf Coast, the application of screening criteria in the region phase led to selection of eight domes for further study in the location phase. Further screening in the area phase identified four domes for more intensive study in the location phase: Oakwood Dome, Texas; Vacherie Dome, Louisiana; and Richton Dome and Cypress Creek Dome, Mississippi. For each dome, this Site Characterization Plan identifies specific hydrologic, geologic, tectonic, geochemical, and environmental key issues that are related to the DOE/NWTS screening criteria or affect the feasibility of constructing an exploratory shaft. The Site Characterization Plan outlines studies need to: (1) resolve issues sufficiently to allow one or more salt domes to be selected and compared to bedded salt sites in order to determine a prime salt site for an exploratory shaft; (2) conduct issue-related studies to provide a higher level of confidence that the preferred salt dome site is viable for construction of an exploratory shaft; and (3) provide a vehicle for state input to issues. Extensive references, 7 figures, 20 tables.

  4. Molten salt-based growth of bulk GaN and InN for substrates.

    SciTech Connect

    Waldrip, Karen Elizabeth

    2007-08-01

    An atmospheric pressure approach to growth of bulk group III-nitrides is outlined. Native III-nitride substrates for optoelectronic and high power, high frequency electronics are desirable to enhance performance and reliability of these devices; currently, these materials are available in research quantities only for GaN, and are unavailable in the case of InN. The thermodynamics and kinetics of the reactions associated with traditional crystal growth techniques place these activities on the extreme edges of experimental physics. The novel techniques described herein rely on the production of the nitride precursor (N{sup 3-}) by chemical and/or electrochemical methods in a molten halide salt. This nitride ion is then reacted with group III metals in such a manner as to form the bulk nitride material. The work performed during the period of funding (February 2006-September 2006) focused on establishing that mass transport of GaN occurs in molten LiCl, the construction of a larger diameter electrochemical cell, the design, modification, and installation of a made-to-order glove box (required for handling very hygroscopic LiCl), and the feasibility of using room temperature molten salts to perform nitride chemistry experiments.

  5. Subsidence and collapse at Texas Salt Domes

    SciTech Connect

    Mullican, W.F.

    1989-01-01

    This book provides a description of the mechanisms and extent of natural and man-induced subsidence and collapse at Texas salt domes. In the Houston diapir province, Frasch mining has caused subsidence bowls and collapse sinkholes at 12 of the 14 sulfur-productive domes. Understanding the structural and hydrologic instability that results at the surface and subsurface is crucial in evaluating the suitability of salt domes as repositories for waste disposal. Part of the Bureau's Coastal Salt Dome Program, this study used aerial photographs, remote-sensing methods, historical and modern topographic maps, and field checks to detect subsidence and collapse associated with natural salt diapiric processes and commercial resource recovery and to determine which processes are likely to reduce the stability and integrity of hydrologic and structural barriers around salt diapirs. Figures and tables illustrating the extent and evolution of subsidence and collapse, along with photographs showing their effects, highlight the text discussion of the salt domes detailed in this study-Boling, Orchard, Moss Bluff, Spindletop, Hoskins Mound, Fannett, Long Point, Nash, High Island, Bryan Mound, Clemens, and Gulf. The author concludes that Frasch sulfur mining from cap rocks causes the most catastrophic subsidence and collapse and that subsidence over salt domes includes processes ranging from trough subsidence to various types of subsurface caving. He concludes that salt domes characterized by subsidence and collapse are unfavorable sites for storage/disposal of hazardous wastes.

  6. Salt splitting using ceramic membranes

    SciTech Connect

    Kurath, D.E. [Pacific Northwest National Lab., Richland, WA (United States)

    1997-10-01

    Many radioactive aqueous wastes in the DOE complex have high concentrations of sodium that can negatively affect waste treatment and disposal operations. Sodium can decrease the durability of waste forms such as glass and is the primary contributor to large disposal volumes. Waste treatment processes such as cesium ion exchange, sludge washing, and calcination are made less efficient and more expensive because of the high sodium concentrations. Pacific Northwest National Laboratory (PNNL) and Ceramatec Inc. (Salt Lake City UT) are developing an electrochemical salt splitting process based on inorganic ceramic sodium (Na), super-ionic conductor (NaSICON) membranes that shows promise for mitigating the impact of sodium. In this process, the waste is added to the anode compartment, and an electrical potential is applied to the cell. This drives sodium ions through the membrane, but the membrane rejects most other cations (e.g., Sr{sup +2}, Cs{sup +}). The charge balance in the anode compartment is maintained by generating H{sup +} from the electrolysis of water. The charge balance in the cathode is maintained by generating OH{sup {minus}}, either from the electrolysis of water or from oxygen and water using an oxygen cathode. The normal gaseous products of the electrolysis of water are oxygen at the anode and hydrogen at the cathode. Potentially flammable gas mixtures can be prevented by providing adequate volumes of a sweep gas, using an alternative reductant or destruction of the hydrogen as it is generated. As H{sup +} is generated in the anode compartment, the pH drops. The process may be operated with either an alkaline (pH>12) or an acidic anolyte (pH <1). The benefits of salt splitting using ceramic membranes are (1) waste volume reduction and reduced chemical procurement costs by recycling of NaOH; and (2) direct reduction of sodium in process streams, which enhances subsequent operations such as cesium ion exchange, calcination, and vitrification.

  7. Efficacy of a Solution-Based Approach for Making Sodalite Waste Forms for an Oxide Reduction Salt Used in the Reprocessing of Used Uranium Oxide Fuel

    SciTech Connect

    Brian J. Riley; David A. Pierce; Steven M. Frank; Josef Matyas; Carolyne A. Burns

    2014-09-01

    This paper describes the various approaches attempted to make solution-derived sodalite with a LiCl-Li2O oxide reduction salt used to dissolve used uranium oxide fuel so the uranium can be recovered and recycled. The approaches include modified sol-gel and solutionbased synthesis processes. As-made products were mixed with 5 and 10 mass% of a Na2O-B2O3- SiO2 glass binder and these, along with product without a binder, were heated using either a cold-press-and-sinter method or hot uniaxial pressing. The results demonstrate the limitation of sodalite yield due to the fast intermediate reactions between Na+ and Cl- to form halite in solution and Li2O and SiO2 to form lithium silicates (e.g., Li2SiO3 or Li2Si2O5) in the calcined and sintered pellets. The results show that pellets can be made with high sodalite fractions in the crystalline product (~92 mass%) and low porosities using a solution-based approach and this LiCl-Li2O salt but that the incorporation of Li into the sodalite is low.

  8. Efficacy of a solution-based approach for making sodalite waste forms for an oxide reduction salt utilized in the reprocessing of used uranium oxide fuel

    DOE PAGESBeta

    Riley, Brian J.; Pierce, David A.; Frank, Steven M.; Matyáš, Josef; Burns, Carolyne A.

    2015-04-01

    This paper describes the various approaches attempted to make solution-derived sodalite with a LiCl-Li2O oxide reduction salt used to dissolve used uranium oxide fuel so the uranium can be recovered and recycled. The approaches include modified sol-gel and solutionbased synthesis processes. As-made products were mixed with 5 and 10 mass% of a Na2O-B2O3- SiO2 glass binder and these, along with product without a binder, were heated using either a cold-press-and-sinter method or hot uniaxial pressing. The results demonstrate the limitation of sodalite yield due to the fast intermediate reactions between Na+ and Cl- to form halite in solution and Li2Omore »and SiO2 to form lithium silicates (e.g., Li2SiO3 or Li2Si2O5) in the calcined and sintered pellets. The results show that pellets can be made with high sodalite fractions in the crystalline product (~92 mass%) and low porosities using a solution-based approach and this LiCl-Li2O salt but that the incorporation of Li into the sodalite is low.« less

  9. Understanding radioactive waste

    SciTech Connect

    Murray, R.L.

    1981-12-01

    This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

  10. Recovery of valuable materials from aluminium salt cakes

    Microsoft Academic Search

    W. J. Bruckard; J. T. Woodcock

    2009-01-01

    Salt cakes, which are nominally waste products derived from aluminium dross melting furnaces, are complex mixtures of some 20 different compounds made up of many different elements. Normally they are regarded as waste products and they are disposed of in toxic waste dumps. However, it is shown here that some components are readily recoverable as high-grade products for recycling or

  11. Resistivity measurements of halide-salt/MgO separators for thermal cells

    NASA Astrophysics Data System (ADS)

    Redey, Lazlo; McParland, Margaret; Guidotti, Ron

    1990-03-01

    Resistivities of 20 compositions of halide-salt/MgO mixtures (various selections and percentages of LiF, LiCl, LiBr, KCl, KBr, CsBr, and MgO) to be used in Li-alloy/metal sulfide cells were measured at temperatures between the melting point of a particular mixture and 500 C. The resistivities were determined with cold pressed electrolyte-binder pellets by using a special cell and dc measuring technique. Temperature, salt composition, and MgO content were found to have a strong influence on resistivity. These factors are listed in decreasing order of the magnitude of the effect. The fabrication density (porosity) of the pellet also has some effect on resistivity. These measured resistivities provide a data base to select optimum compositions of electrolyte-binder pellets for LiSi/FeS2 thermal batteries and to calculate area-specific resistances of these components for battery modeling and optimization.

  12. Application to ship nonmixed transuranic waste to the Nevada Test Site for interim storage. Waste Cerification Program

    SciTech Connect

    Not Available

    1993-12-01

    This report documents various regulations on radioactive waste processing and discusses how the Waste Isolation Pilot Plant will comply with and meet these requirements. Specific procedures are discussed concerning transuranic, metal scrap, salt block, solid, and glove box wastes.

  13. Polyethylene encapsulation of molten salt oxidation mixed low-level radioactive salt residues

    SciTech Connect

    Lageraaen, P.R.; Kalb, P.D. [Brookhaven National Lab., Upton, NY (United States); Grimmett, D.L.; Gay, R.L.; Newman, C.D. [Energy Technology Engineering Center, Canoga Park, CA (United States)

    1995-10-01

    A limited scope treatability study was conducted for polyethylene encapsulation of salt residues generated by a Molten Salt Oxidation (MSO) technology demonstration at the Energy Technology Engineering Center (ETEC), operated by Rockwell International for the US Department of Energy (DOE). During 1992 and 1993, ETEC performed a demonstration with a prototype MSO unit and treated approximately 50 gallons of mixed waste comprised of radioactively contaminated oils produced by hot cell operations. A sample of the mixed waste contaminated spent salt was used during the BNL polyethylene encapsulation treatability study. A nominal waste loading of 50 wt % was successfully processed and waste form test specimens were made for Toxicity Characteristic Leaching Procedure (TCLP) testing. The encapsulated product was compared with base-line TCLP results for total chromium and was found to be well within allowable EPA guidelines.

  14. Effects of heating on salt-occluded zeolite

    SciTech Connect

    Lewis, M.A.; Hash, M.C.; Pereira, C.; Ackerman, J.P.

    1996-05-01

    The electrometallurgical treatment of spent nuclear fuel generates a waste stream of fission products in the electrolyte, LiCl-KCl eutectic salt. Argonne National Laboratory is developing a mineral waste form for this waste stream. The waste form consists of a composite formed by hot pressing salt-occluded zeolite and a glass binder. Pressing conditions must be judiciously chosen. For a given pressure, increasing temperatures and hold times give denser products but the zeolite is frequently converted to sodalite. Reducing the temperature or hold time leads to a porous zeolite composite. Therefore, conditions that affect the thermal stability of salt-occluded zeolite both with and without glass are being investigated in an ongoing study. The parameters varied in this stage of the work were heating time, temperature, salt loading, and glass content. The heat-treated samples were examined primarily by X-ray diffraction. Large variations were found in the rate at which salt-occluded zeolite converted to other phases such as nepheline, salt, and sodalite. The products depended on the initial salt loading. Heating times required for these transitions depended on the procedure and temperature used to prepare the salt-occluded zeolite. Mixtures of glass and zeolite reacted much faster than the pure salt-occluded zeolite and were almost always converted to sodalite.

  15. GEOTECHNICAL ASSESSMENT AND INSTRUMENTATION NEEDS FOR NUCLEAR WASTE ISOLATION IN CRYSTALLINE AND ARGILLACEOUS ROCKS SYMPOSIUM

    E-print Network

    Authors, Various

    2011-01-01

    mechanical cycle result in increased rock mass permeability?rock units (International symposium on Management of Waste from the LWR Fuel Cycle,Cycle and Waste Management (1978) emphasizes the need to evaluate both salt and non-salt rocks

  16. Chemical degradation of an ion exchange resin processing salt solutions

    Microsoft Academic Search

    Stuart T. Arm; David L. Blanchard; Sandra K. Fiskum

    2005-01-01

    This paper describes the results from an investigation into the chemical degradation of an organic ion exchange resin, SuperLig® 644, over 25 repeated cycles separating cesium from an alkaline solution of sodium salts with subsequent elution. Battelle Pacific Northwest Division (PNWD) tested the resin with a salt solution simulating the radioactive wastes currently stored at Hanford, Washington, USA generated from

  17. Electrolyte salts for power sources

    DOEpatents

    Doddapaneni, Narayan (10516 Royal Birkdale, NE., Albuquerque, NM 87111); Ingersoll, David (5824 Mimosa Pl., NE., Albuquerque, NM 87111)

    1995-01-01

    Electrolyte salts for power sources comprising salts of phenyl polysulfonic acids and phenyl polyphosphonic acids. The preferred salts are alkali and alkaline earth metal salts, most preferably lithium salts.

  18. Electrolyte salts for power sources

    DOEpatents

    Doddapaneni, N.; Ingersoll, D.

    1995-11-28

    Electrolyte salts are disclosed for power sources comprising salts of phenyl polysulfonic acids and phenyl polyphosphonic acids. The preferred salts are alkali and alkaline earth metal salts, most preferably lithium salts. 2 figs.

  19. Technical review of Molten Salt Oxidation

    SciTech Connect

    Not Available

    1993-12-01

    The process was reviewed for destruction of mixed low-level radioactive waste. Results: extensive development work and scaleup has been documented on coal gasification and hazardous waste which forms a strong experience base for this MSO process; it is clearly applicable to DOE wastes such as organic liquids and low-ash wastes. It also has potential for processing difficult-to-treat wastes such as nuclear grade graphite and TBP, and it may be suitable for other problem waste streams such as sodium metal. MSO operating systems may be constructed in relatively small units for small quantity generators. Public perceptions could be favorable if acceptable performance data are presented fairly; MSO will likely require compliance with regulations for incineration. Use of MSO for offgas treatment may be complicated by salt carryover. Figs, tabs, refs.

  20. PySALT: the SALT science pipeline

    NASA Astrophysics Data System (ADS)

    Crawford, Steven M.; Still, Martin; Schellart, Pim; Balona, Luis; Buckley, David A. H.; Dugmore, Garith; Gulbis, Amanda A. S.; Kniazev, Alexei; Kotze, Marissa; Loaring, Nicola; Nordsieck, Kenneth H.; Pickering, Timothy E.; Potter, Stephen; Romero Colmenero, Encarni; Vaisanen, Petri; Williams, Theodore; Zietsman, Ewald

    2010-07-01

    PySALT is the python/PyRAF-based data reduction and analysis pipeline for the Southern African Large Telescope (SALT), a modern 10m class telescope with a large user community consisting of 13 partner institutions. The two first generation instruments on SALT are SALTICAM, a wide-field imager, and the Robert Stobie Spectrograph (RSS). Along with traditional imaging and spectroscopy modes, these instruments provide a wide range of observing modes, including Fabry-Perot imaging, polarimetric observations, and high-speed observations. Due to the large user community, resources available, and unique observational modes of SALT, the development of reduction and analysis software is key to maximizing the scientific return of the telescope. PySALT is developed in the Python/PyRAF environment and takes advantage of a large library of open-source astronomical software. The goals in the development of PySALT are: (1) Provide science quality reductions for the major operational modes of SALT, (2) Create analysis tools for the unique modes of SALT, and (3) Create a framework for the archiving and distribution of SALT data. The data reduction software currently provides support for the reduction and analysis of regular imaging, high-speed imaging, and long slit spectroscopy with planned support for multi-object spectroscopy, high-speed spectroscopy, Fabry-Perot imaging, and polarimetric data sets. We will describe the development and current status of PySALT and highlight its benefits through early scientific results from SALT.

  1. Matrix optimisation for hazardous organic waste sorption

    Microsoft Academic Search

    I. Natali Sora; R. Pelosato; L. Zampori; D. Botta; G. Dotelli; M. Vitelli

    2005-01-01

    Organophilic clays have proven to be interesting intermediates for the definitive stabilization of hazardous organic waste in cement matrix. In the present work, the influence of quaternary ammonium salt structure on the organophilic clay load capacity and the interaction type with the organic waste were investigated. Commercial organophilic montmorillonite clays, containing an ammonium quaternary salt with methyl and long chain

  2. Fracture and Healing of Rock Salt Related to Salt Caverns

    SciTech Connect

    Chan, K.S.; Fossum, A.F.; Munson, D.E.

    1999-03-01

    In recent years, serious investigations of potential extension of the useful life of older caverns or of the use of abandoned caverns for waste disposal have been of interest to the technical community. All of the potential applications depend upon understanding the reamer in which older caverns and sealing systems can fail. Such an understanding will require a more detailed knowledge of the fracture of salt than has been necessary to date. Fortunately, the knowledge of the fracture and healing of salt has made significant advances in the last decade, and is in a position to yield meaningful insights to older cavern behavior. In particular, micromechanical mechanisms of fracture and the concept of a fracture mechanism map have been essential guides, as has the utilization of continuum damage mechanics. The Multimechanism Deformation Coupled Fracture (MDCF) model, which is summarized extensively in this work was developed specifically to treat both the creep and fracture of salt, and was later extended to incorporate the fracture healing process known to occur in rock salt. Fracture in salt is based on the formation and evolution of microfractures, which may take the form of wing tip cracks, either in the body or the boundary of the grain. This type of crack deforms under shear to produce a strain, and furthermore, the opening of the wing cracks produce volume strain or dilatancy. In the presence of a confining pressure, microcrack formation may be suppressed, as is often the case for triaxial compression tests or natural underground stress situations. However, if the confining pressure is insufficient to suppress fracture, then the fractures will evolve with time to give the characteristic tertiary creep response. Two first order kinetics processes, closure of cracks and healing of cracks, control the healing process. Significantly, volume strain produced by microfractures may lead to changes in the permeability of the salt, which can become a major concern in cavern sealing and operation. The MDCF model is used in three simulations of field experiments in which indirect measures were obtained of the generation of damage. The results of the simulations help to verify the model and suggest that the model captures the correct fracture behavior of rock salt. The model is used in this work to estimate the generation and location of damage around a cylindrical storage cavern. The results are interesting because stress conditions around the cylindrical cavern do not lead to large amounts of damage. Moreover, the damage is such that general failure can not readily occur, nor does the extent of the damage suggest possible increased permeation when the surrounding salt is impermeable.

  3. Removal of uranium from spent salt from the moltensalt oxidation process

    SciTech Connect

    Summers, L.; Hsu, P. C.; Holtz, E. V.; Hipple, D.; Wang, F.; Adamson, M.

    1997-03-01

    Molten salt oxidation (MSO) is a thermal process that has the capability of destroying organic constituents of mixed wastes, hazardous wastes, and energetic materials. In this process, combustible waste and air are introduced into the molten sodium carbonate salt. The organic constituents of the waste materials are oxidized to carbon dioxide and water, while most of the inorganic constituents, including toxic metals, minerals, and radioisotopes, are retained in the molten salt bath. As these impurities accumulate in the salt, the process efficiency drops and the salt must be replaced. An efficient process is needed to separate these toxic metals, minerals, and radioisotopes from the spent carbonate to avoid generating a large volume of secondary waste. Toxic metals such as cadmium, chromium, lead, and zinc etc. are removed by a method described elsewhere. This paper describes a separation strategy developed for radioisotope removal from the mixed spent salt, as well as experimental results, as part of the spent salt cleanup. As the MSO system operates, inorganic products resulting from the reaction of halides, sulfides, phosphates, metals and radionuclides with carbonate accumulate in the salt bath. These must be removed to prevent complete conversion of the sodium carbonate, which would result in eventual losses of destruction efficiency and acid scrubbing capability. There are two operational modes for salt removal: (1) during reactor operation a slip-stream of molten salt is continuously withdrawn with continuous replacement by carbonate, or (2) the spent salt melt is discharged completely and the reactor then refilled with carbonate in batch mode. Because many of the metals and/or radionuclides captured in the salt are hazardous and/or radioactive, spent salt removed from the reactor would create a large secondary waste stream without further treatment. A spent salt clean up/recovery system is necessary to segregate these materials and minimize the amount of secondary waste. These materials can then be encapsulated for final disposal.

  4. SALT CORE SAMPLING EVOLUTION AT THE SAVANNAH RIVER SITE

    SciTech Connect

    Nance, T; Daniel Krementz, D; William Cheng, W

    2007-11-29

    The Savannah River Site (SRS), a Department of Energy (DOE) facility, has over 30 million gallons of legacy waste from its many years of processing nuclear materials. The majority of waste is stored in 49 buried tanks. Available underground piping is the primary and desired pathway to transfer waste from one tank to another until the waste is delivered to the glass plant, DWPF, or the grout plant, Saltstone. Prior to moving the material, the tank contents need to be evaluated to ensure the correct destination for the waste is chosen. Access ports are available in each tank top in a number of locations and sizes to be used to obtain samples of the waste for analysis. Material consistencies vary for each tank with the majority of waste to be processed being radioactive salts and sludge. The following paper describes the progression of equipment and techniques developed to obtain core samples of salt and solid sludge at SRS.

  5. Pyrochemical process for extracting plutonium from an electrolyte salt

    DOEpatents

    Mullins, Lawrence J. (Los Alamos, NM); Christensen, Dana C. (Los Alamos, NM)

    1984-01-01

    A pyrochemical process for extracting plutonium from a plutonium-bearing salt is disclosed. The process is particularly useful in the recovery of plutonium from electrolyte salts which are left over from the electrorefining of plutonium. In accordance with the process, the plutonium-bearing salt is melted and mixed with metallic calcium. The calcium reduces ionized plutonium in the salt to plutonium metal, and also causes metallic plutonium in the salt, which is typically present as finely dispersed metallic shot, to coalesce. The reduced and coalesced plutonium separates out on the bottom of the reaction vessel as a separate metallic phase which is readily separable from the overlying salt upon cooling of the mixture. Yields of plutonium are typically on the order of 95%. The stripped salt is virtually free of plutonium and may be discarded to low-level waste storage.

  6. Pyrochemical process for extracting plutonium from an electrolyte salt

    DOEpatents

    Mullins, L.J.; Christensen, D.C.

    1982-09-20

    A pyrochemical process for extracting plutonium from a plutonium-bearing salt is disclosed. The process is particularly useful in the recovery of plutonium for electrolyte salts which are left over from the electrorefining of plutonium. In accordance with the process, the plutonium-bearing salt is melted and mixed with metallic calcium. The calcium reduces ionized plutonium in the salt to plutonium metal, and also causes metallic plutonium in the salt, which is typically present as finely dispersed metallic shot, to coalesce. The reduced and coalesced plutonium separates out on the bottom of the reaction vessel as a separate metallic phase which is readily separable from the overlying salt upon cooling of the mixture. Yields of plutonium are typically on the order of 95%. The stripped salt is virtually free of plutonium and may be discarded to low-level waste storage.

  7. Experimental research on thermal damage of Yingcheng Mine rock salt with ultrasonic wave testing

    Microsoft Academic Search

    J. Chen; H. Tang; C. Yang

    2009-01-01

    Because of the special mechanical properties (creep behavior, damage and healing, low permeability), rock salt formation can be used for the high level radioactive waste disposal, and the thermal damage property of rock salt is important issue for the stability and sealing of the cavern. For investigation of the thermal damage characteristic of Yingcheng Mine rock salt (Hubei Provence, P.R.

  8. Waste treatment for removed protective coatings

    SciTech Connect

    Gat, U.; Crosley, S.M. [Oak Ridge National Lab., TN (United States); Gay, R.L. [Rockwell International Corp., Canoga Park, CA (United States)

    1993-07-01

    A molten salt oxidation process is proposed for treatment of removed protective coatings along with the media used for removal. The treatment chemically reduces the waste, leaving any metals associated with the coating as a residue in the salt treatment media. The residue and the salt can be further treated for recycle of the metals, thus all but eliminating metal disposal as a waste problem. The process is expected to be simple and may be integrated into the coatings removal operations on location. Therefore, waste shipment and handling can be significantly reduced, and, as a secondary benefit, other waste can be treated in the same unit.

  9. Diffusion of actinides in NaCl single crystals and in real rock salt

    NASA Astrophysics Data System (ADS)

    Matzkey, Hj; Dyment, F.

    1991-11-01

    In order to provide missing data for storage of actinide containing solidified radioactive waste in deep underground dry geological formations such as salt domes, the tracer diffusion of U-233 was measured in single crystals of NaCl and in actual salt of a repository site (Asse mine in FR Germany). Experiments on interdiffusion between actinide-doped waste glasses and salt were also performed. The mean actinide penetration at the expected maximum temperature of the interface waste matrix/salt in 106 years is extrapolated to be ? 1 ?m for volume diffusion and ? a few ?m for grain boundary diffusion.

  10. Waste Encapsulation and Storage Facility (WESF) Waste Analysis Plan

    SciTech Connect

    SIMMONS, F.M.

    2000-12-01

    The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

  11. Valence and excited dipole-bound states of polar diatomic anions: LiH -, LiF -, LiCl -, NaH -, NaF -, NaCl -, BeO -, and MgO -

    NASA Astrophysics Data System (ADS)

    Gutsev, Gennady L.; Nooijen, Marcel; Bartlett, Rodney J.

    1997-09-01

    Valence and excited states of the anions formed by the polar molecules LiH, LiF, LiCl, NaH, NaF, NaCl, BeO, and MgO are calculated by the recently developed electron-attachment equation-of-motion coupled-cluster (EA-EOMCC) method. The LiH -, NaH -, and LiF - anions are found to possess two excited dipole-bound states and the LiCl -, NaF -, NaCl -, BeO -, and MgO - anions have three excited dipole-bound states. The critical values of the dipole moment required to sustain the first, second, etc., excited state appears to be specific for each class of polar molecules.

  12. Brines formed by multi-salt deliquescence

    SciTech Connect

    Carroll, S; Rard, J; Alai, M; Staggs, K

    2005-11-04

    The FY05 Waste Package Environment testing program at Lawrence Livermore National Laboratory focused on determining the temperature, relative humidity, and solution compositions of brines formed due to the deliquescence of NaCl-KNO{sub 3}-NaNO{sub 3} and NaCl-KNO{sub 3}-NaNO{sub 3}-Ca(NO{sub 3}){sub 2} salt mixtures. Understanding the physical and chemical behavior of these brines is important because they define conditions under which brines may react with waste canister surfaces. Boiling point experiments show that NaCl-KNO{sub 3}-NaNO{sub 3} and NaCl-KNO{sub 3}-NaNO{sub 3}-Ca(NO{sub 3}){sub 2} salt mixtures form brines that transform to hydrous melts that do not truly 'dry out' until temperatures exceed 300 and 400 C, respectively. Thus a conducting solution is present for these salt assemblages over the thermal history of the repository. The corresponding brines form at lower relative humidity at higher temperatures. The NaCl-KNO{sub 3}-NaNO{sub 3} salt mixture has a mutual deliquescence relative humidity (MDRH) of 25.9% at 120 C and 10.8% at 180 C. Similarly, the KNO{sub 3}-NaNO{sub 3} salt mixture has MDRH of 26.4% at 120 C and 20.0% at 150 C. The KNO{sub 3}-NaNO{sub 3} salt mixture salts also absorb some water (but do not appear to deliquesce) at 180 C and thus may also contribute to the transfer of electrons at interface between dust and the waste package surface. There is no experimental evidence to suggest that these brines will degas and form less deliquescent salt assemblages. Ammonium present in atmospheric and tunnel dust (as the chloride, nitrate, or sulfate) will readily decompose in the initial heating phase of the repository, and will affect subsequent behavior of the remaining salt mixture only through the removal of a stoichiometric equivalent of one or more anions. Although K-Na-NO{sub 3}-Cl brines form at high temperature and low relative humidity, these brines are dominated by nitrate, which is known to inhibit corrosion at lower temperature. Nitrate to chloride ratios of the NaCl-KNO{sub 3}-NaNO{sub 3} salt mixture are about NO{sub 3}:Cl = 19:1. The role of nitrate on corrosion at higher temperatures is addressed in a companion report (Dixit et al., 2005).

  13. Novel Ternary Molten Salt Electrolytes for intermediate-temperature sodium/nickel chloride batteries

    SciTech Connect

    Li, Guosheng; Lu, Xiaochuan; Coyle, Christopher A.; Kim, Jin Yong; Lemmon, John P.; Sprenkle, Vincent L.; Yang, Zhenguo

    2012-12-15

    The sodium-nickel chloride (ZEBRA) battery is typically operated at relatively high temperature (250~350°C) to achieve adequate electrochemical performance. Reducing the operating temperature in the range of 150 to 200°C can lead to enhanced cycle life by suppressing temperature related degradation mechanisms. The reduced temperature range also allows for lower cost materials of construction such as elastomeric sealants and gaskets. To achieve adequate electrochemical performance at lower operating temperatures requires an overall reduction in ohmic losses associated with temperature. This includes reducing the ohmic resistance of ?”-alumina solid electrolyte (BASE) and the incorporation of low melting point molten salt as the secondary electrolyte. In present work, planar-type Na/NiCl2 cells with a thin flat plate BASE (600 ?m) and low melting point secondary electrolyte were evaluated at reduced temperatures. Molten salt formulation for use as secondary electrolytes were fabricated by the partial replace of NaCl in the standard secondary electrolyte (NaAlCl4) with other lower melting point alkali metal salts such as NaBr, LiCl, and LiBr. Electrochemical characterization of the ternary molten salts demonstrated , improved ionic conductivity, and sufficient electrochemical window at reduced temperatures. Furthermore, Na/NiCl2 cells with 50 mol% NaBr-containing secondary electrolyte exhibited reduced polarizations at 175°C compared to the cell with the standard NaAlCl4 catholyte. The cells also exhibited stable cycling performance even at 150oC.

  14. Salt effect on the hydrophobic binding of p-toluidino naphthalene sulphonate with cyclodextrins

    NASA Astrophysics Data System (ADS)

    Sarkar, Nilmoni; Das, Kaustuv; Nath, Debnarayan; Bhattacharyya, Kankan

    1994-02-01

    Lithium chloride, lithium perchlorate, cesium bromide, tetra- n-butyl ammonium bromide (TBBr) and guanidine hydrochloride (GnCl) affect the fluorescence properties of 2, 6- p-toluidino naphthalene sulphonate (TNS) bound to ?- and ?-cyclodextrins (CD) in strikingly different ways. This indicates that the salts have considerable influence on the hydrophobic binding of TNS molecules with CDs. The salting-in agents (LiClO 4, CsBr and GnCl) markedly reduce the fluorescence quantum yield (? f) and lifetime (? f) of CD-bound TNS anion. It is suggested that they directly interact with the bound TNS ions. The salting-in agent TBBr increases ? f and ? f. This fluorescence enhancement indicates that the local polarity is reduced by wrapping the four n-butyl groups around the CD-bound TNS ions. The salting-out agent LiCl causes a marginal increase (< 15%) and that at a high concentration (7 M). In the absence of CD in aqueous solution on addition of 0.1 M TBBr; the fluorescence yield of TNS increases sixfold. This is attributed to clustering of TB cations around the TNS anion.

  15. Salt tectonics on Venus

    SciTech Connect

    Wood, C.A.; Amsbury, D.

    1986-05-01

    The discovery of a surprisingly high deuterium/hydrogen ratio on Venus immediately led to the speculation that Venus may have once had a volume of surface water comparable to that of the terrestrial oceans. The authors propose that the evaporation of this putative ocean may have yielded residual salt deposits that formed various terrain features depicted in Venera 15 and 16 radar images. By analogy with models for the total evaporation of the terrestrial oceans, evaporite deposits on Venus should be at least tens to hundreds of meters thick. From photogeologic evidence and in-situ chemical analyses, it appears that the salt plains were later buried by lava flows. On Earth, salt diapirism leads to the formation of salt domes, anticlines, and elongated salt intrusions - features having dimensions of roughly 1 to 100 km. Due to the rapid erosion of salt by water, surface evaporite landforms are only common in dry regions such as the Zagros Mountains of Iran, where salt plugs and glaciers exist. Venus is far drier than Iran; extruded salt should be preserved, although the high surface temperature (470/sup 0/C) would probably stimulate rapid salt flow. Venus possesses a variety of circular landforms, tens to hundreds of kilometers wide, which could be either megasalt domes or salt intrusions colonizing impact craters. Additionally, arcurate bands seen in the Maxwell area of Venus could be salt intrusions formed in a region of tectonic stress. These large structures may not be salt features; nonetheless, salt features should exist on Venus.

  16. Heterogeneity of Equilibrium Molten Globule State of Cytochrome c Induced by Weak Salt Denaturants under Physiological Condition

    PubMed Central

    Rahaman, Hamidur; Alam Khan, Md. Khurshid; Hassan, Md. Imtaiyaz; Islam, Asimul; Moosavi-Movahedi, Ali Akbar; Ahmad, Faizan

    2015-01-01

    While many proteins are recognized to undergo folding via intermediate(s), the heterogeneity of equilibrium folding intermediate(s) along the folding pathway is less understood. In our present study, FTIR spectroscopy, far- and near-UV circular dichroism (CD), ANS and tryptophan fluorescence, near IR absorbance spectroscopy and dynamic light scattering (DLS) were used to study the structural and thermodynamic characteristics of the native (N), denatured (D) and intermediate state (X) of goat cytochorme c (cyt-c) induced by weak salt denaturants (LiBr, LiCl and LiClO4) at pH 6.0 and 25°C. The LiBr-induced denaturation of cyt-c measured by Soret absorption (??400) and CD ([?]409), is a three-step process, N ? X ? D. It is observed that the X state obtained along the denaturation pathway of cyt-c possesses common structural and thermodynamic characteristics of the molten globule (MG) state. The MG state of cyt-c induced by LiBr is compared for its structural and thermodynamic parameters with those found in other solvent conditions such as LiCl, LiClO4 and acidic pH. Our observations suggest: (1) that the LiBr-induced MG state of cyt-c retains the native Met80-Fe(III) axial bond and Trp59-propionate interactions; (2) that LiBr-induced MG state of cyt-c is more compact retaining the hydrophobic interactions in comparison to the MG states induced by LiCl, LiClO4 and 0.5 M NaCl at pH 2.0; and (3) that there exists heterogeneity of equilibrium intermediates along the unfolding pathway of cyt-c as highly ordered (X1), classical (X2) and disordered (X3), i.e., D ? X3 ? X2 ? X1 ? N. PMID:25849212

  17. Heterogeneity of equilibrium molten globule state of cytochrome c induced by weak salt denaturants under physiological condition.

    PubMed

    Rahaman, Hamidur; Alam Khan, Md Khurshid; Hassan, Md Imtaiyaz; Islam, Asimul; Moosavi-Movahedi, Ali Akbar; Ahmad, Faizan

    2015-01-01

    While many proteins are recognized to undergo folding via intermediate(s), the heterogeneity of equilibrium folding intermediate(s) along the folding pathway is less understood. In our present study, FTIR spectroscopy, far- and near-UV circular dichroism (CD), ANS and tryptophan fluorescence, near IR absorbance spectroscopy and dynamic light scattering (DLS) were used to study the structural and thermodynamic characteristics of the native (N), denatured (D) and intermediate state (X) of goat cytochorme c (cyt-c) induced by weak salt denaturants (LiBr, LiCl and LiClO4) at pH 6.0 and 25°C. The LiBr-induced denaturation of cyt-c measured by Soret absorption (??400) and CD ([?]409), is a three-step process, N ? X ? D. It is observed that the X state obtained along the denaturation pathway of cyt-c possesses common structural and thermodynamic characteristics of the molten globule (MG) state. The MG state of cyt-c induced by LiBr is compared for its structural and thermodynamic parameters with those found in other solvent conditions such as LiCl, LiClO4 and acidic pH. Our observations suggest: (1) that the LiBr-induced MG state of cyt-c retains the native Met80-Fe(III) axial bond and Trp59-propionate interactions; (2) that LiBr-induced MG state of cyt-c is more compact retaining the hydrophobic interactions in comparison to the MG states induced by LiCl, LiClO4 and 0.5 M NaCl at pH 2.0; and (3) that there exists heterogeneity of equilibrium intermediates along the unfolding pathway of cyt-c as highly ordered (X1), classical (X2) and disordered (X3), i.e., D ? X3 ? X2 ? X1 ? N. PMID:25849212

  18. Utah: Salt Lake Region

    Atmospheric Science Data Center

    2014-05-15

    article title:  Winter and Summer Views of the Salt Lake Region     View Larger Image Magnificent views of the region surrounding Salt Lake City, Utah are captured in these winter and summer images from the ...

  19. Molten salt electrolyte separator

    DOEpatents

    Kaun, Thomas D. (New Lenox, IL)

    1996-01-01

    A molten salt electrolyte/separator for battery and related electrochemical systems including a molten electrolyte composition and an electrically insulating solid salt dispersed therein, to provide improved performance at higher current densities and alternate designs through ease of fabrication.

  20. Correlation of Creep Behavior of Domal Salts

    SciTech Connect

    Munson, D.E.

    1999-02-16

    The experimentally determined creep responses of a number of domal salts have been reported in, the literature. Some of these creep results were obtained using standard (conventional) creep tests. However, more typically, the creep data have come from multistage creep tests, where the number of specimens available for testing was small. An incremental test uses abrupt changes in stress and temperature to produce several time increments (stages) of different creep conditions. Clearly, the ability to analyze these limited data and to correlate them with each other could be of considerable potential value in establishing the mechanical characteristics of salt domes, both generally and specifically. In any analysis, it is necessary to have a framework of rules to provide consistency. The basis for the framework is the Multimechanism-Deformation (M-D) constitutive model. This model utilizes considerable general knowledge of material creep deformation to supplement specific knowledge of the material response of salt. Because the creep of salt is controlled by just a few micromechanical mechanisms, regardless of the origin of the salt, certain of the material parameters are values that can be considered universal to salt. Actual data analysis utilizes the methodology developed for the Waste Isolation Pilot Plant (WIPP) program, and the response of a bedded pure WIPP salt as the baseline for comparison of the domal salts. Creep data from Weeks Island, Bryan Mound, West Hackberry, Bayou Choctaw, and Big Hill salt domes, which are all sites of Strategic Petroleum Reserve (SPR) storage caverns, were analyzed, as were data from the Avery Island, Moss Bluff, and Jennings salt domes. The analysis permits the parameter value sets for the domal salts to be determined in terms of the M-D model with various degrees of completeness. In turn this permits detailed numerical calculations simulating cavern response. Where the set is incomplete because of the sparse database, reasonable assumptions permit the set to be completed. From the analysis, two distinct response groups were evident, with the salts of one group measurably more creep resistant than the other group. Interestingly, these groups correspond well with the indirectly determined creep closure of the SPR storage caverns, a correlation that probably should be expected. Certainly, the results suggest a simple laboratory determination of the creep characteristics of a salt material from a dome site can indicate the relative behavior of any potential cavern placed within that dome.

  1. Plant salt tolerance

    Microsoft Academic Search

    Jian-Kang Zhu

    2001-01-01

    Soil salinity is a major abiotic stress in plant agriculture worldwide. This has led to research into salt tolerance with the aim of improving crop plants. However, salt tolerance might have much wider implications because transgenic salt-tolerant plants often also tolerate other stresses including chilling, freezing, heat and drought. Unfortunately, suitable genetic model systems have been hard to find. A

  2. Shaking the Salt Habit

    MedlinePLUS

    ... Don't salt food before you taste it; enjoy the natural taste of food. Take the salt shaker off the table. Adding more salt at the table adds to your daily sodium intake without adding much to the flavor of your food. Eat less ...

  3. Plant salt tolerance

    Microsoft Academic Search

    Viswanathan Chinnusamy; Jian-Kang Zhu

    Soil salinity adversely affects crop productivity and quality. The success of breeding programs aimed at salinity tolerant crop varieties is limited by the lack of a clear understanding of the molecular basis of salt tolerance. Recent advances in genetic analysis of Arabidopsis mutants defective in salt tolerance, and molecular cloning of these loci, have showed some insight into salt stress

  4. INTERSTATE WASTE TECHNOLOGIES THERMOSELECT TECHNOLOGY

    E-print Network

    Columbia University

    OVERVIEW Zinc Concentrate Salt Clean water Sulfur Synthesis Gas Production of Hydrogen Methanol AmmoniaHigh Temperature Reactor Waste of all kinds Process water treatment Synthesis gas scrubbing Metals and Minerals Synthesis gas utilization: Gas Engine Generators Northeast Waste Processing Facility #12;14 U. S. Virgin

  5. Characterisation and management of incinerator wastes

    Microsoft Academic Search

    R Ibáñez; A Andrés; J. R Viguri; I Ortiz; J. A Irabien

    2000-01-01

    Management of municipal and hospital wastes by means of incineration processes generates solid residues, such as bottom and fly ashes and air pollution control residues with high content of heavy metals, inorganic salts and other organic compounds. Characterisation of 24 ash samples, collected from four municipal solid waste incinerators (MSWI) and six hospital medical waste incinerators (HMWI) located in the

  6. Brine flow in heated geologic salt.

    SciTech Connect

    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.

  7. Nitrate removal using a mixed-culture entrapped microbial cell immobilization process under high salt conditions

    Microsoft Academic Search

    P. Y. Yang; S. Nitisoravut; Jy S. Wu

    1995-01-01

    Brine wastes resulting from the regeneration of exhausted ion exchange resins require further treatment for final disposal. In this study, a mixed-culture entrapped microbial cell immobilization (EMCI) process for nitrate removal from brine wastes was examined. Because of the presence of elevated concentrations of sodium chloride or sodium bicarbonate in the brine waste, the effects of high salt concentrations on

  8. Photochemistry of triarylsulfonium salts

    SciTech Connect

    Dektar, J.L.; Hacker, N.P. (Almaden Research Center, San Jose, CA (USA))

    1990-08-01

    The photolysis of triphenylsulfonium, tris(4-methylphenyl)sulfonium, tris(4-chlorophenyl)sulfonium, several monosubstituted (4-F, 4-Cl, 4-Me, 4-MeO, 4-PhS, and 4-PhCO), and disubstituted (4,4{prime}-Me{sub 2} and 4,4{prime}-(MeO){sub 2}) triphenylsulfonium salts was examined in solution. It was found that direct irradiation of triphenylsulfonium salts produced new rearrangement products, phenylthiobiphenyls, along with diphenyl sulfide, which had been previously reported. Similarly, the triarylsulfonium salts, with the exception of the (4-(phenylthio)phenyl)diphenylsulfonium salts produced new rearrangement products, phenylthiobiphenyls, along with diphenyl sulfide, which had been previously reported. Similarly, the triarylsulfonium salts, with the exception of the (4-(phenylthio)phenyl)diphenylsulfonium salts, gave the new rearrangement products. The mechanism for direct photolysis is proposed to occur from the singlet excited states to give a predominant heterolytic cleavage along with some homolytic cleavage.

  9. A Dash of Salt 

    E-print Network

    Supercinski, Danielle

    2006-01-01

    more landscapes damaged from too much salt in the water (containing dissolved salts near or in excess of 1,000 parts per million) used for irrigation. ?We just do not have good guidelines to assess potential salinity hazards to landscape plants... with El Paso Water Utilities on plant response to soil salinity. Landscape plant lists for salt tolerance assessment and Photo Guide: Landscape plant response to salinity covers more than 100 species of plants used for landscapes in the Southwest...

  10. Reference repository design concept for bedded salt

    SciTech Connect

    Carpenter, D.W.; Martin, R.W.

    1980-10-08

    A reference design concept is presented for the subsurface portions of a nuclear waste repository in bedded salt. General geologic, geotechnical, hydrologic and geochemical data as well as descriptions of the physical systems are provided for use on generic analyses of the pre- and post-sealing performance of repositories in this geologic medium. The geology of bedded salt deposits and the regional and repository horizon stratigraphy are discussed. Structural features of salt beds including discontinuities and dissolution features are presented and their effect on repository performance is discussed. Seismic hazards and the potential effects of earthquakes on underground repositories are presented. The effect on structural stability and worker safety during construction from hydrocarbon and inorganic gases is described. Geohydrologic considerations including regional hydrology, repository scale hydrology and several hydrological failure modes are presented in detail as well as the hydrological considerations that effect repository design. Operational phase performance is discussed with respect to operations, ventilation system, shaft conveyances, waste handling and retrieval systems and receival rates of nuclear waste. Performance analysis of the post sealing period of a nuclear repository is discussed, and parameters to be used in such an analysis are presented along with regulatory constraints. Some judgements are made regarding hydrologic failure scenarios. Finally, the design and licensing process, consistent with the current licensing procedure is described in a format that can be easily understood.

  11. Reduction of nitrate and nitrite salts under hydrothermal conditions

    SciTech Connect

    Foy, B.R.; Dell`Orco, P.C.; Wilmanns, E.; McInroy, R.; Ely, J.; Robinson, J.M.; Buelow, S.J.

    1994-10-01

    The feasibility of reducing nitrate/nitrite salts under hydrothermal conditions for the treatment of aqueous mixed wastes stored in the underground tanks at the Department of Energy site at Hanford, Washington was studied. The reduction of nitrate and nitrite salts by reaction with EDTA using a tank waste simulant was examined at temperatures between 623K and 800K and pressures between 0.6 and 1.2 kbar. Continuous flow reactors were used to determine kinetics and products of reactions. All reactions were studied under pressures high enough to produce single phase conditions. The reactions are rapid, go to completion in less than a minute, and produce simple products, such as carbonate, nitrogen, and nitrous oxide gases. The experimental results demonstrate the ability of chemical reactions under hydrothermal conditions to reduce the nitrate and nitrite salts and destroy organic compounds in the waste mixtures.

  12. Glass furnace processing of Rocky Flats Plant wastes: An evaluation

    Microsoft Academic Search

    L. M. Klingler; P. L. Abellera

    1988-01-01

    This report evaluates the use of a joule-heated glass furnace to treat four Rocky Flats Plant waste streams. These streams are extremely large, are primarily water soluble inorganic salts, and can be contaminated with hazardous organic material, toxics, andor radioactivity. It runs closely simulating actual process type runs, the glass furnace effectively treated these wastes by degrading the salts to

  13. Tank 37H Salt Removal Batch Process and Salt Dissolution Mixing Study

    SciTech Connect

    Kwon, K.C.

    2001-09-18

    Tank 30H is the receipt tank for concentrate from the 3H Evaporator. Tank 30H has had problems, such as cooling coil failure, which limit its ability to receive concentrate from the 3H Evaporator. SRS High Level Waste wishes to use Tank 37H as the receipt tank for the 3H Evaporator concentrate. Prior to using Tank 37H as the 3H Evaporator concentrate receipt tank, HLW must remove 50 inches of salt cake from the tank. They requested SRTC to evaluate various salt removal methods for Tank 37H. These methods include slurry pumps, Flygt mixers, the modified density gradient method, and molecular diffusion.

  14. Improving crop salt tolerance

    Microsoft Academic Search

    T. J. Flowers

    2004-01-01

    Salinity is an ever-present threat to crop yields, especially in countries where irrigation is an essential aid to agriculture. Although the tolerance of saline conditions by plants is variable, crop species are generally intolerant of one-third of the concentration of salts found in seawater. Attempts to improve the salt tolerance of crops through conventional breeding programmes have met with very

  15. Molten salt electrolyte separator

    DOEpatents

    Kaun, T.D.

    1996-07-09

    The patent describes a molten salt electrolyte/separator for battery and related electrochemical systems including a molten electrolyte composition and an electrically insulating solid salt dispersed therein, to provide improved performance at higher current densities and alternate designs through ease of fabrication. 5 figs.

  16. Acids and Salts (GCMP)

    NSDL National Science Digital Library

    Acids and Salts: this is a resource in the collection "General Chemistry Multimedia Problems". This problem will explore a few properties of common acids and their salts. General Chemistry Multimedia Problems ask students questions about experiments they see presented using videos and images. The questions asked apply concepts from different parts of an introductory course, encouraging students to decompartmentalize the material.

  17. Integrated Salt Studies

    NASA Astrophysics Data System (ADS)

    Urai, Janos L.; Kukla, Peter A.

    2015-04-01

    The growing importance of salt in the energy, subsurface storage, and chemical and food industries also increases the challenges with prediction of geometries, kinematics, stress and transport in salt. This requires an approach, which integrates a broader range of knowledge than is traditionally available in the different scientific and engineering disciplines. We aim to provide a starting point for a more integrated understanding of salt, by presenting an overview of the state of the art in a wide range of salt-related topics, from (i) the formation and metamorphism of evaporites, (ii) rheology and transport properties, (iii) salt tectonics and basin evolution, (iv) internal structure of evaporites, (v) fluid flow through salt, to (vi) salt engineering. With selected case studies we show how integration of these domains of knowledge can bring better predictions of (i) sediment architecture and reservoir distribution, (ii) internal structure of salt for optimized drilling and better cavern design, (iii) reliable long-term predictions of deformations and fluid flow in subsurface storage. A fully integrated workflow is based on geomechanical models, which include all laboratory and natural observations and links macro- and micro-scale studies. We present emerging concepts for (i) the initiation dynamics of halokinesis, (ii) the rheology and deformation of the evaporites by brittle and ductile processes, (iii) the coupling of processes in evaporites and the under- and overburden, and (iv) the impact of the layered evaporite rheology on the structural evolution.

  18. Monte Carlo simulations of salt solutions: exploring the validity of primitive models.

    PubMed

    Abbas, Zareen; Ahlberg, Elisabet; Nordholm, Sture

    2009-04-30

    An extensive series of Monte Carlo (MC) simulations were performed in order to explore the validity of simple primitive models of electrolyte solutions and in particular the effect of ion size asymmetry on the bulk thermodynamic properties of real salt solutions. Ionic activity and osmotic coefficients were calculated for 1:1, 2:1, and 3:1 electrolytes by using the unrestricted primitive model (UPM); i.e., ions are considered as charged hard spheres of different sizes dissolved in a dielectric continuum. Mean ionic activity and osmotic coefficients calculated by the MC simulations were fitted simultaneously to the experimental data by adjusting only the cation radius while keeping the anion radius fixed at its crystallographic value. Ionic radii were further optimized by systematically varying the cation and anion radii at a fixed sum of ionic radii. The success of this approach is found to be highly salt specific. For example, experimental data (mean ionic activity and osmotic coefficients) of salts which are usually considered as dissociated such as HCl, HBr, LiCl, LiBr, LiClO(4), and KOH were successfully fitted up to 1.9, 2.5, 1.9, 3, 2.5, and 4.5 M concentrations, respectively. In the case of partially dissociated salts such as NaCl, the successful fits were only obtained in a more restricted concentration range. Consistent sets of the best fitted cation radii were obtained for acids, alkali, and alkaline earth halides. A list of recommended ionic radii is also provided. The reliability of the optimized ionic radii was further tested in simulations of the osmotic coefficients of LiCl-NaCl-KCl salt mixtures. A very good agreement between the simulated and experimental data was obtained up to ionic strength of 4.5 M. PMID:19341250

  19. Lowering Salt in Your Diet

    MedlinePLUS

    ... this page Home For Consumers Consumer Updates Lowering Salt in Your Diet Search the Consumer Updates Section ... mail Consumer Updates RSS Feed Everyone needs some salt to function. Also known as sodium chloride, salt ...

  20. Hanford's Simulated Low Activity Waste Cast Stone Processing

    SciTech Connect

    Kim, Young

    2013-08-20

    Cast Stone is undergoing evaluation as the supplemental treatment technology for Hanford’s (Washington) high activity waste (HAW) and low activity waste (LAW). This report will only cover the LAW Cast Stone. The programs used for this simulated Cast Stone were gradient density change, compressive strength, and salt waste form phase identification. Gradient density changes show a favorable outcome by showing uniformity even though it was hypothesized differently. Compressive strength exceeded the minimum strength required by Hanford and greater compressive strength increase seen between the uses of different salt solution The salt waste form phase is still an ongoing process as this time and could not be concluded.

  1. Resedimented salt deposits

    SciTech Connect

    Slaczka, A.; Kolasa, K. (Jagiellonian Univ., Krakow (Poland))

    1988-08-01

    Carparthian foredeep's Wieliczka salt mine, unique gravity deposits were lately distinguished. They are mainly built of salt particles and blocks with a small admixture of fragments of Miocene marls and Carpathian rocks, deposited on precipitated salt. The pattern of sediment distribution is similar to a submarine fan. Gravels are dominant in the upper part and sands in lower levels, creating a series of lobes. Coarse-grained deposits are represented by disorganized, self-supported conglomerates passing into matrix-supported ones, locally with gradation, and pebbly sandstones consisting of salt grains and scattered boulder-size clasts. The latter may show in the upper part of a single bed as indistinct cross-bedding and parallel lamination. These sediments are interpreted as debris-flow and high-density turbidity current deposits. Salt sandstones (saltstones) which build a lower part of the fan often show Bouma sequences and are interpreted as turbidity-current deposits. The fan deposits are covered by a thick series of debrites (olistostromes) which consist of clay matrix with salt grains and boulders. The latter as represented by huge (up to 100,000 m{sup 3}) salt blocks, fragments of Miocene marls and Carpathian rocks. These salt debrites represent slumps and debris-flow deposits. The material for resedimented deposits was derived from the southern part of the salt basin and from the adjacent, advancing Carpathian orogen. The authors believe the distinct coarsening-upward sequence of the series is the result of progressive intensification of tectonic movements with paroxysm during the sedimentation of salt debrites (about 15 Ma).

  2. Water purification using organic salts

    DOEpatents

    Currier, Robert P.

    2004-11-23

    Water purification using organic salts. Feed water is mixed with at least one organic salt at a temperature sufficiently low to form organic salt hydrate crystals and brine. The crystals are separated from the brine, rinsed, and melted to form an aqueous solution of organic salt. Some of the water is removed from the aqueous organic salt solution. The purified water is collected, and the remaining more concentrated aqueous organic salt solution is reused.

  3. Simultaneous conditioning of "gaping" responses and taste avoidance in rats injected with LiCl and saccharin: examining the role of context and taste cues in the rodent model of anticipatory nausea.

    PubMed

    Cloutier, Caylen J; Cross-Mellor, Shelley K; Kavaliers, Martin; Ossenkopp, Klaus-Peter

    2011-09-15

    This study examined whether rats can simultaneously learn to associate lithium chloride (LiCl)-induced nausea with both contextual and intravascular taste cues. During the conditioning phase (4 days, 72h apart), 32 male Long Evans rats were injected intraperitoneally with either isotonic saline (NaCl), lithium chloride (LiCl, 127mg/kg), saline plus 2% saccharin (NaCl+Saccharin), or lithium chloride plus 2% saccharin (LiCl+Saccharin) immediately prior to a 30min exposure to a novel context. 72h following the final conditioning day, each animal was re-exposed to the context on a drug-free test day. The next day, animals received a 24h 2-bottle preference test with a choice between water and a palatable saccharin solution. Results showed that animals treated with LiCl during conditioning, with or without saccharin, displayed significantly higher levels of conditioned gaping responses, indicative of nausea, upon re-exposure to the context, relative to NaCl and NaCl+Saccharin controls. Animals administered LiCl+Saccharin during conditioning also displayed significant conditioned taste avoidance to the saccharin solution during the two bottle choice test. These results indicate that systemic administration (intraperitoneal) of a LiCl+Saccharin solution is effective in simultaneously conditioning toxin elicited nausea to both internal (taste) and external (context) cues. PMID:21782892

  4. Bedded-salt repository analysis. Final report

    SciTech Connect

    Guiffre, M.S.; Kaplan, M.F.; Ensminger, D.A.; Oston, S.G.; Nalbandian, J.Y.

    1980-03-31

    This report contains a description of an analysis of generic nuclear waste repository in bedded salt. This analysis was performed by TASC for inclusion in a major Lawrence Livermore Laboratory report to NRC; this report therefore should be viewed as providing more complete and detailed information about this analysis than was possible to include in the LLL report. The analysis is performed with the NUTRAN computer codes which are described in the report. The model to be analyzed is defined, and the results of a series of possible waste migration scenarios are presented. Several of these scenarios are used as the basis for a sensitivity analysis, and an uncertainty analysis utilizing Monte Carlo techniques is also performed. A new method for defining the consequences to users of a well drilled near the repository is also described, and results are presented based on two of the waste migration scenarios.

  5. Development of Polymeric Waste Forms for the Encapsulation of Toxic Wastes Using an Emulsion-Encapsulation Based Process

    SciTech Connect

    Evans, R.; Quach, A.; Birnie, D. P.; Saez, A. E.; Ela, W. P.; Zeliniski, B. J. J.; Xia, G.; Smith, H.

    2003-01-01

    Developed technologies in vitrification, cement, and polymeric materials manufactured using flammable organic solvents have been used to encapsulate solid wastes, including low-level radioactive materials, but are impractical for high salt-content waste streams (Maio, 1998). In this work, we investigate an emulsification process for producing an aqueous-based polymeric waste form as a preliminary step towards fabricating hybrid organic/inorganic polyceram matrices. The material developed incorporates epoxy resin and polystyrene-butadiene (PSB) latex to produce a waste form that is non-flammable, light weight, of relatively low cost, and that can be loaded to a relatively high weight content of waste materials. Sodium nitrate was used as a model for the salt waste. Small-scale samples were manufactured and analyzed using leach tests designed to measure the diffusion coefficient and leachability index for the fastest diffusing species in the waste form, the salt ions. The microstructure and composition of the samples were probed using SEM/EDS techniques. The results show that some portion of the salt migrates towards the exterior surfaces of the waste forms during the curing process. A portion of the salt in the interior of the sample is contained in polymer corpuscles or sacs. These sacs are embedded in a polymer matrix phase that contains fine, well-dispersed salt crystals. The diffusion behavior observed in sections of the waste forms indicates that samples prepared using this emulsion process meet or exceed the leachability criteria suggested for low level radioactivity waste forms.

  6. Rare independent mutations in renal salt handling genes contribute to blood pressure variation

    E-print Network

    Gleeson, Joseph G.

    's syndrome features massive renal salt wasting and hypotension, often resulting in neonatal death. Hypertension affects 1 billion people world-wide and is a major contributor to death from stroke, myocardial

  7. Trace water content of salt in Louisiana salt domes

    Microsoft Academic Search

    L. P. Knauth; M. B. Kumar

    1981-01-01

    The trace water content of salt in six Louisiana salt domes has been determined and has been found to be the lowest of any terrestrial rock type. The average water content of normal domal salt is on the order of 0.003 percent by weight, but anomalous zones within salt stocks can have more than ten times this amount. From the

  8. Results of water quality sampling near Richton, Cypress Creek and Lampton Salt Domes, Mississippi

    USGS Publications Warehouse

    Gandl, L.A.; Spiers, C.A.

    1980-01-01

    In the Mississippi salt basin in southern Mississippi, chemical quality studies of surface water and ground water have been made to determine present water-quality conditions near three salt domes being studied by the Department of Energy as potential repositories for radioactive wastes. Chloride concentrations in excess of 60 milligrams per liter in surface water and ground water in Perry County indicate that contamination could be occurring from industrial wastes, oil test wells, or dissolution of Richton or Cypress Creek domes. (USGS)

  9. Determination of particle size distribution of salt crystals in aqueous slurries. [From reprocessing of fuel elements

    Microsoft Academic Search

    1977-01-01

    A method for determining particle size distribution of water-soluble crystals in aqueous slurries is described. The salt slurries, containing sodium salts of predominantly nitrate, but also nitrite, sulfate, phosphate, aluminates, carbonate, and hydroxide, occur in radioactive, concentrated chemical waste from the reprocessing of nuclear fuel elements. The method involves separating the crystals from the aqueous phase, drying them, and then

  10. Amine salts of nitroazoles

    DOEpatents

    Kienyin Lee; Stinecipher, M.M.

    1993-10-26

    Compositions of matter, a method of providing chemical energy by burning said compositions, and methods of making said compositions are described. These compositions are amine salts of nitroazoles. 1 figure.

  11. Salt Plains Microbial Observatory

    NSDL National Science Digital Library

    Mark Buchheim

    This site is home of the Salt Plains Microbial Observatory, located in the Salt Plains National Wildlife Refuge in northern Oklahoma. This area has permitted the first extensive study of a non-marine, terrestrial, hypersaline environment. The web site offers information about the extreme environment, images and video clips of its microbial inhabitants, an image-rich summary of research activities, information about summer courses and research opportunities, a list of publications, and links to other informative resources pertaining to hypersaline environments.

  12. Crushed-salt constitutive model update

    SciTech Connect

    Callahan, G.D.; Loken, M.C.; Mellegard, K.D. [RE/SPEC Inc., Rapid City, SD (United States); Hansen, F.D. [Sandia National Labs., Albuquerque, NM (United States)

    1998-01-01

    Modifications to the constitutive model used to describe the deformation of crushed salt are presented in this report. Two mechanisms--dislocation creep and grain boundary diffusional pressure solutioning--defined previously but used separately are combined to form the basis for the constitutive model governing the deformation of crushed salt. The constitutive model is generalized to represent three-dimensional states of stress. New creep consolidation tests are combined with an existing database that includes hydrostatic consolidation and shear consolidation tests conducted on Waste Isolation Pilot Plant and southeastern New Mexico salt to determine material parameters for the constitutive model. Nonlinear least-squares model fitting to data from the shear consolidation tests and a combination of the shear and hydrostatic consolidation tests produced two sets of material parameter values for the model. The change in material parameter values from test group to test group indicates the empirical nature of the model but demonstrates improvement over earlier work with the previous models. Key improvements are the ability to capture lateral strain reversal and better resolve parameter values. To demonstrate the predictive capability of the model, each parameter value set was used to predict each of the tests in the database. Based on the fitting statistics and the ability of the model to predict the test data, the model appears to capture the creep consolidation behavior of crushed salt quite well.

  13. Effect of Chorda Tympani Nerve Transection on Salt Taste Perception in Mice

    PubMed Central

    Ishiwatari, Yutaka; Theodorides, Maria L.; Bachmanov, Alexander A.

    2011-01-01

    Effects of gustatory nerve transection on salt taste have been studied extensively in rats and hamsters but have not been well explored in the mouse. We examined the effects of chorda tympani (CT) nerve transection on NaCl taste preferences and thresholds in outbred CD-1 mice using a high-throughput phenotyping method developed in our laboratory. To measure taste thresholds, mice were conditioned by oral self-administration of LiCl or NaCl and then presented with NaCl concentration series in 2-bottle preference tests. LiCl-conditioned and control NaCl-exposed mice were given bilateral transections of the CT nerve (LiCl-CTX, NaCl-CTX) or were left intact as controls (LiCl-CNT, NaCl-CNT). After recovery from surgery, mice received a concentration series of NaCl (0–300 mM) in 48-h 2-bottle tests. CT transection increased NaCl taste thresholds in LiCl-conditioned mice and eliminated avoidance of concentrated NaCl in control NaCl-exposed mice. This demonstrates that in mice, the CT nerve is important for detection and recognition of NaCl taste and is necessary for the normal avoidance of high concentrations of NaCl. The results of this experiment also show that the method of high-throughput phenotyping of salt taste thresholds is suitable for detecting changes in the taste periphery in mouse genetic studies. PMID:21743094

  14. Resistivity measurements of halide-salt/MgO separators for thermal cells

    SciTech Connect

    Redey, L.; McParland, M. (Argonne National Lab., IL (USA)); Guidotti, R. (Sandia National Labs., Albuquerque, NM (USA))

    1990-01-01

    Resistivities of 20 compositions of halide-salt/MgO mixtures (various selections and percentages of LiF, LiCl, LiBr, KCl, KBr, CsBr, and MgO) to be used in Li-alloy/metal sulfide cells have been measured at temperatures between the melting point of a particular mixture and 500{degrees}C. The resistivities were determined with cold-pressed electrolyte-binder pellets by using a special cell and DC measuring technique. Temperature, salt composition, and MgO content were found to have a strong influence on resistivity. These factors are listed in decreasing order of the magnitude of the effect. The fabrication density (porosity) of the pellet also has some effect on resistivity. These measured resistivities provide a data base to select optimum compositions of electrolyte-binder pellets for LiSi/FeS{sub 2} thermal batteries and to calculate area-specific resistances of these components for battery modeling and optimization. 5 refs., 7 figs.

  15. Electrochemistry of LiCl-Li2O-H2O Molten Salt Systems

    SciTech Connect

    Natalie J. Gese; Batric Pesic

    2013-03-01

    Uranium can be recovered from uranium oxide (UO2) spent fuel through the combination of the oxide reduction and electrorefining processes. During oxide reduction, the spent fuel is introduced to molten LiCl-Li2O salt at 650 degrees C and the UO2 is reduced to uranium metal via two routes: (1) electrochemically, and (2) chemically by lithium metal (Li0) that is produced electrochemically. However, the hygroscopic nature of both LiCl and Li2O leads to the formation of LiOH, contributing hydroxyl anions (OH-), the reduction of which interferes with the Li0 generation required for the chemical reduction of UO2. In order for the oxide reduction process to be an effective method for the treatment of uranium oxide fuel, the role of moisture in the LiCl-Li2O system must be understood. The behavior of moisture in the LiCl-Li2O molten salt system was studied using cyclic voltammetry, chronopotentiometry and chronoamperometry, while reduction to hydrogen was confirmed with gas chromatography.

  16. HLW Salt Disposition Alternatives Preconceptual Phase II Summary Report

    SciTech Connect

    Piccolo, S.F.

    1999-07-09

    The purpose of the report is to summarize the process used to identify the Short List alternatives that will be evaluated during Phase III and to document the results of the selection process. The Phase III evaluation will result in the determination of the preferred alternative(s) to be used for final disposition of the HLW salt to a permitted waste form.

  17. Study of Salt Wash Water Toxicity on Wastewater Treatment

    Microsoft Academic Search

    Mostafa F. Hashad; Surabhi Sharma; Loring F. Nies; James E. Alleman

    2006-01-01

    This research effort focused on evaluating the toxicity of the saline waste water generated from washing of Indiana Department of Transportation (INDOT) deicing trucks and to study the feasibility of discharging it into wastewater treatment plants. Performance of activated sludge treating wastewater under varying levels of salt concentration was studied by measuring the Chemical Oxygen Demand (COD), activated sludge oxygen

  18. Stability of SG1 nitroxide towards unprotected sugar and lithium salts: a preamble to cellulose modification by nitroxide-mediated graft polymerization

    PubMed Central

    Moreira, Guillaume; Charles, Laurence; Major, Mohamed; Vacandio, Florence; Guillaneuf, Yohann

    2013-01-01

    Summary The range of applications of cellulose, a glucose-based polysaccharide, is limited by its inherently poor mechanical properties. The grafting of synthetic polymer chains by, for example, a “grafting from” process may provide the means to broaden the range of applications. The nitroxide-mediated polymerization (NMP) method is a technique of choice to control the length, the composition and the architecture of the grafted copolymers. Nevertheless, cellulose is difficult to solubilize in organic media because of inter- and intramolecular hydrogen bonds. One possibility to circumvent this limitation is to solubilize cellulose in N,N-dimethylformamide (DMF) or N,N-dimethylacetamide (DMA) with 5 to 10 wt % of lithium salts (LiCl or LiBr), and carry out grafted polymerization in this medium. The stability of nitroxides such as SG1 has not been studied under these conditions yet, even though these parameters are of crucial importance to perform the graft modification of polysaccharide by NMP. The aim of this work is to offer a model study of the stability of the SG1 nitroxide in organic media in the presence of unprotected glucose or cellobiose (used as a model of cellulose) and in the presence of lithium salts (LiBr or LiCl) in DMF or DMA. Contrary to TEMPO, SG1 proved to be stable in the presence of unprotected sugar, even with an excess of 100 molar equivalents of glucose. On the other hand, lithium salts in DMF or DMA clearly degrade SG1 nitroxide as proven by electron-spin resonance measurements. The instability of SG1 in these lithium-containing solvents may be explained by the acidification of the medium by the hydrolysis of DMA in the presence of LiCl. This, in turn, enables the disproportionation of the SG1 nitroxide into an unstable hydroxylamine and an oxoammonium ion. Once the conditions to perform an SG1-based nitroxide-mediated graft polymerization from cellobiose have been established, the next stage of this work will be the modification of cellulose and cellulose derivatives by NMP. PMID:23946859

  19. Salt Made the World Go Round: MRBLOCH Salt Archive

    NSDL National Science Digital Library

    Bloch, David.

    Don't you just love it when everything can be summed up with one simple explanantion? Created by David Bloch, this Website proves that life as we know depends upon salt. Sections of the site look at salt in relation to a wide range of areas of study, such as Physiology, Geology, Archaeology, Paleoclimatology, Religion, and Economics. For example, the Economics section provides information on the use of salt as money, the history of the control of salt by monopolies, and the influence of the salt trade on transportation. The Religion section points out the importance of salt in religious practices, such as Jewish koshering and Egyptian embalming. Also included are links to over fifty additional salt sites, an email list, and an announcement for Salt 2000, the 8th World Salt Symposium, to be held in the Hague in May 2000.

  20. Genetic engineering of the unsaturation of fatty acids in membrane lipids alters the tolerance of Synechocystis to salt stress

    PubMed Central

    Allakhverdiev, Suleyman I.; Nishiyama, Yoshitaka; Suzuki, Iwane; Tasaka, Yasushi; Murata, Norio

    1999-01-01

    The role of unsaturated fatty acids in membrane lipids in the tolerance of the photosynthetic machinery to salt stress was studied by comparing the desA?/desD? mutant of Synechocystis sp. PCC 6803, which contained monounsaturated fatty acids, with the wild-type strain, which contained a full complement of polyunsaturated fatty acids. In darkness, the loss of oxygen-evolving photosystem II activity in the presence of 0.5 M NaCl or 0.5 M LiCl was much more rapid in desA?/desD? cells than in wild-type cells. Oxygen-evolving activity that had been lost during incubation with 0.5 M NaCl in darkness returned when cells were transferred to conditions that allowed photosynthesis or respiration. Recovery was much greater in wild-type than in desA?/desD? cells, and it was prevented by lincomycin. Thus, the unsaturation of fatty acids is important in the tolerance of the photosynthetic machinery to salt stress. It appears also that the activity and synthesis of the Na+/H+ antiporter system might be suppressed under high-salt conditions and that this effect can be reversed, in part, by the unsaturation of fatty acids in membrane lipids. PMID:10318975

  1. Analysis of Multistage and Other Creep Data for Domal Salts

    SciTech Connect

    Munson, D.E.

    1998-10-01

    There have existed for some time relatively sparse creep databases for a number of domal salts. Although all of these data were analyzed at the time they were reported, to date there has not been a comprehensive, overall evaluation within the same analysis framework. Such an evaluation may prove of value. The analysis methodology is based on the Multimechanism Deformation (M-D) description of salt creep and the corresponding model parameters determined from conventional creep tests. The constitutive model of creep wss formulated through application of principles involved in micromechanical modeling. It was possible, at minimum, to obtain the steady state parameters of the creep model from the data on the domal salts. When this was done, the creep of the domal salts, as compared to the well-defined Waste Isolation Pilot Plant (WIPP) bedded clean salt, was either essentially identical to, or significantly harder (more creep resistant) than WIPP salt. Interestingly, the domal salts form two distinct groups, either sofl or hard, where the difference is roughly a factor often in creep rate between the twcl groups. As might be expected, this classification corresponds quite well to the differences in magnitude of effective creep volume losses of the Strategic Petroleum Reserve (SPR) caverns as determined by the CAVEMAN cavern pressure history analysis, depending upon the specific dome or region within the dome. Creep response shoulcl also correlate to interior cavern conditions that produce salt falls. WMle, in general, the caverns in hard sah have a noticeably greater propensity for salt falls, a smaller number of similar events are exhibited even in the caverns in soft salt.

  2. Stabilization of a mixed waste sludge for land disposal

    Microsoft Academic Search

    S. E. Powers; A. K. Zander

    1996-01-01

    A solidification and stabilization technique was developed for a chemically complex mixed waste sludge containing nitrate processing wastes, sewage sludge and electroplating wastewaters, among other wastes. The sludge is originally from a solar evaporation pond and has high concentrations of nitrate salts; cadmium, chromium, and nickel concentrations of concern; and low levels of organic constituents and alpha and beta emitters.

  3. Treatment for hydrazine-containing waste water solution

    NASA Technical Reports Server (NTRS)

    Yade, N.

    1986-01-01

    The treatment for waste solutions containing hydrazine is presented. The invention attempts oxidation and decomposition of hydrazine in waste water in a simple and effective processing. The method adds activated charcoal to waste solutions containing hydrazine while maintaining a pH value higher than 8, and adding iron salts if necessary. Then, the solution is aerated.

  4. Fundamental Properties of Salts

    SciTech Connect

    Toni Y Gutknecht; Guy L Fredrickson

    2012-11-01

    Thermal properties of molten salt systems are of interest to electrorefining operations, pertaining to both the Fuel Cycle Research & Development Program (FCR&D) and Spent Fuel Treatment Mission, currently being pursued by the Department of Energy (DOE). The phase stability of molten salts in an electrorefiner may be adversely impacted by the build-up of fission products in the electrolyte. Potential situations that need to be avoided, during electrorefining operations, include (i) fissile elements build up in the salt that might approach the criticality limits specified for the vessel, (ii) electrolyte freezing at the operating temperature of the electrorefiner due to changes in the liquidus temperature, and (iii) phase separation (non-homogenous solution). The stability (and homogeneity) of the phases can be monitored by studying the thermal characteristics of the molten salts as a function of impurity concentration. Simulated salt compositions consisting of the selected rare earth and alkaline earth chlorides, with a eutectic mixture of LiCl-KCl as the carrier electrolyte, were studied to determine the melting points (thermal characteristics) using a Differential Scanning Calorimeter (DSC). The experimental data were used to model the liquidus temperature. On the basis of the this data, it became possible to predict a spent fuel treatment processing scenario under which electrorefining could no longer be performed as a result of increasing liquidus temperatures of the electrolyte.

  5. Testing of stripping columns for the removal of benzene from aqueous radioactive salt solution

    SciTech Connect

    Georgeton, G.K.; Taylor, G.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Gaughan, T.P. [Elf Atochem North America, Inc., King of Prussia, PA (United States)] [and others

    1995-06-27

    Radioactive high level wastes (HLW) generated from production of special nuclear materials at the Savannah River Site (SRS) are held in interim storage in 51 underground, million gallon tanks. Radioactive cesium ({sup 137}Cs) is segregated by evaporation of aqueous waste solution for interim storage in a salt matrix comprised of Na and K salts or in concentrated salt solution. The saltcake will be dissolved and {sup 137}Cs will be separated from the nonradioactive salts in solution in the In-Tank Precipitation (ITP) Process. The cesium will be combined with other radioactive species and glass formers to be melted and poured into stainless steel canisters in the Defense Waste Processing Facility (DWPF). The salt solution remaining after decontamination in the ITP process will be incorporated into grout for disposal at the site`s Saltstone facility. In the ITP facility, sodium tetraphenylborate (STPB) will be added to precipitate the cesium. Potassium in the waste solution also reacts with STPB and precipitates. Due to radiolytic and chemical degradation of the tetraphenylborate (TPB) precipitate, benzene is generated. The benzene dissolves into the decontaminated salt solution (DSS) and into water (WW) used to {open_quotes}wash{close_quotes} the precipitate to lower the soluble salt content of the slurry. Safety and processing requirements for disposal of the DSS and for temporary storage of the WW dictate that the benzene concentration be reduced.

  6. Safe actinide disposition in molten salt reactors

    SciTech Connect

    Gat, U.

    1997-03-01

    Safe molten salt reactors (MSR) can readily accommodate the burning of all fissile actinides. Only minor compromises associated with plutonium are required. The MSRs can dispose safely of actinides and long lived isotopes to result in safer and simpler waste. Disposing of actinides in MSRs does increase the source term of a safety optimized MSR. It is concluded that the burning and transmutation of actinides in MSRs can be done in a safe manner. Development is needed for the processing to handle and separate the actinides. Calculations are needed to establish the neutron economy and the fuel management. 9 refs.

  7. Development of iron phosphate ceramic waste form to immobilize radioactive waste solution

    SciTech Connect

    Choi, Jongkwon; Um, Wooyong; Choung, Sungwook

    2014-05-09

    The objective of this research was to develop an iron phosphate ceramic (IPC) waste form using converter slag obtained as a by-product of the steel industry as a source of iron instead of conventional iron oxide. Both synthetic off-gas scrubber solution containing technetium-99 (or Re as a surrogate) and LiCl-KCl eutectic salt, a final waste solution from pyrochemical processing of spent nuclear fuel, were used as radioactive waste streams. The IPC waste form was characterized for compressive strength, reduction capacity, chemical durability, and contaminant leachability. Compressive strengths of the IPC waste form prepared with different types of waste solutions were 16 MPa and 19 MPa for LiCl-KCl eutectic salt and the off-gas scrubber simulant, respectively, which meet the minimum compressive strength of 3.45 MPa (500 psi) for waste forms to be accepted into the radioactive waste repository. The reduction capacity of converter slag, a main dry ingredient used to prepare the IPC waste form, was 4,136 meq/kg by the Ce(IV) method, which is much higher than those of the conventional Fe oxides used for the IPC waste form and the blast furnace slag materials. Average leachability indexes of Tc, Li, and K for the IPC waste form were higher than 6.0, and the IPC waste form demonstrated stable durability even after 63-day leaching. In addition, the Toxicity Characteristic Leach Procedure measurements of converter slag and the IPC waste form with LiCl-KCl eutectic salt met the universal treatment standard of the leachability limit for metals regulated by the Resource Conservation and Recovery Act. This study confirms the possibility of development of the IPC waste form using converter slag, showing its immobilization capability for radionuclides in both LiCl-KCl eutectic salt and off-gas scrubber solutions with significant cost savings.

  8. Tank waste chemistry: A new understanding of waste aging

    SciTech Connect

    Babad, H. [Westinghouse Hanford Co., Richland, WA (United States); Camaioni, D.M.; Lilga, M.A.; Samuels, W.D.; Strachan, D.M. [Pacific Northwest Lab., Richland, WA (United States)

    1993-02-01

    There is concern about the risk of uncontrolled exothermic reactions(s) in Hanford Site waste tanks containing NO{sub 3{sup minus}}/NO{sub 2{sup minus}} based salts and/or metal hydroxide sludges in combination with organics or ferrocyanides. However, gradual oxidation of the waste in the tanks to less reactive species appears to have reduced the risk. In addition, wastes sampled to date contain sufficiently large quantities of water so that propagation reactions are highly unlikely. This report details an investigation into the risk of an uncontrolled exothermic reaction in Hanford Site high-activity water tanks.

  9. The Nature of Salt

    NSDL National Science Digital Library

    This is a hands-on lab activity about the composition of salt. Learners will explain the general relationship between an element's Periodic Table Group Number and its tendency to gain or lose electron(s), and explain the difference between molecular compounds and ionic compounds. They will then use household materials to build a model to demonstrate sodium chloride's cubic form and describe the nature of the electrostatic attraction that holds the structure of salt together. Background information, common preconceptions, a glossary and more is included. This activity is part of the Aquarius Hands-on Laboratory Activities.

  10. ENVIROCARE OF UTAH: EXPANDING WASTE ACCEPTANCE CRITERIA TO PROVIDE LOW-LEVEL AND MIXED WASTE DISPOSAL OPTIONS

    SciTech Connect

    Rogers, B.; Loveland, K.

    2003-02-27

    Envirocare of Utah operates a low-level radioactive waste disposal facility 80 miles west of Salt Lake City in Clive, Utah. Accepted waste types includes NORM, 11e2 byproduct material, Class A low-level waste, and mixed waste. Since 1988, Envirocare has offered disposal options for environmental restoration waste for both government and commercial remediation projects. Annual waste receipts exceed 12 million cubic feet. The waste acceptance criteria (WAC) for the Envirocare facility have significantly expanded to accommodate the changing needs of restoration projects and waste generators since its inception, including acceptable physical waste forms, radiological acceptance criteria, RCRA requirements and treatment capabilities, PCB acceptance, and liquids acceptance. Additionally, there are many packaging, transportation, and waste management options for waste streams acceptable at Envirocare. Many subcontracting vehicles are also available to waste generators for both government and commercial activities.

  11. Mixed salt crystallisation fouling

    Microsoft Academic Search

    A Helalizadeh; H Müller-Steinhagen; M Jamialahmadi

    2000-01-01

    The main purpose of this investigation was to study the mechanisms of mixed salt crystallisation fouling on heat transfer surfaces during convective heat transfer and sub-cooled flow boiling. To date, no investigations on the effects of operating parameters on the deposition of mixtures of calcium sulphate and calcium carbonate, which are the most common constituents of scales formed on heat

  12. Avi's Sensational Salt Dough

    NSDL National Science Digital Library

    American Chemical Society

    2006-01-01

    In this activity on page 5 of the PDF, learners mimic the process for making bricks. Learners shape and bake creations from a dough that is made from flour, salt, and water. Use this activity to introduce learners to chemical changes. Safety notes: Follow Milli's safety notes (on page 2) and do this activity with an adult.

  13. SALT and Spelling Achievement.

    ERIC Educational Resources Information Center

    Nelson, Joan

    A study investigated the effects of suggestopedic accelerative learning and teaching (SALT) on the spelling achievement, attitudes toward school, and memory skills of fourth-grade students. Subjects were 20 male and 28 female students from two self-contained classrooms at Kennedy Elementary School in Rexburg, Idaho. The control classroom and the…

  14. Utah: Salt Lake City

    Atmospheric Science Data Center

    2014-05-15

    ... mountains surrounding Salt Lake City are renowned for the dry, powdery snow that results from the arid climate and location at the ... should be used with the red filter placed over your left eye. The canyons and peaks of the Uinta and Wasatch Mountains are ...

  15. Thermodynamic Properties of Magnesium Chloride Hydroxide Hydrate (Mg3Cl(OH)5:4H2O, Phase 5), and Its importance to Nuclear Waste Isolation in Geological Repositories in Salt Formations

    Microsoft Academic Search

    Y. Xiong; H. Deng; M. B. Nemer; S. Johnsen

    2009-01-01

    MgO (bulk, pure MgO corresponding to the mineral periclase) is the only engineered barrier certified by the Environmental Protection Agency for emplacement in the Waste Isolation Pilot Plant (WIPP) in the US, and an Mg(OH)2-based engineered barrier (bulk, pure Mg(OH)2 corresponding to brucite) is to be employed in the Asse repository in Germany. Both the WIPP and the Asse are

  16. Viscous flow during salt welding

    NASA Astrophysics Data System (ADS)

    Wagner, Bryce H.; Jackson, Martin P. A.

    2011-10-01

    Salt can be partially removed by viscous flow from between wall rocks to form a salt weld. Welds in autochthonous and allochthonous salt can form significant structures in evaporite basins, where petroleum and mineral discovery can hinge on whether salt welds act as seals or windows for migrating hydrocarbons or brines containing dissolved metals. Despite the importance of welds, little is known about salt evacuation during welding. We investigate viscous flow during welding using analytical and numerical models, based on exact solutions to the Navier-Stokes equations for idealized geometries and boundary conditions. We explore two questions: how does salt thin during evacuation, and what are the limits of viscous flow during salt welding? Hydraulic-gradient and displacement boundary conditions are shown to drive salt evacuation, which is rate-limited by drag along the boundaries of a salt layer. Where salt flow is restricted, for example beneath a broad, prograding sediment wedge, up to ~ 50 m salt can remain in an incomplete weld. Where salt flow is unrestricted, for example beneath a subsiding minibasin, viscous flow can remove all but a vanishingly thin (<<1 m) salt layer. In both cases, any remaining salt must be dissolved to leave a weld containing no remnant salt. Evacuation rate increases with increasing differential stress and decreasing flow length and dynamic viscosity of the salt. Translation of wall rock parallel to bedding may result in a fault weld but may also inhibit evacuation if the displacement counteracts flow driven by a hydraulic gradient. Evacuation of multilayered evaporites is controlled by the distribution of layer thickness and viscosity. Multilayered evaporites can be compositionally modified during evacuation.

  17. Continuous salt precipitation and separation from supercritical water. Part 2. Type 2 salts and mixtures of two salts

    Microsoft Academic Search

    Martin Schubert; Johann W. Regler; Frédéric Vogel

    2010-01-01

    Using a continuously operated laboratory plant for the catalytic hydrothermal gasification of biomass featuring a supercritical water salt separator we investigated the separation performance of three different binary type 2 salt–water mixtures and three ternary salt–water mixtures that consisted either of two type 1 salts or two type 2 salts dissolved in water. It turned out that a concentrated salt

  18. APPLICATIONS OF SALT IN ELECTROFISHING

    E-print Network

    APPLICATIONS OF SALT IN ELECTROFISHING iNlarine Biological Laboratory LIB55.A.K.Y WOODS HOLE, MASS OF SALT IN ELECTROFISHING By Robert E . Lennon and Phillip S . Parker Fishery Research Biologists Leetown. Electric fisliliiK. 2. Salt. i. Farker, Phillip Slieridaii, 192t>- .joiut author, ii. Title. ( Series : IT

  19. Petrofabric Study of Deformed Salt.

    PubMed

    Clabaugh, P S

    1962-05-01

    Petrofabric examination of salt crystals in Grand Saline salt dome reveals a preferred orientation that may bear significantly on other physical properties and on the genesis of salt domes. The symmetry of the orientation patterns indicates that translation gliding in halite may occur predominantly on cubic glide planes. PMID:17798061

  20. Significant volume reduction of tank waste by selective crystallization: 1994 Annual report

    Microsoft Academic Search

    D. L. Herting; T. R. Lunsford

    1994-01-01

    The objective of this technology task plan is to develop and demonstrate a scaleable process of reclaim sodium nitrate (NaNOâ) from Hanford waste tanks as a clean nonradioactive salt. The purpose of the so-called Clean Salt Process is to reduce the volume of low level waste glass by as much as 70%. During the reporting period of October 1, 1993,

  1. Geohydrology of the Keechi, Mount Sylvan, Oakwood, and Palestine salt domes in the northeast Texas salt-dome basin

    USGS Publications Warehouse

    Carr, Jerry E.; Halasz, Stephen J.; Peters, Henry B.

    1980-01-01

    The U.S. Department of Energy is considering the feasibility of using salt domes in the northeast Texas salt-dome basin as repositories for radioactive wastes that may require complete confinement for as much as 250,000 years. Four of fourteen known shallow piercement salt domes within the basin--Keechi, Mount Sylvan, Oakwood, and Palestine Salt Domes--have been selected as candidate domes for further study and possible selection as storage sites. Dissolution may exist at all four candidate salt domes, possibly through contact with Cretaceous or Tertiary aquifers, or through fault systems in the vicinity of the domes. Strata overlying and surrounding Palestine and Keechi Salt Domes have been arched into steeply-dipping folds that are complexly faulted. Similar conditions exist at Oakwood and Mount Sylvan Domes, except that the Tertiary strata have been only moderately disturbed. Cap rock, which is generally accepted to be an indication of salt dissolution, is present in varying amounts over all four domes. Saline water has been reported at the surface at all candidate domes except Oakwood, but only two water wells near the domes yield water containing possible anomalous concentrations of dissolved chloride--one at Keechi and one at Oakwood. Possible subsurface plumes of saline water, which are indications of instability, exist at all four domes. Additional problems concerning the hydrologic stability of Oakwood and Palestine salt domes have resulted from the disposal of oil-field saline water in the cap rock at the Oakwood dome and previous solution mining of salt at the Palestine dome. Additional investigations are needed to determine if a selected dome is hydrologically stable. Needed investigations include (1) more complete comparative analysis of the regional and local geohydrologic system; (2) a site-specific drilling and sampling program to analyze the cap rock-aquifer boundary, sediment distribution, hydraulic-parameter variations, hydraulic-head relationships, and hydrochemical patterns; and (3) mass-transport computer modeling of groundwater flow at the domes. (USGS)

  2. Concentration and precipitation of NaCl and KCl from salt cake leach solutions by electrodialysis

    SciTech Connect

    Sreenivasarao, K; Patsiogiannis, F.; Hryn, J.N.

    1997-02-09

    Electrodialysis was investigated for cost-effective recovery of salt from salt cake leach solutions. (Salt cake is a waste stream generated by the aluminum industry during treatment of aluminum drosses and scrap.) We used a pilot-scale electrodialysis stack of 5 membrane pairs, each with an effective area of 0.02 m{sup 2}. The diluate stream contained synthetic NaCl, KCl,mixtures of NaCl and KCl, and actual salt cake leach solutions (mainly NaCl and KCl, with small amounts of MgCl{sub 2}). We concentrated and precipitated NaCl and KCl salts from the concentrate steam when the initial diluate stream concentration was 21.5 to 28.8 wt% NaCl and KCl. We found that water transferring through the membranes was a significant factor in overall efficiency of salt recovery by electrodialysis.

  3. Defining a metal-based waste form for IFR pyroprocessing wastes

    SciTech Connect

    McDeavitt, S.M.; Park, J.Y.; Ackerman, J.P.

    1994-01-01

    Pyrochemical electrorefining to recover actinides from metal nuclear fuel is a key element of the Integral Fast Reactor (IFR) fuel cycle. The process separates the radioactive fission products from the long-lived actinides in a molten LiCl-KCl salt, and it generates a lower waste volume with significantly less long-term toxicity as compared to spent nuclear fuel. The process waste forms include a mineral-based waste form that will contain fission products removed from an electrolyte salt and a metal-based waste form that will contain metallic fission products and the fuel cladding and process materials. Two concepts for the metal-based waste form are being investigated: (1) encapsulating the metal constituents in a Cu-Al alloy and (2) alloying the metal constituents into a uniform stainless steel-based waste form. Results are given from our recent studies of these two concepts.

  4. The Mixed Waste Management Facility. Preliminary design review

    SciTech Connect

    NONE

    1995-12-31

    This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones.

  5. TOTAL RECYCLE SYSTEMS FOR PETROCHEMICAL WASTE BRINES CONTAINING REFRACTORY CONTAMINANTS

    EPA Science Inventory

    Petrochemical wastewaters containing relatively high concentrations of salt and refractory organics were selected to study their feasibility for total recycle. A combination of reverse osmosis and electrodialysis was operated as a hybrid system using the pretreated wastes to prod...

  6. Radioactive air emissions notice of construction use of a portable exhauster on single shell tanks (SSTs) during salt well pumping

    SciTech Connect

    GRANDO, C.J.

    1999-11-18

    This document serves as a notice of construction (NOC), pursuant to the requirements of Washington Administrative Code (WAC) 246-247-060, and as a request for approval to construct, pursuant to 40 Code of Federal Regulations (CFR) 61.07, portable exhausters for use on single-shell tanks (SSTs) during salt well pumping. Table 1-1 lists 18 SSTs covered by this NOC. This NOC also addresses other activities that are performed in support of salt well pumping but do not require the application of a portable exhauster. Specifically this NOC analyzes the following three activities that have the potential for emissions. (1) Salt well pumping (i.e., the actual transferring of waste from one tank to another) under nominal tank operating conditions. Nominal tank operating conditions include existing passive breathing rates. (2) Salt well pumping (the actual transferring of waste from one tank to another) with use of a portable exhauster. (3) Use of a water lance on the waste to facilitate salt well screen and salt well jet pump installation into the waste. This activity is to be performed under nominal (existing passive breathing rates) tank operating conditions. The use of portable exhausters represents a cost savings because one portable exhauster can be moved back and forth between SSTs as schedules for salt well pumping dictate. A portable exhauster also could be used to simultaneously exhaust more than one SST during salt well pumping.

  7. Influence of initial conditions and hydrogeological setting on variable density flow in an aquifer above a salt dome

    Microsoft Academic Search

    PETER VOGEL; KLAUS SCHELKES

    The Gorleben salt dome, in the northeastern part of Lower Saxony in Germany, is under investigation as a candidate site for the final disposal of radioactive waste. The diapir is crossed by an Elsterian subglacial erosion channel, which forms the lowermost aquifer and is partly in contact with the cap rock or the salt itself. Saturated brines . occur in

  8. TRU waste acceptance criteria for the Waste Isolation Pilot Plant: Revision 3

    SciTech Connect

    Not Available

    1989-01-01

    This document is intended to delineate the criteria by which unclassified waste will be accepted for emplacement at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico and describe the bases upon which these criteria were established. These criteria are not intended to be specifications but rather limits that will allow waste generating and shipping sites to develop their own procedures and specifications for preparation of TRU waste for shipment to the WIPP. These criteria will also allow waste generating sites to plan future facilities for waste preparation that will produce TRU waste forms compatible with WIPP waste emplacement and isolation requirements. These criteria only apply to contract-handled (CH) and remote-handled (RH) transuranic (TRU) waste forms and are not intended to apply to beta-gamma wastes, spent fuel, high-level waste (HLW), low-level waste (LLW), low specific activity (LSA) waste, or forms of radioactive waste for experimental purposes. Specifications for receipt of experimental waste forms will be prepared by the responsible projects in conjunction with the staff of the WIPP project at a later date. In addition, these criteria only apply to waste emplaced in bedded rock salt. Technical bases for these criteria may differ significantly from those for other host rocks. 25 refs. 4 figs., 1 tab.

  9. Determination of Waste Groupings for Safety Analyses

    SciTech Connect

    BARKER, S.A.

    2000-04-27

    Two workshops were held in May and July 1999 to review data analysis methodologies associated with the analysis of flammable gas behavior. The workshop participants decided that missing data could he estimated by using a distribution of values that encompassed tanks with wastes that behaved in a similar fashion. It was also determined that because of the limited amount of tank data pertaining to flammable gas generation and retention, it was not justified to divide the tanks into many small waste groupings. The purpose for grouping tanks is so that limited gas retention and release data, which may be available for some tanks within a group, can be applied to other tanks containing the same waste form. This is necessary when estimating waste properties for tanks with missing or incomplete information. Following the workshop, a preliminary tank grouping was prepared based on content of solids, liquids, sludge, saltcake, or salt slurry The saltcake and salt slurry were then grouped together and referred to as saltcake/salt slurry. Initial tank classifications were based on waste forms from the Rest Basis Inventory, the Hanford Defined Waste (HDW) (''Agnew'') Model, or the Waste Tank Summary (''Hanlon'') Report The results of this grouping arc presented in ''Flamable Gas Safety Analysis Data Review'', SNL-000 198 (Barker, et al., 1999). At the time of the release of SNL-000198, tank waste inventories were not consistent between published sources, such as the ''Best Basis Inventory'' and the ''Waste Tank Summary Report for Month Ending August 31, 1999'' (Hanlon l999). This calculation note documents the process and basis used when revising the waste groupings following the release of SNL-000198. The waste layer volume information is compared between the various databases, including information obtained from process measurements. Differences are then resolved based on tank characterization information and waste behavior.

  10. Salt deposits in Los Medanos area, Eddy and Lea counties, New Mexico

    USGS Publications Warehouse

    Jones, C.L.; with sections on Ground water hydrology, Cooley, Maurice E.; and Surficial Geology, Bachman, George Odell

    1973-01-01

    The salt deposits of Los Medanos area, in Eddy and Lea Counties, southeastern New Mexico, are being considered for possible use as a receptacle for radioactive wastes in a pilot-plant repository. The salt deposits of the area. are in three evaporite formations: the Castile, Salado, and Rustler Formations, in ascending order. The three formations are dominantly anhydrite and rock salt, but some gypsum, potassium ores, carbonate rock, and fine-grained clastic rocks are present. They have combined thicknesses of slightly more than 4,000 feet, of which roughly one-half belongs to the Salado. Both the Castile and the Rustler are-richer in anhydrite-and poorer in rock salt-than the Salado, and they provide this salt-rich formation with considerable Protection from any fluids which might be present in underlying or overlying rocks. The Salado Formation contains many thick seams of rock salt at moderate depths below the surface. The rock salt has a substantial cover of well-consolidated rocks, and it is very little deformed structurally. Certain geological details essential for Waste-storage purposes are unknown or poorly known, and additional study involving drilling is required to identify seams of rock salt suitable for storage purposes and to establish critical details of their chemistry, stratigraphy, and structure.

  11. Computer simulations of highly-concentrated aqueous solutions of ionic salts: modeling of the pre-crystallization phases

    NASA Astrophysics Data System (ADS)

    Zapalowski, Michal; Bartczak, Witold M.

    1997-07-01

    The computer simulation method has been applied to study the structure of aqueous solutions of simple ionic salts in the region of very high concentrations. Most of the calculations were performed using different versions of the molecular dynamics method for sodium chloride, lithium chloride and sodium hydroxide solutions. The concentrations ranged from 0.5 M to saturated solutions, in some cases as much as 20 M. The structures of hydration shells of the ions were analyzed using such tools as radial distribution functions, Voronoi tessellations, O'Keeffe coordination numbers, etc. Particularly careful analysis was applied to the topological properties of the ionic structures in solution. Ruff's theory of ionic quasi-lattices in concentrated solutions was investigated for LiCl, NaCl, NaOH and MgCl2 solutions. The distributions of the number of faces of the Voronoi polyhedra were calculated for the ionic substructures in the configurations produced by the molecular dynamics simulation. The increase of the salt concentration causes evolution of these distributions towards appearance of predominant geometries of the Voronoi polyhedra, what is reflected by the appearance of the peaks at certain numbers of faces of the polyhedra. This provides a proof for existence of the ordered structures of ions in the solution.

  12. A chimeric vacuolar Na(+)/H(+) antiporter gene evolved by DNA family shuffling confers increased salt tolerance in yeast.

    PubMed

    Wu, Guangxia; Wang, Gang; Ji, Jing; Li, Yong; Gao, Hailing; Wu, Jiang; Guan, Wenzhu

    2015-06-10

    The vacuolar Na(+)/H(+) antiporter plays an important role in maintaining ionic homeostasis and the osmotic balance of the cell with the environment by sequestering excessive cytoplasmic Na(+) into the vacuole. However, the relatively low Na(+)/H(+) exchange efficiency of the identified Na(+)/H(+) antiporter could limit its application in the molecular breeding of salt tolerant crops. In this study, DNA family shuffling was used to create chimeric Na(+)/H(+) antiporters with improved transport activity. Two homologous Na(+)/H(+) antiporters from halophytes Salicornia europaea (SeNHX1) and Suaeda salsa (SsNHX1) were shuffled to generate a diverse gene library. Using a high-throughput screening system of yeast complementation, a novel chimeric protein SseNHX1 carrying 12 crossover positions and 2 point mutations at amino acid level was selected. Expression of SseNHX1 in yeast mutant exhibited approximately 46% and 22% higher salt tolerance ability in yeast growth test than that of SsNHX1and SeNHX1, respectively. Measurements of the ion contents demonstrated that SseNHX1 protein in yeast cells accumulated more Na(+) and slightly more K(+) than the parental proteins did. Furthermore, this chimera also conferred increased tolerance to LiCl and a similar tolerance to hygromycin B compared with the parental proteins in yeast. PMID:25784157

  13. Tests of prototype salt stripper system for IFR fuel cycle

    SciTech Connect

    Carls, E.L.; Blaskovitz, R.J.; Johnson, T.R. [Argonne National Lab., IL (United States); Ogata, T. [Central Research Inst. of Electric Power Industry, Tokyo (Japan)

    1993-09-01

    One of the waste treatment steps for the on-site reprocessing of spent fuel from the Integral Fast Reactor fuel cycles is stripping of the electrolyte salt used in the electrorefining process. This involves the chemical reduction of the actinides and rare earth chlorides forming metals which then dissolve in a cadmium pool. To develop the equipment for this step, a prototype salt stripper system has been installed in an engineering scale argon-filled glovebox. Pumping trails were successful in transferring 90 kg of LiCl-KCl salt containing uranium and rare earth metal chlorides at 500{degree}C from an electrorefiner to the stripper vessel at a pumping rate of about 5 L/min. The freeze seal solder connectors which were used to join sections of the pump and transfer line performed well. Stripping tests have commenced employing an inverted cup charging device to introduce a Cd-15 wt % Li alloy reductant to the stripper vessel.

  14. Dynamics of salt playa polygons

    NASA Astrophysics Data System (ADS)

    Goehring, L.; Fourrière, A.

    2014-12-01

    In natural salt playa or in evaporation pools for the salt extraction industry, one can sometimes see surprising regular structures formed by ridges of salt. These ridges connect together to form a self-organized network of polygons one to two meters in diameter, which we call salt polygons. Here we propose a mechanism based on porous media convection of salty water in soil to explain the formation and the scaling of the salt polygons. Surface evaporation causes a steady upward flow of salty water, which can cause precipitation near the surface. A vertical salt gradient then builds up in the porous soil, with heavy salt-saturated water lying over the less salty source water. This can drive convection when a threshold is reached, given by a critical Rayleigh number of about 7. We suggest that the salt polygons are the surface expression of the porous medium convection, with salt crystallizing along the positions of the convective downwellings. To study this instability directly, we developed a 2D analogue experiment using a Hele-Shaw cell filled with a porous medium saturated with a salt solution and heated from above. We perform a linear stability analysis of this system, and find that it is unstable to convection, with a most unstable wavelength that is set by a balance between salt diffusion and water evaporation. The Rayleigh number in our experiment is controlled by the particle size of our model soil, and the evaporation rate. We obtain results that scale with the observation of natural salt polygons. Using dye, we observe the convective movement of salty water and find downwelling convective plumes underneath the spots where surface salt ridges form, as shown in the attached figure.

  15. Monitoring system specifications: retrieval of surf from a salt repository

    SciTech Connect

    Not Available

    1980-01-01

    The task of developing specifications for a reference monitoring system determined by repository environmental conditions, retrieval operations, and federal regulatory criteria is discussed. The monitoring system specified in this report is capable of measuring (1) package position and orientation, (2) vault deformation, (3) brine accumulation, (4) spent fuel dissolution, (5) temperature, (6) nuclear radiation, and (7) package condition with sufficient accuracy to provide data input to a general risk assessment model. In order to define a monitoring system which can provide probabilistic data on radiological risk to operating personnel and the general public for a salt mine repository, the following information is required: (1) a complete design of the salt SURF repository including inventory, density and waste package design details; (2) probalistic failure rate data on containment integrity of the SURF waste package; (3) probabilistic failure rate data on the monitoring system components (i.e., monitoring procedure, instrumentation, data acquisition, data processing and data interpretation).

  16. Polymer solidification of mixed wastes at the Rocky Flats Plant

    SciTech Connect

    Faucette, A.M.; Logsdon, B.W.; Lucerna, J.J.; Yudnich, R.J.

    1994-02-01

    The Rocky Flats Plant is pursuing polymer solidification as a viable treatment option for several mixed waste streams that are subject to land disposal restrictions within the Resource Conservation and Recovery Act provisions. Tests completed to date using both surrogate and actual wastes indicate that polyethylene microencapsulation is a viable treatment option for several mixed wastes at the Rocky Flats Plant, including nitrate salts, sludges, and secondary wastes such as ash. Treatability studies conducted on actual salt waste demonstrated that the process is capable of producing waste forms that comply with all applicable regulatory criteria, including the Toxicity Characteristic Leaching Procedure. Tests have also been conducted to evaluate the feasibility of macroencapsulating certain debris wastes in polymers. Several methods and plastics have been tested for macroencapsulation, including post-consumer recycle and regrind polyethylene.

  17. Hazardous Waste

    MedlinePLUS

    ... you throw these substances away, they become hazardous waste. Some hazardous wastes come from products in our homes. Our garbage can include such hazardous wastes as old batteries, bug spray cans and paint ...

  18. Recent advances in the molten salt destruction of energetic materials

    Microsoft Academic Search

    Pruneda

    1996-01-01

    We have demonstrated the use of the Molten Salt Destruction (MSD) Process for destroying explosives, liquid gun propellant, and explosives-contaminated materials on a 1.5 kg of explosive\\/hr bench- scale unit (1, 2, 3, 4, 5). In our recently constructed 5 kg\\/hr pilot- scale unit we have also demonstrated the destruction of a liquid gun propellant and simulated wastes containing HMX

  19. Water, Vapor, and Salt Dynamics in a Hot Repository

    SciTech Connect

    Bahrami, Davood; Danko, George [Department of Mining Engineering, University of Nevada, Reno, 1664 N. Virginia St., Reno, NV, 89557 (United States); Walton, John [Department of Civil Engineering, University of Texas at El Paso, 500 W. University, El Paso, TX, 79968 (United States)

    2007-07-01

    The purpose of this paper is to report the results of a new model study examining the high temperature nuclear waste disposal concept at Yucca Mountain using MULTIFLUX, an integrated in-drift- and mountain-scale thermal-hydrologic model. The results show that a large amount of vapor flow into the drift is expected during the period of above-boiling temperatures. This phenomenon makes the emplacement drift a water/moisture attractor during the above-boiling temperature operation. The evaporation of the percolation water into the drift gives rise to salt accumulation in the rock wall, especially in the crown of the drift for about 1500 years in the example. The deposited salts over the drift footprint, almost entirely present in the fractures, may enter the drift either by rock fall or by water drippage. During the high temperature operation mode, the barometric pressure variation creates fluctuating relative humidity in the emplacement drift with a time period of approximately 10 days. Potentially wet and dry conditions and condensation on salt-laden drift wall sections may adversely affect the storage environment. Salt accumulations during the above-boiling temperature operation must be sufficiently addressed to fully understand the waste package environment during the thermal period. Until the questions are resolved, a below-boiling repository design is favored where the Alloy-22 will be less susceptible to localized corrosion. (authors)

  20. DEVELOPMENT OF AN INSOLUBLE SALT SIMULANT TO SUPPORT ENHANCED CHEMICAL CLEANING TESTS

    SciTech Connect

    Eibling, R

    2008-05-23

    The closure process for high level waste tanks at the Savannah River Site will require dissolution of the crystallized salts that are currently stored in many of the tanks. The insoluble residue from salt dissolution is planned to be removed by an Enhanced Chemical Cleaning (ECC) process. Development of a chemical cleaning process requires an insoluble salt simulant to support evaluation tests of different cleaning methods. The Process Science and Engineering section of SRNL has been asked to develop an insoluble salt simulant for use in testing potential ECC processes (HLE-TTR-2007-017). An insoluble salt simulant has been developed based upon the residues from salt dissolution of saltcake core samples from Tank 28F. The simulant was developed for use in testing SRS waste tank chemical cleaning methods. Based on the results of the simulant development process, the following observations were developed: (1) A composition based on the presence of 10.35 grams oxalate and 4.68 grams carbonate per 100 grams solids produces a sufficiently insoluble solids simulant. (2) Aluminum observed in the solids remaining from actual waste salt dissolution tests is probably precipitated from sodium aluminate due to the low hydroxide content of the saltcake. (3) In-situ generation of aluminum hydroxide (by use of aluminate as the Al source) appears to trap additional salts in the simulant in a manner similar to that expected for actual waste samples. (4) Alternative compositions are possible with higher oxalate levels and lower carbonate levels. (5) The maximum oxalate level is limited by the required Na content of the insoluble solids. (6) Periodic mixing may help to limit crystal growth in this type of salt simulant. (7) Long term storage of an insoluble salt simulant is likely to produce a material that can not be easily removed from the storage container. Production of a relatively fresh simulant is best if pumping the simulant is necessary for testing purposes. The insoluble salt simulant described in this report represents the initial attempt to represent the material which may be encountered during final waste removal and tank cleaning. The final selected simulant was produced by heating and evaporation of a salt slurry sample to remove excess water and promote formation and precipitation of solids with solubility characteristics which are consistent with actual tank insoluble salt samples. The exact anion composition of the final product solids is not explicitly known since the chemical components in the final product are distributed between the solid and liquid phases. By combining the liquid phase analyses and total solids analysis with mass balance requirements a calculated composition of assumed simple compounds was obtained and is shown in Table 0-1. Additional improvements to and further characterization of the insoluble salt simulant are possible. During the development of these simulants it was recognized that: (1) Additional waste characterization on the residues from salt dissolution tests with actual waste samples to determine the amount of species such as carbonate, oxalate and aluminosilicate would allow fewer assumptions to be made in constructing an insoluble salt simulant. (2) The tank history will impact the amount and type of insoluble solids that exist in the salt dissolution solids. Varying the method of simulant production (elevated temperature processing time, degree of evaporation, amount of mixing (shear) during preparation, etc.) should be tested.

  1. Electrolyte salts for nonaqueous electrolytes

    DOEpatents

    Amine, Khalil; Zhang, Zhengcheng; Chen, Zonghai

    2012-10-09

    Metal complex salts may be used in lithium ion batteries. Such metal complex salts not only perform as an electrolyte salt in a lithium ion batteries with high solubility and conductivity, but also can act as redox shuttles that provide overcharge protection of individual cells in a battery pack and/or as electrolyte additives to provide other mechanisms to provide overcharge protection to lithium ion batteries. The metal complex salts have at least one aromatic ring. The aromatic moiety may be reversibly oxidized/reduced at a potential slightly higher than the working potential of the positive electrode in the lithium ion battery. The metal complex salts may also be known as overcharge protection salts.

  2. Thermolysis of carboxylic acid salts

    SciTech Connect

    Khlestkin, R.N.; Khlestkina, V.L.; Usanov, N.G.; Gareev, V.M.

    1982-07-01

    The dependence of the thermal stability of carboxylic acid salts on the nature of the anion and cation of the salt was studied. It was found that the capacity for thermal decomposition by salts of aliphatic, naphthenic, aromatic and heterocyclic carboxylic acids (with the exception of alkali salts) varies in inverse proportion to the values of the pK/sub a/ of the acids and to the values of the standard heats of formation of oxides (of the metal which forms the salt) relative to a monovalent bond with oxygen. An empirical equation which permits the thermal stability of many carboxylic acid salts to be predicted is given. Recommendations are developed for evaluating the relative activity of oxide and carbonate catalysts in reactions of vapor-phase conversion of aliphatic carboxylic acids to ketones and their operating temperatures.

  3. Primary aldosteronism and salt.

    PubMed

    Funder, John W

    2015-03-01

    For many years, primary aldosteronism was thought (and taught) to be a relatively rare (< 1 %) and benign form of high blood pressure: now we know that neither is the case. Currently, the prevalence is considered to be 5-10 % of hypertensives, on the basis of more or less stringent cutoffs for the aldosterone/renin ratio and plasma aldosterone concentration: increasingly, evidence is mounting that the true prevalence of (relatively) autonomous aldosterone secretion may be ? 30 % of hypertensives. There is, in addition, a consensus that the risk profile for patients with primary aldosteronism is substantially higher than in age-, sex-, and blood pressure-matched essential hypertensives; the cardiovascular/renal damage in primary aldosteronism is thus not a primary effect of raised blood pressure. The nexus between salt and primary aldosteronism is clear, as equivalently raised or even higher levels of plasma aldosterone in chronic sodium deficiency are homeostatic and do not cause cardiovascular damage, thus ruling out deleterious effects of aldosterone acting alone. In primary aldosteronism the normal homeostatic feedback loops between sodium status and aldosterone levels are disturbed, so that cardiovascular/renal damage reflects inappropriate aldosterone levels for sodium status. One possible actor in such a scenario is endogenous ouabain (or similar compounds), which is elevated in the sodium-loaded state and a vasoconstrictor, and thus potentially be able both to raise blood pressure and to cause cardiovascular/renal damage. A second consideration is that of the epidemiologic data linking a chronically high salt intake to a raised blood pressure. If autonomous aldosterone secretion is in fact present in ? 30 % of hypertensives, this may be the group sensitive to the pressor effects of high salt, with the remainder much less affected. Finally, at a practical level given even the currently accepted prevalence of primary aldosteronism, a radical reconsideration of first-line antihypertensive therapy is proposed. PMID:25502114

  4. Bacterial degradation of bile salts

    Microsoft Academic Search

    Bodo Philipp

    2011-01-01

    Bile salts are surface-active steroid compounds. Their main physiological function is aiding the digestion of lipophilic nutrients\\u000a in intestinal tracts of vertebrates. Many bacteria are capable of transforming and degrading bile salts in the digestive tract\\u000a and in the environment. Bacterial bile salt transformation and degradation is of high ecological relevance and also essential\\u000a for the biotechnological production of steroid

  5. Electrochromic Salts, Solutions, and Devices

    DOEpatents

    Burrell, Anthony K. (Los Alamos, NM); Warner, Benjamin P. (Los Alamos, NM); McClesky, T. Mark (Los Alamos, NM)

    2008-11-11

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  6. Salt appetite in the elderly.

    PubMed

    Hendi, Khadeja; Leshem, Micah

    2014-11-28

    The present study investigated whether salt appetite in the elderly is impaired similar to thirst because of the commonality of their physiological substrates and whether alterations in salt appetite are related to mood. Elderly (65-85 years, n 30) and middle-aged (45-58 years, n 30) men and women were compared in two test sessions. Thirst, psychophysical ratings of taste solutions, dietary Na and energy intakes, seasoning with salt and sugar, number of salty and sweet snacks consumed, preferred amounts of salt in soup and sugar in tea, and an overall measure of salt appetite and its relationship with mood, nocturia and sleep were measured. Elderly participants were found to be less thirsty and respond less to thirst. In contrast, no impairment of salt appetite was found in them, and although they had a reduced dietary Na intake, it dissipated when corrected for their reduced dietary energy intake. Diet composition and Na intake were found to be similar in middle-aged and elderly participants, despite the lesser intake in elderly participants. There were no age-related differences in the intensity of taste or hedonic profile of Na, in salting habits, in tests of salting soup, or number of salty snacks consumed. No relationship of any measure of salt appetite with mood measured by the Positive and Negative Affect Schedule, frequency of nocturia, or sleep duration was observed. The age-related impairment of the physiology of mineralofluid regulation, while compromising thirst and fluid intake, spares salt appetite, suggesting that salt appetite in humans is not regulated physiologically. Intact salt appetite in the elderly might be utilised judiciously to prevent hyponatraemia, increase thirst and improve appetite. PMID:25287294

  7. Electrochromic Salts, Solutions, and Devices

    DOEpatents

    Burrell, Anthony K. (Los Alamos, NM); Warner, Benjamin P. (Los Alamos, NM); McClesky, T. Mark (Los Alamos, NM)

    2008-10-14

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  8. Electrochromic salts, solutions, and devices

    DOEpatents

    Burrell, Anthony K. (Los Alamos, NM); Warner, Benjamin P. (Los Alamos, NM); McClesky,7,064,212 T. Mark (Los Alamos, NM)

    2006-06-20

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  9. Batteries using molten salt electrolyte

    DOEpatents

    Guidotti, Ronald A. (Albuquerque, NM)

    2003-04-08

    An electrolyte system suitable for a molten salt electrolyte battery is described where the electrolyte system is a molten nitrate compound, an organic compound containing dissolved lithium salts, or a 1-ethyl-3-methlyimidazolium salt with a melting temperature between approximately room temperature and approximately 250.degree. C. With a compatible anode and cathode, the electrolyte system is utilized in a battery as a power source suitable for oil/gas borehole applications and in heat sensors.

  10. Molten salt lithium cells

    DOEpatents

    Raistrick, Ian D. (Menlo Park, CA); Poris, Jaime (Portola Valley, CA); Huggins, Robert A. (Stanford, CA)

    1983-01-01

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400.degree.-500.degree. C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell (10) which may be operated at temperatures between about 100.degree.-170.degree. C. Cell (10) comprises an electrolyte (16), which preferably includes lithium nitrate, and a lithium or lithium alloy electrode (12).

  11. Molten salt lithium cells

    DOEpatents

    Raistrick, Ian D. (Menlo Park, CA); Poris, Jaime (Portola Valley, CA); Huggins, Robert A. (Stanford, CA)

    1982-02-09

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400.degree.-500.degree. C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell (10) which may be operated at temperatures between about 100.degree.-170.degree. C. Cell (10) comprises an electrolyte (16), which preferably includes lithium nitrate, and a lithium or lithium alloy electrode (12).

  12. Nucleated deliquescence of salt

    NASA Astrophysics Data System (ADS)

    Cantrell, Will; McCrory, Charles; Ewing, George E.

    2002-02-01

    We have studied deliquescence on the (001) face of single crystals of NaCl and find that it is a nucleated phenomenon. The phase transition occurs only after the relative humidity exceeds that found over the saturated solution by at least 5%. The contrast between our observations and previous measurements using salt powders or crystallites leads us to the conclusion that deliquescence is controlled by the differences in energy required to solvate ions from the smooth (001) face and from the defect-rich surfaces of particulate samples.

  13. Should we eat less salt?

    PubMed

    Delahaye, François

    2013-05-01

    High blood pressure is a major cardiovascular risk factor. There is overwhelming evidence that high salt consumption is a major cause of increased blood pressure. There is also a link between high salt consumption and risk of stroke, left ventricular hypertrophy, renal disease, obesity, renal stones and stomach cancer. Reducing salt consumption leads to a decrease in blood pressure and the incidence of cardiovascular disease. There are no deleterious effects associated with reducing salt consumption and it is also very cost-effective. Many organizations and state governments have issued recommendations regarding the suitable amount of salt consumption. In France, the objective is a salt consumption<8g/day in men and<6.5g/day in women and children. As 80% of consumed salt comes from manufactured products in developed countries, reduction of salt consumption requires the participation of the food industry. The other tool is consumer information and education. Salt consumption has already decreased in France in recent years, but efforts must continue. PMID:23769406

  14. New high-level waste management technology for IFR pyroprocessing wastes

    SciTech Connect

    Ackerman, J.P.; Johnson, T.R.

    1993-09-01

    The pyrochemical electrorefining process for recovery of actinides in spent fuel from the Integral Fast Reactor accumulates fission product wastes as chlorides dissolved in molten LiCI-KCI and as metals, some of which are in molten cadmium. Pyrochemical processes are being developed to recover uranium and transuranium elements for return to the reactor, and to separate and immobilize fission products in suitable waste forms. Solvent cadmium is recycled within the process. Electrolyte salt is treated in a series of salt/cadmium extraction steps; it is also returned to the process. Salt-borne fission products are concentrated on a zeolite bed that is converted to a stable, leach-resistant mineral. Rare earth fission products from the salt, noble metal fission products, and cladding hulls are dispersed in a metal matrix.

  15. Laboratory Characterization of Mechanical and Permeability Properties of Dynamically Compacted Crushed Salt

    SciTech Connect

    Hansen, F.D.; Mellegard, K.D.; Pfeifle, T.W.

    1999-02-01

    The U. S. Department of Energy plans to dispose of transuranic wastes at the Waste Isolation Pilot Plant (WIPP), a geologic repository located at a depth of about 655 meters. The WIPP underground facility is located in the bedded salt of the Salado Formation. Access to the facility is provided through vertical shafts, which will be sealed after decommissioning to limit the release of hazardous waste from the repository and to limit flow into the facility. Because limited data are available to characterize the properties of dynamically compacted crushed salt, Sandia National Laboratories authorized RE/SPEC to perform additional tests on specimens of dynamically compacted crushed salt. These included shear consolidation creep, permeability, and constant strain-rate triaxial compression tests. A limited number of samples obtained from the large compacted mass were available for use in the testing program. Thus, additional tests were performed on samples that were prepared on a smaller scale device in the RE/SPEC laboratory using a dynamic-compaction procedure based on the full-scale construction technique. The laboratory results were expected to (1) illuminate the phenomenology of crushed-salt deformation behavior and (2) add test results to a small preexisting database for purposes of estimating parameters in a crushed-salt constitutive model. The candidate constitutive model for dynamically compacted crushed salt was refined in parallel with this laboratory testing.

  16. Salt sensitivity in chickpea.

    PubMed

    Flowers, Timothy J; Gaur, Pooran M; Gowda, C L Laxmipathi; Krishnamurthy, L; Samineni, Srinivasan; Siddique, Kadambot H M; Turner, Neil C; Vadez, Vincent; Varshney, Rajeev K; Colmer, Timothy D

    2010-04-01

    The growth of chickpea (Cicer arietinum L.) is very sensitive to salinity, with the most susceptible genotypes dying in just 25 mm NaCl and resistant genotypes unlikely to survive 100 mm NaCl in hydroponics; germination is more tolerant with some genotypes tolerating 320 mm NaCl. When growing in a saline medium, Cl(-), which is secreted from glandular hairs on leaves, stems and pods, is present in higher concentrations in shoots than Na(+). Salinity reduces the amount of water extractable from soil by a chickpea crop and induces osmotic adjustment, which is greater in nodules than in leaves or roots. Chickpea rhizobia show a higher 'free-living' salt resistance than chickpea plants, and salinity can cause large reductions in nodulation, nodule size and N(2)-fixation capacity. Recent screenings of diverse germplasm suggest significant variation of seed yield under saline conditions. Both dominance and additive gene effects have been identified in the effects of salinity on chickpea and there appears to be sufficient genetic variation to enable improvement in yield under saline conditions via breeding. Selections are required across the entire life cycle with a range of rhizobial strains under salt-affected, preferably field, conditions. PMID:19843257

  17. Aluminium salt slag characterization and utilization--a review.

    PubMed

    Tsakiridis, P E

    2012-05-30

    Aluminium salt slag (also known as aluminium salt cake), which is produced by the secondary aluminium industry, is formed during aluminium scrap/dross melting and contains 15-30% aluminium oxide, 30-55% sodium chloride, 15-30% potassium chloride, 5-7% metallic aluminium and impurities (carbides, nitrides, sulphides and phosphides). Depending on the raw mix the amount of salt slag produced per tonne of secondary aluminium ranges from 200 to 500 kg. As salt slag has been classified as toxic and hazardous waste, it should be managed in compliance with the current legislation. Its landfill disposal is forbidden in most of the European countries and it should be recycled and processed in a proper way by taking the environmental impact into consideration. This paper presents a review of the aluminium salt slag chemical and mineralogical characteristics, as well as various processes for metal recovery, recycling of sodium and potassium chlorides content back to the smelting process and preparation of value added products from the final non metallic residue. PMID:22480708

  18. Evaluation of Fluorine-Trapping Agents for Use During Storage of the MSRE Fuel Salt

    SciTech Connect

    Brynestad, J.; Williams, D.F.

    1999-05-01

    A fundamental characteristic of the room temperature Molten Salt Reactor Experiment (MSRE) fuel is that the radiation from the retained fission products and actinides interacts with this fluoride salt to produce fluorine gas. The purpose of this investigation was to identify fluorine-trapping materials for the MSRE fuel salt that can meet both the requirement of interim storage in a sealed (gastight) container and the vented condition required for disposal at the Waste Isolation Pilot Plant (WIPP). Sealed containers will be needed for interim storage because of the large radon source that remains even in fuel salt stripped of its uranium content. An experimental program was undertaken to identify the most promising candidates for efficient trapping of the radiolytic fluorine generated by the MSRE fuel salt. Because of the desire to avoid pressurizing the closed storage containers, an agent that traps fluorine without the generation of gaseous products was sought.

  19. Biological production of products from waste gases

    DOEpatents

    Gaddy, James L. (Fayetteville, AR)

    2002-01-22

    A method and apparatus are designed for converting waste gases from industrial processes such as oil refining, and carbon black, coke, ammonia, and methanol production, into useful products. The method includes introducing the waste gases into a bioreactor where they are fermented to various products, such as organic acids, alcohols, hydrogen, single cell protein, and salts of organic acids by anaerobic bacteria within the bioreactor. These valuable end products are then recovered, separated and purified.

  20. ANIMAL WASTE MANAGEMENT IN THE NORTHERN GREAT PLAINS

    EPA Science Inventory

    The effect of salt level of the ration for beef steers upon salinity of the waste and the effects of the applied waste upon the soil and upon crop production was investigated. In addition, the study was conducted in both covered and open feedlot pens to study the effect of shelte...

  1. Ignition of gas during activities in Hanford waste tanks

    SciTech Connect

    Darby, J.; Unal, C.; Pasamehmetoglu, K. [Los Alamos National Laboratory, NM (United States)

    1996-12-31

    The purpose of this work was to quantity the likelihood of the ignition of flammable gas during core sampling and salt well pumping operations in single-shell waste tanks at the Hanford site. Deflagration of the gas in the tank dome can lead to dome collapse and uncontrolled release of radionuclides and toxic gases from the waste.

  2. Art with Salt and Ice

    NSDL National Science Digital Library

    KCET

    2007-01-01

    This open-ended art project allows learners to create their own colorful ice sculpture by using rock salt and food coloring on a solid block of ice. The entire activity is like a mini-science lesson because it teaches learners the physical reaction of salt on ice.

  3. Salt-gradient solar ponds

    SciTech Connect

    Neeper, D.A.

    1984-01-01

    A description of salt-gradient solar ponds is presented. Guidelines concerning the construction and maintenance of the pond are discussed. A computer model was used to study layer migration in laboratory tanks and in an outdoor pond. The status of solar ponds is briefly discussed. An equation relating heat flux and salt flux at a boundary is included. (BCS)

  4. Consolidation and permeability of salt in brine

    SciTech Connect

    Shor, A.J.; Baes, C.F. Jr.; Canonico, C.M.

    1981-07-01

    The consolidation and loss of permeability of salt crystal aggregates, important in assessing the effects of water in salt repositories, has been studied as a function of several variables. The kinetic behavior was similar to that often observed in sintering and suggested the following expression for the time dependence of the void fraction: phi(t) = phi(0) - (A/B)ln(1 + Bt/z(0)/sup 3/), where A and B are rate constants and z(0) is initial average particle size. With brine present, A and phi(0) varied linearly with stress. The initial void fraction was also dependent to some extent on the particle size distribution. The rate of consolidation was most rapid in brine and least rapid in the presence of only air as the fluid. A brine containing 5 m MgCl/sub 2/ showed an intermediate rate, presumably because of the greatly reduced solubility of NaCl. A substantial wall effect was indicated by an observed increase in the void fraction of consolidated columns with distance from the top where the stress was applied and by a dependence of consolidation rate on the column height and radius. The distance through which the stress fell by a factor of phi was estimated to change inversely as the fourth power of the column diameter. With increasing temperature (to 85/sup 0/C), consolidation proceeded somewhat more rapidly and the wall effect was reduced. The permeability of the columns dropped rapidly with consolidation, decreasing with about the sixth power of the void fraction. In general, extrapolation of the results to repository conditions confirms the self-sealing properties of bedded salt as a storage medium for radioactive waste.

  5. Salt-saturated concrete strength and permeability

    SciTech Connect

    Pfeifle, T.W. [RE/SPEC Inc., Rapid City, SD (United States); Hansen, F.D.; Knowles, M.K. [Sandia National Labs., Albuquerque, NM (United States)

    1996-11-01

    Laboratory-scale experiments applicable to the use of salt-saturated concrete as a seal material for a transuranic waste repository have been completed. Nitrogen gas permeability measurements were made using a flexible-wall permeameter, a confining pressure of 1 MPa, and gas pressure gradients ranging from 0.3 MPa to 0.75 MPa. Results show that salt-saturated concrete has very low intrinsic permeability with values ranging from 9.4 {times} 10{sup {minus}22} m{sup 2} to 9.7 {times} 10{sup {minus}17} m{sup 2}. Strength and deformation characteristics were investigated under conditions of triaxial compression with confining pressures ranging from 0 to 15 MPa using either axial strain-rate or axial stress-rate control and show that the failure strength of concrete increases with confining pressure which can be adequately described through pressure-sensitive failure criteria. Axial, radial, and volumetric strains were also measured during each test and these data were used to determine elastic properties. Experimental results are applicable in the design and analysis of scale-related functions and apply to other concrete structures subjected to compressive loadings such as dams and prestressed structural members.

  6. 7 CFR 58.721 - Salt.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ...Agriculture 3 2010-01-01 2010-01-01 false Salt. 58.721 Section 58.721 Agriculture Regulations...Quality Specifications for Raw Material § 58.721 Salt. Salt shall be free flowing, white refined sodium chloride...

  7. 7 CFR 58.721 - Salt.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ...Agriculture 3 2013-01-01 2013-01-01 false Salt. 58.721 Section 58.721 Agriculture Regulations...Quality Specifications for Raw Material § 58.721 Salt. Salt shall be free flowing, white refined sodium chloride...

  8. 40 CFR 721.6085 - Phosphonocarboxylate salts.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ...2014-07-01 false Phosphonocarboxylate salts. 721.6085 Section 721.6085 ...Substances § 721.6085 Phosphonocarboxylate salts. (a) Chemical substances and significant...identified generically as phosphonocarboxylate salts (PMNs P-93-722,...

  9. 40 CFR 721.7655 - Alkylsulfonium salt.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ...2013-07-01 false Alkylsulfonium salt. 721.7655 Section 721.7655 ...Substances § 721.7655 Alkylsulfonium salt. (a) Chemical substance and significant...identified generically as alkylsulfonium salt (PMN P-93-1166) is subject to...

  10. 7 CFR 58.721 - Salt.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ...Agriculture 3 2012-01-01 2012-01-01 false Salt. 58.721 Section 58.721 Agriculture Regulations...Quality Specifications for Raw Material § 58.721 Salt. Salt shall be free flowing, white refined sodium chloride...

  11. 40 CFR 721.6085 - Phosphonocarboxylate salts.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ...2011-07-01 false Phosphonocarboxylate salts. 721.6085 Section 721.6085 ...Substances § 721.6085 Phosphonocarboxylate salts. (a) Chemical substances and significant...identified generically as phosphonocarboxylate salts (PMNs P-93-722,...

  12. 7 CFR 58.721 - Salt.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ...Agriculture 3 2011-01-01 2011-01-01 false Salt. 58.721 Section 58.721 Agriculture Regulations...Quality Specifications for Raw Material § 58.721 Salt. Salt shall be free flowing, white refined sodium chloride...

  13. Plant salt-tolerance mechanisms

    DOE PAGESBeta

    Deinlein, Ulrich; Stephan, Aaron B.; Horie, Tomoaki; Luo, Wei; Xu, Guohua; Schroeder, Julian I.

    2014-06-01

    Crop performance is severely affected by high salt concentrations in soils. To engineer more salt-tolerant plants it is crucial to unravel the key components of the plant salt-tolerance network. Here we review our understanding of the core salt-tolerance mechanisms in plants. Recent studies have shown that stress sensing and signaling components can play important roles in regulating the plant salinity stress response. We also review key Na+ transport and detoxification pathways and the impact of epigenetic chromatin modifications on salinity tolerance. In addition, we discuss the progress that has been made towards engineering salt tolerance in crops, including marker-assisted selectionmore »and gene stacking techniques. We also identify key open questions that remain to be addressed in the future.« less

  14. Plant salt-tolerance mechanisms

    DOE PAGESBeta

    Deinlein, Ulrich; Stephan, Aaron B.; Horie, Tomoaki; Luo, Wei; Xu, Guohua; Schroeder, Julian I.

    2014-06-01

    Crop performance is severely affected by high salt concentrations in soils. To engineer more salt-tolerant plants it is crucial to unravel the key components of the plant salt-tolerance network. Here we review our understanding of the core salt-tolerance mechanisms in plants. Recent studies have shown that stress sensing and signaling components can play important roles in regulating the plant salinity stress response. We also review key Na+ transport and detoxification pathways and the impact of epigenetic chromatin modifications on salinity tolerance. In addition, we discuss the progress that has been made towards engineering salt tolerance in crops, including marker-assisted selection and gene stacking techniques. We also identify key open questions that remain to be addressed in the future.

  15. Plant salt-tolerance mechanisms

    PubMed Central

    Deinlein, Ulrich; Stephan, Aaron B.; Horie, Tomoaki; Luo, Wei; Xu, Guohua; Schroeder, Julian I.

    2014-01-01

    Crop performance is severely affected by high salt concentrations in soils. To engineer more salt-tolerant plants it is crucial to unravel the key components of the plant salt tolerance network. Here we review our understanding of the core salt-tolerance mechanisms in plants. Recent studies have shown that stress sensing and signaling components may play important roles in regulating the plant salinity stress response. We also review key Na+ transport and detoxification pathways and the impact of epigenetic chromatin modifications on salinity tolerance. In addition, we discuss the progress that has been made toward engineering salt tolerance in crops, including marker assisted selection and gene stacking techniques. We also identify key open questions that remain to be addressed in the future. PMID:24630845

  16. Salt resistant crop plants.

    PubMed

    Roy, Stuart J; Negrão, Sónia; Tester, Mark

    2014-04-01

    Soil salinity is a major constraint to agriculture. To improve salinity tolerance of crops, various traits can be incorporated, including ion exclusion, osmotic tolerance and tissue tolerance. We review the roles of a range of genes involved in salt tolerance traits. Different tissues and cells are adapted for specific and often diverse function, so it is important to express the genes in specific cell-types and to pyramid a range of traits. Modern biotechnology (marker-assisted selection or genetic engineering) needs to be increasingly used to introduce the correct combination of genes into elite crop cultivars. Importantly, the effects of introduced genes need to be evaluated in the field to determine their effect on salinity tolerance and yield improvement. PMID:24679267

  17. IMPACT OF URANIUM AND THORIUM ON HIGH TIO2 CONCENTRATION NUCLEAR WASTE GLASSES

    Microsoft Academic Search

    K. Fox; T. Edwards

    2012-01-01

    This study focused on the potential impacts of the addition of Crystalline Silicotitanate (CST) and Monosodium Titanate (MST) from the Small Column Ion Exchange (SCIX) process on the Defense Waste Processing Facility (DWPF) glass waste form and the applicability of the DWPF process control models. MST from the Salt Waste Processing Facility (SWPF) is also considered in the study. The

  18. Waste Isolation Pilot Plant (WIPP) We are applying our unique capabilities in actinide and repository

    E-print Network

    Waste Isolation Pilot Plant (WIPP) We are applying our unique capabilities in actinide and repository science to help develop and manage salt repositories. 8 08 FACT SHEET Waste Isolation Pilot Plant, was selected as the site for the Waste Isolation Pilot Plant (WIPP). WIPP received Environmental Protection

  19. Feed Acceptance for the Defense Waste Processing Facility at the Savannah River Site

    Microsoft Academic Search

    R. A. Jacobs; H. H. Elder

    1998-01-01

    The DWPF at the Department of Energy`s (DOE) Savannah River Site (SRS) began radioactive operations in December of 1995. The High Level Waste Tank Farm at SRS contains approximately thirty three million gallons of salt, supernate, and insoluble sludge wastes accumulated during more than three decades of weapons manufacture. In the DWPF, the radioactive components from this waste will ultimately

  20. A STRUCTURAL INTEGRITY EVALUATION OF THE TANK FARM WASTE TRANSFER SYSTEM

    Microsoft Academic Search

    Wiersma

    2006-01-01

    Radioactive supernate, salt, and\\/or sludge wastes (i.e., high level wastes) are confined in 49 underground storage tanks at the Savannah River Site (SRS). The waste is transported between tanks within and between the F and H area tank farms and other facilities on site via underground and a limited number of aboveground transfer lines. The Department of Energy - Savannah

  1. Pyrochemical Processing for Low-Level Waste Production in PEACER

    SciTech Connect

    Byung Gi Park; Il Soon Hwang [Nuclear Materials Laboratory, Seoul National University, 56-1 Shinlim-dong Gwanak-gu Seoul 151-742 (Korea, Republic of)

    2002-07-01

    A pyrochemical partitioning process has been conceptually designed so that the transmutation of spent LWR fuels in PEACER can produce mainly low-level waste (Class C waste) for near-surface burial. Chloride salt technology developed for IFR has been employed as the baseline. Electrorefining, reductive extraction and salt recycling steps are used to construct overall flowsheet in order to support PEACER operation. The decontamination factor for transuranic elements was estimated based on both thermodynamic models and reported experimental data. It is expected that overall decontamination factor can be as high as 10{sup 5} for transuranic elements. Final wastes from pyrochemical processing for PEACER are noble metals, alkaline earth metal, and lanthanides. The final wastes are stabilized by mixing with zeolite and glass-frits such that concentration limit for class C waste can be met. The volume of Class C waste is estimated to be small enough to make PEACER concept valuable for densely populated countries. (authors)

  2. Crystallization of sodium nitrate from radioactive waste

    SciTech Connect

    Krapukhin, V.B.; Krasavina, E.P. Pikaev, A.K. [Russian Academy of Sciences, Moscow (Russian Federation). Institute of Physical Chemistry

    1997-07-01

    From the 1940s to the 1980s, the Institute of Physical Chemistry of the Russian Academy of Sciences (IPC/RAS) conducted research and development on processes to separate acetate and nitrate salts and acetic acid from radioactive wastes by crystallization. The research objective was to decrease waste volumes and produce the separated decontaminated materials for recycle. This report presents an account of the IPC/RAS experience in this field. Details on operating conditions, waste and product compositions, decontamination factors, and process equipment are described. The research and development was generally related to the management of intermediate-level radioactive wastes. The waste solutions resulted from recovery and processing of uranium, plutonium, and other products from irradiated nuclear fuel, neutralization of nuclear process solutions after extractant recovery, regeneration of process nitric acid, equipment decontamination, and other radiochemical processes. Waste components include nitric acid, metal nitrate and acetate salts, organic impurities, and surfactants. Waste management operations generally consist of two stages: volume reduction and processing of the concentrates for storage, solidification, and disposal. Filtration, coprecipitation, coagulation, evaporation, and sorption were used to reduce waste volume. 28 figs., 40 tabs.

  3. Iodized Salt Sales in the United States

    PubMed Central

    Maalouf, Joyce; Barron, Jessica; Gunn, Janelle P.; Yuan, Keming; Perrine, Cria G.; Cogswell, Mary E.

    2015-01-01

    Iodized salt has been an important source of dietary iodine, a trace element important for regulating human growth, development, and metabolic functions. This analysis identified iodized table salt sales as a percentage of retail salt sales using Nielsen ScanTrack. We identified 1117 salt products, including 701 salt blends and 416 other salt products, 57 of which were iodized. When weighted by sales volume in ounces or per item, 53% contained iodized salt. These findings may provide a baseline for future monitoring of sales of iodized salt. PMID:25763528

  4. bHLH106 Integrates Functions of Multiple Genes through Their G-Box to Confer Salt Tolerance on Arabidopsis

    PubMed Central

    Ahmad, Aftab; Niwa, Yasuo; Goto, Shingo; Ogawa, Takeshi; Shimizu, Masanori; Suzuki, Akane; Kobayashi, Kyoko; Kobayashi, Hirokazu

    2015-01-01

    An activation-tagging methodology was applied to dedifferentiated calli of Arabidopsis to identify new genes involved in salt tolerance. This identified salt tolerant callus 8 (stc8) as a gene encoding the basic helix-loop-helix transcription factor bHLH106. bHLH106-knockout (KO) lines were more sensitive to NaCl, KCl, LiCl, ABA, and low temperatures than the wild-type. Back-transformation of the KO line rescued its phenotype, and over-expression (OX) of bHLH106 in differentiated plants exhibited tolerance to NaCl. Green fluorescent protein (GFP) fused with bHLH106 revealed that it was localized to the nucleus. Prepared bHLH106 protein was subjected to electrophoresis mobility shift assays against E-box sequences (5'-CANNTG-3'). The G-box sequence 5'-CACGTG-3' had the strongest interaction with bHLH106. bHLH106-OX lines were transcriptomically analyzed, and resultant up- and down-regulated genes selected on the criterion of presence of a G-box sequence. There were 198 genes positively regulated by bHLH106 and 36 genes negatively regulated; these genes possessed one or more G-box sequences in their promoter regions. Many of these genes are known to be involved in abiotic stress response. It is concluded that bHLH106 locates at a branching point in the abiotic stress response network by interacting directly to the G-box in genes conferring salt tolerance on plants. PMID:25978450

  5. The effects of ocean-dumped wastes on marine phytoplankto 

    E-print Network

    Schwab, Claude Raymond

    1980-01-01

    dumpsite was studied, he Gulf of Mexico waste was a biosludge originating in the chemical plant biotreater of the Shell Chemical Company Deer Park Manufacturing Complex at Deer Park, Texas. At levels less than approximately 5 X l4 this waste caused... in the chemical plant biotreater of the Shell Chemical Company Deer Park Manufacturing Complex at Deer Park, Texas. The waste consisted principally of water (90-95 wt X) which contained a large variety of organic materials, inorganic salts and metals...

  6. What You Always Wanted to Know About Salt

    NSDL National Science Digital Library

    The What You Always Wanted to Know About Salt Web site is maintained by the nonprofit organization the Salt Institute. Information on nearly every aspect of salt can be found here, including salt facts, properties of sodium chloride, salt deposits in the US, the various uses of salt, salt in the winter, the history of salt, and much more.

  7. Solubility of pllutonium in alkaline salt solutions

    SciTech Connect

    Hobbs, D.T.; Edwards, T.B.

    1993-02-26

    Plutonium solubility data from several studies have been evaluated. For each data set, a predictive model has been developed where appropriate. In addition, a statistical model and corresponding prediction intervals for plutonium solubility as a quadratic function of the hydroxide concentration have been developed. Because of the wide range of solution compositions, the solubility of plutonium can vary by as much as three orders of magnitude for any given hydroxide concentration and still remain within the prediction interval. Any nuclear safety assessments that depend on the maximum amount of plutonium dissolved in alkaline salt solutions should use concentrations at least as great as the upper prediction limits developed in this study. To increase the confidence in the prediction model, it is recommended that additional solubility tests be conducted at low hydroxide concentrations and with all of the other solution components involved. To validate the model for application to actual waste solutions, it is recommended that the plutonium solubilities in actual waste solutions be determined and compared to the values predicted by the quadratic model.

  8. U.S. Space Station Freedom waste fluid disposal system with consideration of hydrazine waste gas injection thrusters

    NASA Technical Reports Server (NTRS)

    Winters, Brian A.

    1990-01-01

    The results are reported of a study of various methods for propulsively disposing of waste gases. The options considered include hydrazine waste gas injection, resistojets, and eutectic salt phase change heat beds. An overview is given of the waste gas disposal system and how hydrozine waste gas injector thruster is implemented within it. Thruster performance for various gases are given and comparisons with currently available thruster models are made. The impact of disposal on station propellant requirements and electrical power usage are addressed. Contamination effects, reliability and maintainability assessments, safety issues, and operational scenarios of the waste gas thruster and disposal system are considered.

  9. Salt Lake City, Utah

    NASA Technical Reports Server (NTRS)

    2001-01-01

    The 2002 Winter Olympics are hosted by Salt Lake City at several venues within the city, in nearby cities, and within the adjacent Wasatch Mountains. This simulated natural color image presents a late spring view of north central Utah that includes all of the Olympic sites. The image extends from Ogden in the north, to Provo in the south; and includes the snow-capped Wasatch Mountains and the eastern part of the Great Salt Lake.

    This image was acquired on May 28, 2000 by the Advanced Spaceborne Thermal Emission and Reflection Radiometer (ASTER) on NASA's Terra satellite. With its 14 spectral bands from the visible to the thermal infrared wavelength region, and its high spatial resolution of 15 to 90 meters (about 50 to 300 feet), ASTER will image Earth for the next 6 years to map and monitor the changing surface of our planet.

    ASTER is one of five Earth-observing instruments launched December 18,1999, on NASA's Terra satellite. The instrument was built by Japan's Ministry of Economy, Trade and Industry. A joint U.S./Japan science team is responsible for validation and calibration of the instrument and the data products. Dr. Anne Kahle at NASA's Jet Propulsion Laboratory, Pasadena, California, is the U.S. Science team leader; Bjorn Eng of JPL is the project manager. ASTER is the only high resolution imaging sensor on Terra. The Terra mission is part of NASA's Earth Science Enterprise, a long-term research and technology program designed to examine Earth's land, oceans, atmosphere, ice and life as a total integrated system.

    The broad spectral coverage and high spectral resolution of ASTER will provide scientists in numerous disciplines with critical information for surface mapping, and monitoring dynamic conditions and temporal change. Example applications are: monitoring glacial advances and retreats; monitoring potentially active volcanoes; identifying crop stress; determining cloud morphology and physical properties; wetlands evaluation; thermal pollution monitoring; coral reef degradation; surface temperature mapping of soils and geology; and measuring surface heat balance.

    Size: 63.5 x 123.3 km (38.1 x 74 miles) Location: 40.7 deg. North lat., 111.9 deg. West long. Orientation: North at top Image Data: ASTER bands 1,2, and 3. Original Data Resolution: 15 m Date Acquired: May 28, 2000

  10. An economic and technical assessment of black-dross and salt-cake-recycling systems for application in the secondary aluminum industry

    Microsoft Academic Search

    D. Karvelas; E. Daniels; B. Jody; P. Bonsignore

    1991-01-01

    The secondary aluminum industry annually disposes of large amounts of dross residues and salt cake, which are by-products from the processing of scrap aluminum for reuse. These wastes contain as much as 50% salts and are presently disposed of in conventional landfills. As the costs of landfill space increase and the availability of landfill space decreases, disposal of the residues

  11. Halite dissolution derived brines in the vicinity of a Permian salt dome (N German Basin). Evidence from boron, strontium, oxygen, and hydrogen isotopes

    Microsoft Academic Search

    W. Kloppmann; Ph. Négrel; J. Casanova; H. Klinge; K. Schelkes; C. Guerrot

    2001-01-01

    The paper presents the isotopic (B, Sr, O, H) and chemical composition of solid salts, brines, groundwater, and surface water in the vicinity of a Permian salt dome in Northern Germany (diapir of Gorleben-Rambow) being considered for disposal of high level radioactive waste. The site is situated in the NW European Basin that is dominated by intensive diapirism of Permian

  12. Does salt increase thirst?

    PubMed

    Leshem, Micah

    2015-02-01

    Our diet is believed to be overly rich in sodium, and it is commonly believed that sodium intake increases drinking. Hence the concern of a possible contribution of dietary sodium to beverage intake which in turn may contribute to obesity and ill health. Here we examine whether voluntary, acute intake of a sodium load, as occurs in routine eating and snacking, increases thirst and drinking. We find that after ingesting 3.5 or 4.4?g NaCl (men) and 1.9 or 3.7?g (women) on nuts during 15 minutes, there is no increase in thirst or drinking of freely available water in the following 2?h compared with eating similar amounts of sugared or unflavored nuts. This suggests that routine ingestion of boluses of salt (~30-40% of daily intake for men,?~?20-40% for women) does not increase drinking. Methodological concerns such as about nuts as vehicle for sodium suggest further research to establish the generalizability of this unexpected result. PMID:25447020

  13. Response report from US Department of Energy Hearings on proposed salt site nominations

    SciTech Connect

    Not Available

    1983-11-01

    As required by the Nuclear Waste Policy Act (US Congress, 1983, Pub. L. 97-425, Section 112(b) (2)), the US Department of Energy (DOE) conducted a series of nine formal public hearings during April and May 1983, in Louisiana, Mississippi, Texas, and Utah and in the state capitals of Mississippi, Texas, and Utah. The hearings were held in local communities in the vicinity of sites identified as potentially suitable for further study in the program to select a site for the nation's first repository for high-level nuclear waste. The public hearings for potential sites in salt focused on the proposed nomination of the Vacherie salt dome site in Louisiana; the Richton and Cypress Creek salt dome sites in Mississippi; the Deaf Smith County and Swisher County bedded salt sites in Texas; and the Davis and Lavender Canyon bedded salt sites in Utah. The oral and written comments made during the course of the nine formal public hearings were analyzed, paraphrased into almost 1100 comments, and grouped into 62 issues or subjects within the following nine major topical areas: National Waste Terminal Storage Program Planning Process, Consultation and Cooperation, Engineering/Repository Design, Geology, Hydrology, Transportation, Public Health and Safety, Environmental Quality, and Socioeconomics. This document provides general responses to each of the 62 major issues raised during the hearings. 137 references, 7 figures, 12 tables.

  14. Response report from US Department of Energy hearings on proposed salt site nominations

    SciTech Connect

    Not Available

    1983-11-01

    As required by the Nuclear Waste Policy Act (US Congress, 1983, Pub. L. 97-425, Section 112(b)(2)), the US Department of Energy (DOE) conducted a series of nine formal public hearings during April and May 1983, in Louisiana, Mississippi, Texas, and Utah and in the state capitals of Mississippi, Texas, and Utah. The hearings were held in local communities in the vicinity of sites identified as potentially suitable for further study in the program to select a site for the nation's first repository for high-level nuclear waste. The public hearings for potential sites in salt focused on the proposed nomination of the Vacherie salt dome site in Louisiana; the Richton and Cypress Creek salt dome sites in Mississippi; the Deaf Smith County and Swisher County bedded salt sites in Texas; and the Davis and Lavender Canyon bedded salt sites in Utah. The oral and written comments made during the course of the nine formal public hearings were analyzed, paraphrased into almost 1100 comments, and grouped into 62 issues or subjects within the following nine major topical areas: National Waste Terminal Storage program Planning Process, Consultation and Cooperation, Engineering/Repository Design, Geology, Hydrology, Transportation, Public Health and Safety, Environmental Quality, and Socioeconomics. This document provides general responses to each of the 62 major issues raised during the hearings.

  15. An approach to selecting routes over which to transport excess salt from the Deaf Smith County Site

    SciTech Connect

    Not Available

    1987-09-01

    This report presents an approach to be utilized in the identification of rail and/or highway routes for the disposal of waste salt and other salt contaminated material from repository construction. Relevant issues regarding salt transport also are identified. The report identifies a sequence of activities that precede actual route selection, i.e., final selection of a salt disposal method and its location, refined estimates of salt shipment volume and schedule, followed by selection of rail or truck or a combination thereof, as the preferred transport mode. After these factors are known, the route selection process can proceed. Chapter 2.0 of this report identifies directives and requirements that potentially could affect salt transport from the Deaf Smith site. A summary of salt disposal alternatives and reference cases is contained in Chapter 3.0. Chapter 4.0 identifies and discusses current methods of salt handling and transport in the United States, and also provides some perspective as to the volume of excess salt to be transported from the Deaf Smith site relative to current industry practices. Chapter 5.0 identifies an approach to the salt transportation issue, and suggests one system for evaluating alternative highway routes for truck shipments.

  16. Energetic salts from nitroformate ion.

    PubMed

    Jadhav, Pandurang M; Radhakrishnan, S; Ghule, Vikas D; Pandey, Raj K

    2015-05-01

    Development of new energetic salts is the key factor in replacing low performance compounds in conventional formulations of high explosives as well as propellants. Ten salts based on the nitroformate anion and various nitrogen-rich cations were designed and their geometric optimizations carried out using the density functional method. With reasonable oxygen balance (from -36% to 0%), heats of formation (47-624 kJ mol(-1)) and high densities (1.81-1.89 g cm(-3)), the detonation velocity (D) and pressure (P) values of salts were calculated as 8.62-9.36 km s(-1) and 33.10-40.01 GPa, respectively. Lastly, the nitroformate salts studied in this work are of prospective interest as high performance explosives. PMID:25935336

  17. BYU Salt Lake Center Financial Aid Program

    E-print Network

    Hart, Gus

    BYU Salt Lake Center Financial Aid Program 2012 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  18. BYU Salt Lake Center Financial Aid Program

    E-print Network

    Martinez, Tony R.

    BYU Salt Lake Center Financial Aid Program 2011 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  19. BYU Salt Lake Center Financial Aid Program

    E-print Network

    Hart, Gus

    BYU Salt Lake Center Financial Aid Program 2014 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  20. BYU Salt Lake Center Financial Aid Program

    E-print Network

    Olsen Jr., Dan R.

    BYU Salt Lake Center Financial Aid Program 2013 A financial aid program of the Brigham Young University Division of Continuing Education BYU Salt Lake Center 345 West North Temple Street 3 Triad Center Salt Lake City, UT 84180 Fax: (801) 933­9456 Email: slc@byu.edu #12;BYU Salt Lake Center Financial Aid

  1. Microbial biodiversity of Great Salt Lake, Utah

    Microsoft Academic Search

    Bart C. Weimer; Giovanni Rompato; Jacob Parnell; Reed Gann; Balasubramanian Ganesan; Cristian Navas; Martin Gonzalez; Mario Clavel; Steven Albee-Scott

    2009-01-01

    Microbial biodiversity is difficult to measure in extreme environments due to the inability to culture many of the species, especially from hypersaline environments. Great Salt Lake (GSL), Utah, USA offers a unique ecology to study microbial diversity across a salt gradient. GSL has increasing salt from South to North that varies from marine salt concentrations to saturation, respectively. We used

  2. GRAVITY MEASUREMENTS ON THE PAARUP SALT DOME

    Microsoft Academic Search

    IVAR B. RAMBERG; GUSTAF LIND

    The Danish Salt Dome Province, a part of the North Sea Salt Dome Area, occurs in' the deepest part of the Danish Embayment. Permian rock salt has risen almost to the present day surface at many places. Tne southernmost known dome is the Paarup Salt Dome, which constitutes the north-western part of an elongate gravity low on the south-western flank

  3. Moving salt sills and hydrocarbon maturity

    Microsoft Academic Search

    K. Carter; I. Lerche

    1992-01-01

    Salt sills have been observed in the Gulf Coast. The contrast in the thermal conductivity between salt and detrital sediments means that a salt sill focuses heat around its leading edge, resulting in the devlopment of an anomalous temperature pattern in the vicinity of the salt sill. The consequent anomaly in thermal maturity pattern for hydrocarbons is related to four

  4. SALT: South African Large Telescope

    NSDL National Science Digital Library

    South African Astronomical Observatory

    The South African Astronomical Observatory, near Sutherland in Northern Cape, has developed an extensive internet site devoted to SALT; a $30-million project to develop the largest telescope in the southern hemisphere. Visitors with a general interest in the project can follow its progress, scheduled for completion in December of 2004. Astronomers and students will find descriptions of SALT's optical and near-infrared telescopic capabilities. All can enjoy the latest images of the skies above Sutherland gathered by the telescope.

  5. Selected hydrologic data from the vicinity of Rayburns and Vacherie salt domes, northern Louisiana salt-dome basin

    USGS Publications Warehouse

    Ryals, G.N.; Hosman, R.L.

    1980-01-01

    The U.S. Department of Energy is considering salt domes in northern Louisiana as possible sites for storage of nuclear waste. As part of this National Waste Terminal Storage (NWTS) Program, the U.S. Geological Survey is conducting a regional study of the geohydrology of the northern Louisiana salt-dome basin. Field studies involving the collection of data began in 1977. Data-collection networks were established for both ground- and surface- water sources, primarily in the vicinity of two salt domes, Rayburns and Vacherie. Groundwater data collection involved measuring water levels and sampling existing production wells and test wells drilled by the Louisiana State University for Environmental Studies. Samples were analyzed for one or more of the following categories of chemical constituents: inorganic, trace metal, and radiochemical. A network of surface-water stations was set up for measuring discharge and collecting periodic samples. Initial sampling was for analysis for inorganic chemical constituents and radioactive elements. Subsequent sampling has been for inorganic chemical constituents. (USGS)

  6. A preliminary report of the geohydrology of the Mississippi Salt-Dome Basin

    USGS Publications Warehouse

    Spiers, C.A.; Gandl, L.A.

    1980-01-01

    The U.S. Department of Energy is investigating the suitability of salt domes in the Mississippi salt-dome basin as repositories for storing radioactive wastes. The Department of Energy has requested that the U.S. Geological Survey describe the groundwater hydrology of the Mississippi salt-dome basin, giving special attention to direction and rate of movement of water. In this first part of a continuing investigation the data obtained from one year of extensive literature search and data compilation are summarized. The regional groundwater hydrology in the salt-dome basin is defined with respect to (1) groundwater flow, (2) facies changes, (3) geological structure, (4) recharge and discharge, (5) freshwater-saltwater relations, and (6) identification of localities where additional data are needed. From the 50 piercement-type salt domes in the Mississippi salt-dome basin three domes (Richton, Cypress Creek, and Lampton) were selected for more intensive study. To further evaluate the geohydrology of Richton, Lampton, and Cypress Creek domes as possible sites for storage of radioactive waste, an intensive geohydrologic study based on a comprehensive test drilling program near the domes is planned. (USGS)

  7. US/German Collaboration in Salt Repository Research, Design and Operation - 13243

    SciTech Connect

    Steininger, Walter [Karlsruhe Institute of Technology, Project Management Agency Karlsruhe - (PTKA-WTE) Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)] [Karlsruhe Institute of Technology, Project Management Agency Karlsruhe - (PTKA-WTE) Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Hansen, Frank [Sandia National Laboratories, Albuquerque NM USA 87111 (United States)] [Sandia National Laboratories, Albuquerque NM USA 87111 (United States); Biurrun, Enrique; Bollingerfehr, Wilhelm [DBE TECHNOLOGY GmbH, Eschenstr. 55, 31224 Peine (Germany)] [DBE TECHNOLOGY GmbH, Eschenstr. 55, 31224 Peine (Germany)

    2013-07-01

    Recent developments in the US and Germany [1-3] have precipitated renewed efforts in salt repository investigations and related studies. Both the German rock salt repository activities and the US waste management programs currently face challenges that may adversely affect their respective current and future state-of-the-art core capabilities in rock salt repository science and technology. The research agenda being pursued by our respective countries leverages collective efforts for the benefit of both programs. The topics addressed by the US/German salt repository collaborations align well with the findings and recommendations summarized in the January 2012 US Blue Ribbon Commission on America's Nuclear Future (BRC) report [4] and are consistent with the aspirations of the key topics of the Strategic Research Agenda of the Implementing Geological Disposal of Radioactive Waste Technology Platform (IGD-TP) [5]. Against this background, a revival of joint efforts in salt repository investigations after some years of hibernation has been undertaken to leverage collective efforts in salt repository research, design, operations, and related issues for the benefit of respective programs and to form a basis for providing an attractive, cost-effective insurance against the premature loss of virtually irreplaceable scientific expertise and institutional memory. (authors)

  8. Chemical species of plutonium in Hanford radioactive tank waste

    SciTech Connect

    Barney, G.S.

    1997-10-22

    Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other potential complexants. The sodium nitrate and sodium phosphate salts that form most of the salt cake layers have little interaction with plutonium in the wastes and contain relatively small plutonium concentrations. For these reasons the authors consider plutonium species in the sludges and supernate solutions only. The low concentrations of plutonium in waste tank supernate solutions and in the solid sludges prevent identification of chemical species of plutonium by ordinary analytical techniques. Spectrophotometric measurements are not sensitive enough to identify plutons oxidation states or complexes in these waste solutions. Identification of solid phases containing plutonium in sludge solids by x-ray diffraction or by microscopic techniques would be extremely difficult. Because of these technical problems, plutonium speciation was extrapolated from known behavior observed in laboratory studies of synthetic waste or of more chemically simple systems.

  9. Electrochemical/Pyrometallurgical Waste Stream Processing and Waste Form Fabrication

    SciTech Connect

    Steven Frank; Hwan Seo Park; Yung Zun Cho; William Ebert; Brian Riley

    2014-12-01

    This report summarizes treatment and waste form options being evaluated for waste streams resulting from the electrochemical/pyrometallurgical (pyro ) processing of used oxide nuclear fuel. The technologies that are described are South Korean (Republic of Korea – ROK) and United States of America (US) ‘centric’ in the approach to treating pyroprocessing wastes and are based on the decade long collaborations between US and ROK researchers. Some of the general and advanced technologies described in this report will be demonstrated during the Integrated Recycle Test (IRT) to be conducted as a part of the Joint Fuel Cycle Study (JFCS) collaboration between US Department of Energy (DOE) and ROK national laboratories. The JFCS means to specifically address and evaluated the technological, economic, and safe guard issues associated with the treatment of used nuclear fuel by pyroprocessing. The IRT will involve the processing of commercial, used oxide fuel to recover uranium and transuranics. The recovered transuranics will then be fabricated into metallic fuel and irradiated to transmutate, or burn the transuranic elements to shorter lived radionuclides. In addition, the various process streams will be evaluated and tested for fission product removal, electrolytic salt recycle, minimization of actinide loss to waste streams and waste form fabrication and characterization. This report specifically addresses the production and testing of those waste forms to demonstrate their compatibility with treatment options and suitability for disposal.

  10. Agricultural Wastes.

    ERIC Educational Resources Information Center

    Jewell, W. J.; Switzenbaum, M. S.

    1978-01-01

    Presents a literature review of agricultural wastes, covering publications of 1976-77. Some of the areas covered are: (1) water characteristics and impacts; (2) waste treatment; (3) reuse of agricultural wastes; and (4) nonpoint pollution sources. A list of 150 references is also presented. (HM)

  11. Application of microfiltration and ceramic membranes for treatment of salted aqueous effluents from fish processing

    Microsoft Academic Search

    Mateusz Kuca; Daniela Szaniawska

    2009-01-01

    The results of microfiltration (MF) studies using ceramic 150 kDa membrane and model solutions containing bovine serum albumin (BSA) with and without NaCl as well as salted wastewater from fish industry are reported. The aim of the research was experimental analysis of operating parameters enabling regeneration of waste brine for recycling purposes. In the first step of the research effect

  12. Leaching of lead by ammonium salts and EDTA from Salvinia minima biomass produced during aquatic phytoremediation

    Microsoft Academic Search

    Roberto Aurelio Núñez-López; Yunny Meas; Silvia Citlalli Gama; Raúl Ortega Borges; Eugenia J. Olguín

    2008-01-01

    Plant biomass harvested after heavy-metal phytoremediation must be considered as a hazardous waste that should be contained or treated appropriately before disposal or reuse. As a potential method to detoxify the biomass and to convert this material to a suitable fertilizer or mulch, leaching of lead (Pb) from Salvinia minima biomass was studied by testing water, several aqueous ammonium salts,

  13. Recent advances in the molten salt technology for the destruction of energetic materials

    Microsoft Academic Search

    R. S. Upadhye; B. E. Watkins; C. O. Pruneda

    1995-01-01

    The DOE has thousands of pounds of energetic materials which result from dismantlement operations at the Pantex Plant. The authors have demonstrated the Molten Salt Destruction (MSD) Process for the treatment of explosives and explosive-containing wastes on a 1.5 kilogram of explosive per hour scale and are currently building a 5 kilogram per hour unit. MSD converts the organic constituents

  14. Advanced pyrochemical technologies for minimizing nuclear waste

    SciTech Connect

    Bronson, M.C.; Dodson, K.E.; Riley, D.C.

    1994-06-01

    The Department of Energy (DOE) is seeking to reduce the size of the current nuclear weapons complex and consequently minimize operating costs. To meet this DOE objective, the national laboratories have been asked to develop advanced technologies that take uranium and plutonium, from retired weapons and prepare it for new weapons, long-term storage, and/or final disposition. Current pyrochemical processes generate residue salts and ceramic wastes that require aqueous processing to remove and recover the actinides. However, the aqueous treatment of these residues generates an estimated 100 liters of acidic transuranic (TRU) waste per kilogram of plutonium in the residue. Lawrence Livermore National Laboratory (LLNL) is developing pyrochemical techniques to eliminate, minimize, or more efficiently treat these residue streams. This paper will present technologies being developed at LLNL on advanced materials for actinide containment, reactors that minimize residues, and pyrochemical processes that remove actinides from waste salts.

  15. NAME: Salt Creek Estuary Restoration LOCATION: Salt Creek Watershed, Clallam County, Washington

    E-print Network

    US Army Corps of Engineers

    NAME: Salt Creek Estuary Restoration LOCATION: Salt Creek Watershed, Clallam County, Washington Federal funds $0 PROJECT DESCRIPTION: The Salt Creek Estuary Reconnection project will significantly enhance tidal and fluvial hydrology to 22.5 acres of salt marsh, which will return the salt marsh to its

  16. Adiabatic Heat of Hydration Calorimetric Measurements for Reference Saltstone Waste

    SciTech Connect

    Bollinger, James

    2006-01-12

    The production of nuclear materials for weapons, medical, and space applications from the mid-1950's through the late-1980's at the Savannah River Site (SRS) generated approximately 35 million gallons of liquid high-level radioactive waste, which is currently being processed into vitrified glass for long-term storage. Upstream of the vitrification process, the waste is separated into three components: high activity insoluble sludge, high activity insoluble salt, and very low activity soluble salts. The soluble salt represents 90% of the 35 million gallons of overall waste and is processed at the SRS Saltstone Facility, where it mixed with cement, blast furnace slag, and flyash, creating a grout-like mixture. The resulting grout is pumped into aboveground storage vaults, where it hydrates into concrete monoliths, called saltstone, thus immobilizing the low-level radioactive salt waste. As the saltstone hydrates, it generates heat that slowly diffuses out of the poured material. To ensure acceptable grout properties for disposal and immobilization of the salt waste, the grout temperature must not exceed 95 C during hydration. Adiabatic calorimetric measurements of the heat generated for a representative sample of saltstone were made to determine the time-dependent heat source term. These measurements subsequently were utilized as input to a numerical conjugate heat transfer model to determine the expected peak temperatures for the saltstone vaults.

  17. Uranium solubility studies during waste evaporation

    SciTech Connect

    Karraker, D.G.

    1993-08-16

    The liquid waste streams from chemical processing of reactor-irradiated targets and fuel are neutralized with excess NaOH and discharged to mild steel waste tanks for interim storage. To reduce the number of tanks required, and thus the cost of waste storage, the supernate is evaporated to about 70% solids, discharged while hot into clean waste tanks. As the solution cools, solids crystallize from the saturated solution and form a solid layer on the bottom of the tank. The supernate is re-evaporated to concentrate the volume further. Evaporation and crystallization are continued until, for tank 41, the tank is almost filled with crystallized salts. In the DWPF processing scheme, these salts will be redissolved in water and {sup 137}Cs precipitated with sodium tetraphenylborate in the in-tank precipitation facility. The decontaminated supernate is now mixed with cement and stored as a solid monolith; the precipitated Cs and the base-insoluble solids are encapsulated in glass for permanent storage. Questions have been raised about the nuclear safety of these operations, particularly for tank 41, where the waste source was waste from the H-Area fuel processing. One scenario for a potential nuclear accident considers that the salts in tank 41 would dissolve in water, but the enriched uranium solids would not dissolve. The uranium is hypothesized to settle to the bottom of the tank and become concentrated enough to reach a critical mass. A second scenario, promulgated by West Valley, is that uranium would precipitate in the evaporator and form a critical mass in the evaporator. To shed some light on the probable behavior of U in the waste system, the solubility of U in synthetic waste was studied. The results are reported here.

  18. Molten salt reactors for burning dismantled weapons fuel

    SciTech Connect

    Gat, U.; Engel, J.R. (Oak Ridge National Lab., TN (United States)); Dodds, H.L. (Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering)

    1992-12-01

    In this paper, the molten salt reactor (MSR) option for burning fissile fuel form dismantled weapons is examined. It is concluded that MSRs are potentially suitable for beneficial utilization of the dismantled fuel. the MSRs have the flexibility to utilize any fissile fuel in continuous operation with no special modifications, as demonstrated in the Molten Salt Reactor Experiment, while maintaining their economy. The MSRs further require a minimum of special fuel preparation and can tolerate denaturing and dilution of the fuel. Fuel shipments can be arbitrarily small, which may reduce the risk of diversion. The MSRs have inherent safety features that make them acceptable and attractive. They can burn a fuel type completely and convert it to other fuels. The MSRs also have the potential for burning the actinides and delivering the waste in an optimal form, thus contributing to the solution of one of the major remaining problems for deployment o nuclear power.

  19. Base of fresh ground water, northern Louisiana Salt-Dome Basin and vicinity, northern Louisiana and southern Arkansas

    USGS Publications Warehouse

    Ryals, G.N.

    1980-01-01

    The National Waste Terminal Storage Program is an effort by the U.S. Department of Energy to locate and develop sites for disposal or storage of commercially produced radioactive wastes. As part of this program, salt domes in the northern Louisiana salt-dome basin are being studied to determine their suitability as repositories. Part of the U.S. Geological Survey 's participation in the program has been to describe the regional geohydrology of the northern Louisiana salt-dome basin. A map based on a compilation of published data and the interpretation of electrical logs shows the altitude of the base of freshwater in aquifers in the northern Louisiana salt-dome basin. (USGS)

  20. Waste Online

    NSDL National Science Digital Library

    2004-01-01

    Sure enough, there is a good deal of "waste" online, so it's nice to learn about the Waste Online website which serves as a great repository for information about an entirely different set of waste-related matters. This British-based website has been funded by the New Opportunities Fund Digitise project. The project is overseen by Waste Watch, which is "the leading environmental charity dedicated to the reduction, reuse and recycling of household waste." First-time visitors can get started by clicking on "Wacky waste facts", which contains some basic facts about the nature of waste in the United Kingdom. In the same vicinity, visitors can dig deeper by looking into sections titled "The problem with waste", "Waste in the workplace", and "Waste at home". Moving on, the "Search our library" area allows guests to the site to look for specific items of interest related to dozens of topics, such as household recycling, office recycling, and metal recycling. Moving along, the "Information Sheets" area features almost two dozen fact sheets that can be used as guides to composting, battery recycling, and the history of waste.

  1. Salt excretion in Suaeda fruticosa.

    PubMed

    Labidi, Nehla; Ammari, Manel; Mssedi, Dorsaf; Benzerti, Maali; Snoussi, Sana; Abdelly, C

    2010-09-01

    Suaeda fruticosa is a perennial "includer" halophyte devoid of glands or trichomes with a strong ability of accumulating and sequestrating Na(+) and Cl(-). We were interested in determining whether leaf cuticle salt excretion could be involved as a further mechanism in salt response of this species after long-term treatment with high salinity levels. Seedlings had been treated for three months with seawater (SW) diluted with tap water (0, 25, 50 and 75% SW). Leaf scanning electron microscopy revealed a convex adaxial side sculpture and a higher accumulation of saline crystals at the lamina margin, with a large variability on repartition and size between treatments. No salt gland or salt bladder was found. Threedimensional wax decorations were the only structures found on leaf surface. Washing the leaf surface with water indicated that sodium and chloride predominated in excreted salts, and that potassium was poorly represented. Optimal growth of whole plant was recorded at 25% SW, correlating with maximum Na(+) and Cl(-) absolute secretion rate. The leaves of plants treated with SW retained more water than those of plants treated with tap water due to lower solute potential, especially at 25% SW. Analysis of compatible solute, such as proline, total soluble carbohydrates and glycinebetaine disclosed strong relationship between glycinebetaine and osmotic potential (r = 0.92) suggesting that tissue hydration was partly maintained by glycinebetaine accumulation. Thus in S. fruticosa , increased solute accumulation associated with water retention, and steady intracellular ion homeostasis confirms the "includer" strategy of salt tolerance previously demonstrated. However, salt excretion at leaf surface also participated in conferring to this species a capacity in high salinity tolerance. PMID:20724276

  2. A salt-free treatment of aluminum dross using plasma heating

    NASA Astrophysics Data System (ADS)

    Lavoie, S.; Dubé, G.

    1991-02-01

    The plasma dross treatment process is similar in operation and equipment to the conventional RSF process, but its elimination of salt fluxes solves the problem of corrosive gas evolution, and also results in salt-free by-products (NMP), which are recyclable and are a marketable raw material for other industries. Labor and equipment demands are about the same for both processes, but the new process dispenses with the costs of salt purchase and landfilling or recycling of salt cake. The new process is the first industrial application of plasma heating technology in the aluminum industry, and greatly reduces environmental risks, while providing a closed-loop, pollution-and waste-free dross treatment method.

  3. Molten salt extraction of transuranic and reactive fission products from used uranium oxide fuel

    DOEpatents

    Herrmann, Steven Douglas

    2014-05-27

    Used uranium oxide fuel is detoxified by extracting transuranic and reactive fission products into molten salt. By contacting declad and crushed used uranium oxide fuel with a molten halide salt containing a minor fraction of the respective uranium trihalide, transuranic and reactive fission products partition from the fuel to the molten salt phase, while uranium oxide and non-reactive, or noble metal, fission products remain in an insoluble solid phase. The salt is then separated from the fuel via draining and distillation. By this method, the bulk of the decay heat, fission poisoning capacity, and radiotoxicity are removed from the used fuel. The remaining radioactivity from the noble metal fission products in the detoxified fuel is primarily limited to soft beta emitters. The extracted transuranic and reactive fission products are amenable to existing technologies for group uranium/transuranic product recovery and fission product immobilization in engineered waste forms.

  4. Excavation design in rock salt: Laboratory experiments, material modelling and validations

    SciTech Connect

    Wawersik, W.R.; Herrmann, W.; Montgomery, S.T.; Lauson, H.S.

    1981-01-01

    The design of a radioactive waste isolation facility and of oil storage caverns in rock salt deposits in the US is supported by thermo-structural design calculations using a variety of finite element codes. Prerequisites for the successful application of such calculations are described: (1) Laboratory measurements of the time-dependent behavior of rock salt; (2) data smoothing, statistical data analyses and constitutive modelling of rock salt creep; and (3) testing of design predictions against independent measurements which were made both in the laboratory and in situ. Time-dependent rock salt properties were measured in single and multistage triaxial creep experiments up to 21 MPa confining pressure, 41 MPa principal stress difference (deviator stress) and 200/sup 0/C temperature. Measurements included continuous records of stress, shear strain and volumetric strain with a resolution of strain rates to 2 x 10/sup -11/ 1/s.

  5. Retrieval of Hanford Single Shell Nuclear Waste Tanks using Technologies Foreign and Domestic

    SciTech Connect

    EACKER, J.A.; GIBBONS, P.W.

    2003-01-01

    The Hanford Site is accelerating its SST retrieval mission. One aspect of this acceleration is the identification of new baseline retrieval technologies that can be applied to all tank conditions for salt & sludge wastes in both sound & leaking tanks.

  6. 78 FR 79615 - Vermont: Final Authorization of State Hazardous Waste Management Program Revisions

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-31

    ...Federal: Academic Laboratories Generator Standards...7-308(c); OECD Requirements; Export...Its Salts from the Lists of Hazardous Constituents...requirements for Laboratory Management Plans...additional wastes to their list of universal...

  7. IMPACT OF THE SMALL COLUMN ION EXCHANGE PROCESS ON THE DEFENSE WASTE PROCESSING FACILITY - 12112

    SciTech Connect

    Koopman, D.; Lambert, D.; Fox, K.; Stone, M.

    2011-11-07

    The Savannah River Site (SRS) is investigating the deployment of a parallel technology to the Salt Waste Processing Facility (SWPF, presently under construction) to accelerate high activity salt waste processing. The proposed technology combines large waste tank strikes of monosodium titanate (MST) to sorb strontium and actinides with two ion exchange columns packed with crystalline silicotitanate (CST) resin to sorb cesium. The new process was designated Small Column Ion Exchange (SCIX), since the ion exchange columns were sized to fit within a waste storage tank riser. Loaded resins are to be combined with high activity sludge waste and fed to the Defense Waste Processing Facility (DWPF) for incorporation into the current glass waste form. Decontaminated salt solution produced by SCIX will be fed to the SRS Saltstone Facility for on-site immobilization as a grout waste form. Determining the potential impact of SCIX resins on DWPF processing was the basis for this study. Accelerated salt waste treatment is projected to produce a significant savings in the overall life cycle cost of waste treatment at SRS.

  8. Processed waste of polyethylene production as corrosion inhibitor of steel in petroleum processing waste water

    Microsoft Academic Search

    R. Z. Fakhrutdinov; I. N. Andreev; I. A. Kozhinova; G. G. Gilmanshin; I. N. Diyarov

    1987-01-01

    In this work an electrochemical method was used to study the inhibitory properties of the tabulated materials in the corrosion of St3 steel in contact with simulated highly mineralized waste water (up to 170 g\\/liter of salts) containing oxygen and some petroleum products. The test materials are essentially anodic type inhibitors that retard metal ionization by adsorption on iron, apparently

  9. Summary of tank information relating salt well pumping to flammable gas safety issues

    SciTech Connect

    Caley, S.M.; Mahoney, L.A.; Gauglitz, P.A.

    1996-09-01

    The Hanford Site has 149 single-shell tanks (SSTs) containing radioactive wastes that are complex mixes of radioactive and chemical products. Active use of these SSTs was phased out completely by November 1980, and the first step toward final disposal of the waste in the SSTs is interim stabilization, which involves removing essentially all of the drainable liquid from the tank. Stabilization can be achieved administratively, by jet pumping to remove drainable interstitial liquid, or by supernatant pumping. To date, 116 tanks have been declared interim stabilized; 44 SSTs have had drainable liquid removed by salt well jet pumping. Of the 149 SSTs, 19 are on the Flammable Gas Watch List (FGWL) because the waste in these tanks is known or suspected, in all but one case, to generate and retain mixtures of flammable gases, including; hydrogen, nitrous oxide, and ammonia. Salt well pumping to remove the drainable interstitial liquid from these SSTs is expected to cause the release of much of the retained gas, posing a number of safety concerns. The scope of this work is to collect and summarize information, primarily tank data and observations, that relate salt well pumping to flammable gas safety issues. While the waste within FGWL SSTs is suspected offering flammable gases, the effect of salt well pumping on the waste behavior is not well understood. This study is being conducted for the Westinghouse Hanford Company as part of the Flammable Gas Project at the Pacific Northwest National Laboratory (PNNL). Understanding the historical tank behavior during and following salt well pumping will help to resolve the associated safety issues.

  10. Results from simulated contact-handled transuranic waste experiments at the Waste Isolation Pilot Plant

    SciTech Connect

    Molecke, M.A.; Sorensen, N.R.; Krumhansl, J.L.

    1993-12-31

    We conducted in situ experiments with nonradioactive, contact-handled transuranic (CH TRU) waste drums at the Waste Isolation Pilot Plant (WIPP) facility for about four years. We performed these tests in two rooms in rock salt, at WIPP, with drums surrounded by crushed salt or 70 wt % salt/30 wt % bentonite clay backfills, or partially submerged in a NaCl brine pool. Air and brine temperatures were maintained at {approximately}40C. These full-scale (210-L drum) experiments provided in situ data on: backfill material moisture-sorption and physical properties in the presence of brine; waste container corrosion adequacy; and, migration of chemical tracers (nonradioactive actinide and fission product simulants) in the near-field vicinity, all as a function of time. Individual drums, backfill, and brine samples were removed periodically for laboratory evaluations. Waste container testing in the presence of brine and brine-moistened backfill materials served as a severe overtest of long-term conditions that could be anticipated in an actual salt waste repository. We also obtained relevant operational-test emplacement and retrieval experience. All test results are intended to support both the acceptance of actual TRU wastes at the WIPP and performance assessment data needs. We provide an overview and technical data summary focusing on the WIPP CH TRU envirorunental overtests involving 174 waste drums in the presence of backfill materials and the brine pool, with posttest laboratory materials analyses of backfill sorbed-moisture content, CH TRU drum corrosion, tracer migration, and associated test observations.

  11. Biochemical changes associated with fast fermentation of squid processing by-products for low salt fish sauce

    Microsoft Academic Search

    Wei Xu; Gang Yu; Changhu Xue; Yong Xue; Yan Ren

    2008-01-01

    In order to enhance the economical values of squid processing by-products and reduce the environmental problems caused by the wastes from squid processing, the possibility of utilizing squid processing by-products for low salt fish sauce production was investigated. Low salt fish sauce was prepared experimentally from squid processing by-products, according to three different manufacturing techniques (A, B and C) with

  12. Sedimentation dynamics about salt features

    SciTech Connect

    Lowrie, A.; Blake, D.W.

    1985-02-01

    Detailed side-scan sonar and gridded bathymetric surveys on continental margins reveal the existence of numerous submarine canyons. Recently published compilations of current velocities in submarine canyons indicate that alternating and undirectionaly flows often exceed 20-30 cm/sec with peak velocities ranging from 70 to 100 cm/sec. Current meters attached to the ocean floor have been lost at current velocities of 190 cm/sec. Such velocities are ample to transport sand-size sediments. The results of DSDP Leg 96 show the existence of massive sands and gravels on the Louisiana slope, deposited during the last glacial advance. Thus, present physical oceanographic data may be an analog to conditions during glacially induced lowered sea levels. Salt ridges and domes underlie much of the Louisiana slope, determining morphology. Submarine canyons lace the slope. Given a prograding shelf, the net sediment transport routes will be down the submarine canyons. Sediment deposition patterns around the salt ridges and domes include parallel-bedded foredrifts on the upslope side, lee drifts on the downslope side, and moats along the lateral flanks of the salt features. Major differences exist between the sedimentation patterns around a ridge and a dome. The size and shape of the flow pattern will determine whether there can be a flow over the salt feature with a resulting turbulent wave that may influence sedimentation. Sedimentation patterns about salt features on the present slope should be applicable to similar paleoenvironments.

  13. Task Technical and Quality Assurance Plan for Determining Uranium and Plutonium Solubility in Actual Tank Waste Supernates

    Microsoft Academic Search

    William D

    2005-01-01

    Savannah River Site tank waste supernates contain small quantities of dissolved uranium and plutonium. Due to the large volume of supernates, significant quantities of dissolved uranium and plutonium are managed as part of waste transfers, evaporation and pretreatment at the Savannah River Site in tank farm operations, the Actinide Removal Project (ARP), and the Salt Waste Processing Facility (SWPF). Previous

  14. COMPLEX EVOLUTION OF BILE SALTS IN BIRDS.

    PubMed

    Hagey, Lee R; Vidal, Nicolas; Hofmann, Alan F; Krasowski, Matthew D

    2010-10-01

    Bile salts are the major end-metabolites of cholesterol and are important in lipid digestion and shaping of the gut microflora. There have been limited studies of bile-salt variation in birds. The purpose of our study was to determine bile-salt variation among birds and relate this variation to current avian phylogenies and hypotheses on the evolution of bile salt pathways. We determined the biliary bile-salt composition of 405 phylogenetically diverse bird species, including 7 paleognath species. Bile salt profiles were generally stable within bird families. Complex bile-salt profiles were more common in omnivores and herbivores than in carnivores. The structural variation of bile salts in birds is extensive and comparable to that seen in surveys of bile salts in reptiles and mammals. Birds produce many of the bile salts found throughout nonavian vertebrates and some previously uncharacterized bile salts. One difference between birds and other vertebrates is extensive hydroxylation of carbon-16 of bile salts in bird species. Comparison of our data set of bird bile salts with that of other vertebrates, especially reptiles, allowed us to infer evolutionary changes in the bile salt synthetic pathway. PMID:21113274

  15. COMPLEX EVOLUTION OF BILE SALTS IN BIRDS

    PubMed Central

    Hagey, Lee R.; Vidal, Nicolas; Hofmann, Alan F.; Krasowski, Matthew D.

    2010-01-01

    Bile salts are the major end-metabolites of cholesterol and are important in lipid digestion and shaping of the gut microflora. There have been limited studies of bile-salt variation in birds. The purpose of our study was to determine bile-salt variation among birds and relate this variation to current avian phylogenies and hypotheses on the evolution of bile salt pathways. We determined the biliary bile-salt composition of 405 phylogenetically diverse bird species, including 7 paleognath species. Bile salt profiles were generally stable within bird families. Complex bile-salt profiles were more common in omnivores and herbivores than in carnivores. The structural variation of bile salts in birds is extensive and comparable to that seen in surveys of bile salts in reptiles and mammals. Birds produce many of the bile salts found throughout nonavian vertebrates and some previously uncharacterized bile salts. One difference between birds and other vertebrates is extensive hydroxylation of carbon-16 of bile salts in bird species. Comparison of our data set of bird bile salts with that of other vertebrates, especially reptiles, allowed us to infer evolutionary changes in the bile salt synthetic pathway. PMID:21113274

  16. Leaching behavior of phosphate-bonded ceramic waste forms

    SciTech Connect

    Singh, D.; Wagh, A.S.; Jeong, S.Y.; Dorf, M.

    1996-04-01

    Over the last few years, Argonne National Laboratory has been developing room-temperature-setting chemically bonded phosphate ceramics for solidifying and stabilizing low-level mixed wastes. This technology is crucial for stabilizing waste streams that contain volatile species and off-gas secondary waste streams generated by high-temperature treatment of such wastes. We have developed a magnesium phosphate ceramic to treat mixed wastes such as ash, salts, and cement sludges. Waste forms of surrogate waste streams were fabricated by acid-base reactions between the mixtures of magnesium oxide powders and the wastes, and phosphoric acid or acid phosphate solutions. Dense and hard ceramic waste forms are produced in this process. The principal advantage of this technology is that the contaminants are immobilized by both chemical stabilization and subsequent microencapsulation of the reaction products. This paper reports the results of durability studies conducted on waste forms made with ash waste streams spiked with hazardous and radioactive surrogates. Standard leaching tests such as ANS 16.1 and TCLP were conducted on the final waste forms. Fates of the contaminants in the final waste forms were established by electron microscopy. In addition, stability of the waste forms in aqueous environments was evaluated with long-term water-immersion tests.

  17. Method of preparing sodalite from chloride salt occluded zeolite

    DOEpatents

    Lewis, M.A.; Pereira, C.

    1997-03-18

    A method is described for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form leach resistant sodalite with occluded radionuclides and hazardous nuclear material. The zeolite and glass are heated to a temperature up to about 1000 K to convert the zeolite to sodalite and thereafter maintained at a pressure and temperature sufficient to form a sodalite product near theoretical density. Pressure is used on the formed sodalite to produce the required density.

  18. Method of preparing sodalite from chloride salt occluded zeolite

    DOEpatents

    Lewis, Michele A. (Naperville, IL); Pereira, Candido (Lisle, IL)

    1997-01-01

    A method for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form leach resistant sodalite with occluded radionuclides and hazardous nuclear material. The zeolite and glass are heated to a temperature up to about 1000.degree. K. to convert the zeolite to sodalite and thereafter maintained at a pressure and temperature sufficient to form a sodalite product near theoretical density. Pressure is used on the formed sodalite to produce the required density.

  19. Method of preparing sodalite from chloride salt occluded zeolite A

    SciTech Connect

    Lewis, M.A.; Pereira, C.

    1995-12-31

    A method is described for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form leach resistance sodalite with occluded radionuclides and hazardous nuclear material. The zeolite and glass are heated to a temperature up to about 1,000 K to convert the zeolite to sodalite and thereafter maintained at a pressure and temperature sufficient to form a sodalite product near theoretical density. Pressure is used on the formed sodalite to produce the required density.

  20. Potash recovery from process and waste brines by solar evaporation and flotation. Report of Investigations\\/1984

    Microsoft Academic Search

    D. G. Foot; J. L. Huiatt; L. J. Froisland

    1984-01-01

    The Bureau of Mines investigated energy-efficient methods for recovering potash values from process and waste brines. Laboratory pan evaporation of four chloride brines produced crude salts containing predominantly sylvite, halite, and carnallite. Six sulfate-chloride brines produced crude salts containing primarily schoenite, kainite, leonite, sylvite, carnallite, and halite. An economic evaluation suggested a rate of return of 3 pct for a

  1. Development and testing of a wet oxidation waste processing system. [for waste treatment aboard manned spacecraft

    NASA Technical Reports Server (NTRS)

    Weitzmann, A. L.

    1977-01-01

    The wet oxidation process is considered as a potential treatment method for wastes aboard manned spacecraft for these reasons: (1) Fecal and urine wastes are processed to sterile water and CO2 gas. However, the water requires post-treatment to remove salts and odor; (2) the residual ash is negligible in quantity, sterile and easily collected; and (3) the product CO2 gas can be processed through a reduction step to aid in material balance if needed. Reaction of waste materials with oxygen at elevated temperature and pressure also produces some nitrous oxide, as well as trace amounts of a few other gases.

  2. Coupled Hydro-mechanical Processes In Rock Salt

    NASA Astrophysics Data System (ADS)

    Popp, T.; Kern, H.; Schulze, O.

    Salt structures are widely used as host rocks for the storage of oil and hydrocarbons and, probably, for the long-term storage of radioactive waste, due to their very low in-situ permeability (less than 10-20 m2). The low permeability is basically attributed to the ductility of the halite minerals ensuring healing processes. Nevertheless, rock salt shows all aspects of brittle-ductile deformation. The poster presents results of deformation experiments focusing on the transport properties of rock salt subjected to a pore fluid pressure. Combined measurements of ultrasonic wave velocities (Vp, Vs) and permeability were used to determine the state of stresses at the dilatancy boundary, that is, at the transition from the compaction to the dilation domain. The crack-sensitivity of ultrasonic wave velocities is found to provide a powerful means to monitor the in-situ state of the microstructure and to identify onset of dilatancy. Loading in the dilatant stress domain gives rise to the generation and propagation of cracks and to the increase of damage with strain. Effects of pore fluid pressure leading to reduction of effective pressure are only of importance in the dilatant domain, due to strain-induced increase of permeability. The coupling between stress and fluid flow is particularly dependent on the geometry of the fracture network. The experimental results give evidence that rock salt tends to become permeable at two specific con- ditions: (1) at large deviatoric stresses (see also Peach, 1991; Popp et al., 2001), and (2) at fluid pressures higher than the minimum principal stress. At conditions where fluids can permeate into the polycrystalline microstructure and generate a pore fluid pressure the physical properties of rock salt will be significantly changed.

  3. Protein aggregation in salt solutions.

    PubMed

    Kastelic, Miha; Kalyuzhnyi, Yurij V; Hribar-Lee, Barbara; Dill, Ken A; Vlachy, Vojko

    2015-05-26

    Protein aggregation is broadly important in diseases and in formulations of biological drugs. Here, we develop a theoretical model for reversible protein-protein aggregation in salt solutions. We treat proteins as hard spheres having square-well-energy binding sites, using Wertheim's thermodynamic perturbation theory. The necessary condition required for such modeling to be realistic is that proteins in solution during the experiment remain in their compact form. Within this limitation our model gives accurate liquid-liquid coexistence curves for lysozyme and [Formula: see text] IIIa-crystallin solutions in respective buffers. It provides good fits to the cloud-point curves of lysozyme in buffer-salt mixtures as a function of the type and concentration of salt. It than predicts full coexistence curves, osmotic compressibilities, and second virial coefficients under such conditions. This treatment may also be relevant to protein crystallization. PMID:25964322

  4. Evaluation of potential for MSRE spent fuel and flush salt storage and treatment at the INEL

    SciTech Connect

    Ougouag, A.M.; Ostby, P.A.; Nebeker, R.L.

    1996-09-01

    The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spent fuel at INEL has been evaluated. Provided that some minimal packaging and chemical stabilization prerequisites are satisfied, safe interim storage of the spent fuel at the INEL can be achieved in a number of existing or planned facilities. Treatment by calcination in the New Waste Calcining Facility at the INEL can also be a safe, effective, and economical alternative to treatment that would require the construction of a dedicated facility. If storage at the INEL is chosen for the Molten Salt Reactor Experiment (MSRE) spent fuel salts, their transformation to the more stable calcine solid would still be desirable as it would result in a lowering of risks. Treatment in the proposed INEL Remote-Handled Immobilization Facility (RHIF) would result in a waste form that would probably be acceptable for disposal at one of the proposed national repositories. The cost increment imputable to the treatment of the MSRE salts would be a small fraction of the overall capital and operating costs of the facility or the cost of building and operating a dedicated facility. Institutional and legal issues regarding shipments of fuel and waste to the INEL are summarized. The transfer of MSRE spent fuel for interim storage or treatment at the INEL is allowed under existing agreements between the State of idaho and the Department of energy and other agencies of the Federal Government. In contrast, current agreements preclude the transfer into Idaho of any radioactive wastes for storage or disposal within the State of Idaho. This implies that wastes and residues produced from treating the MSRE spent fuel at locations outside Idaho would not be acceptable for storage in Idaho. Present agreements require that all fuel and high-level wastes stored at the INEL, including MSRE spent fuel if received at the INEL, must be moved to a location outside Idaho by the year 2035.

  5. Salt flat and salt grass habitat at the Mojave desert

    NSDL National Science Digital Library

    Katie Hale (California State University, Fullerton; Student, Biological Sciences)

    2007-01-06

    The salt flat/ grass habitat provides shade and shelter for desert organisms. This habitat is found at a higher elevation than the sand and rock habitats and has slightly cooler temperatures and more moisture, which accounts for the abundance of vegetation.

  6. On Progressive Law Teaching: SALT Principles, SALT Values

    Microsoft Academic Search

    Matthew Charity; Jackie Gardina; Ngai Pindell

    2012-01-01

    This session discusses what it means to teach a progressive curriculum and educate from a social justice perspective. It is also an introduction to the Society of American Law Teachers (SALT), a community of activist law professors allied with LatCrit. Finally, the session will focus on the networking advantages that can result from a connection to a progressive law teachers’

  7. Recent advances in the molten salt destruction of energetic materials

    SciTech Connect

    Pruneda, C. O., LLNL

    1996-09-01

    We have demonstrated the use of the Molten Salt Destruction (MSD) Process for destroying explosives, liquid gun propellant, and explosives-contaminated materials on a 1.5 kg of explosive/hr bench- scale unit (1, 2, 3, 4, 5). In our recently constructed 5 kg/hr pilot- scale unit we have also demonstrated the destruction of a liquid gun propellant and simulated wastes containing HMX (octogen). MSD converts the organic constituents of the waste into non-hazardous substances such as carbon dioxide, nitrogen, and water. Any inorganic constituents of the waste, such as metallic particles, are retained in the molten salt. The destruction of energetic materials waste is accomplished by introducing it, together with air, into a vessel containing molten salt (a eutectic mixture of sodium, potassium, and lithium carbonates). The following pure explosives have been destroyed in our bench-scale experimental unit located at Lawrence Livermore National Laboratory`s (LLNL) High Explosives Applications Facility (HEAF): ammonium picrate, HMX, K- 6 (keto-RDX), NQ, NTO, PETN, RDX, TATB, and TNT. In addition, the following compositions were also destroyed: Comp B, LX- IO, LX- 1 6, LX- 17, PBX-9404, and XM46 (liquid gun propellant). In this 1.5 kg/hr bench-scale unit, the fractions of carbon converted to CO and of chemically bound nitrogen converted to NO{sub x} were found to be well below 1%. In addition to destroying explosive powders and compositions we have also destroyed materials that are typical of residues which result from explosives operations. These include shavings from machined pressed parts of plastic-bonded explosives and sump waste containing both explosives and non-explosive debris. Based on the process data obtained on the bench-scale unit we designed and constructed a next-generation 5 kg/hr pilot-scale unit, incorporating LLNL`s advanced chimney design. The pilot unit has completed process implementation operations and explosives safety reviews. To date, in this pilot unit we have successfully destroyed liquid gun propellant and dimethylsulfoxide containing HMX in continuous, long-duration runs.

  8. Potential for exothermic chemical reactions in waste tanks

    SciTech Connect

    Van Tuyl, H.H.

    1983-02-03

    The potential for exothermic chemical reactions in waste tanks at Hanford is discussed. Organic chemicals have been added to Hanford waste tanks, particularly as ferrocyanides and when processing sludges at B Plant. Recent planned or ongoing activities involving stored wastes have possibly increased the potential for reaction of these wastes with nitrate salts in the waste tanks. Risk evaluations appear to be deficient in assessing the consequences of a deflagration, and in determining the probability of either a deflagration or detonation. The present question is whether current plans and recent safety-related documentation have given proper consideration to the available information about organic compounds in waste tanks. The principal organic additions to Hanford waste tanks are 1200 tonnes of organic carbon'' and 500 tonnes of Ni{sub 2}Fe(CN){sub 6}. 13 refs.

  9. Deformation of allochthonous salt and evolution of related salt-structural systems, eastern Louisiana Gulf Coast

    SciTech Connect

    Schuster, D.C. [Shell Offshore Inc., New Orleans, LA (United States)

    1996-12-31

    Salt tectonics in the northern Gulf of Mexico involves both vertical diapirism and lateral silling or flow of salt into wings and tablets (sheets). Combinations of these two modes of salt deformation, concurrent with sediment loading and salt evacuation, have produced complex structures in the coastal and offshore region of southeastern Louisiana, a prolific oil and gas province. Many large growth faults and salt domes in the study area root into intra-Tertiary salt welds that were formerly occupied by allochthonous salt tablets. Two end-member structural systems involving evacuation of former tabular salt are recognized: roho systems and stepped counter-regional systems. Both end-member systems share a similar multi-staged evolution, including (1) initial formation of a south-leaning salt dome or wall sourced from the Jurassic salt level; (2) progressive development into a semi-tabular allochthonous salt body; and (3) subsequent loading, evacuation, and displacement of the tabular salt into secondary domes. In both systems, it is not uncommon to find salt displaced as much as 16-24 km south of its autochthonous source, connected by a horizontal salt weld to an updip, deflated counter-regional feeder. Although both end-member structural systems may originate before loading of allochthonous salt having grossly similar geometry, their final structural configurations after loading and salt withdrawal are distinctly different. Roho systems are characterized by large-displacement, listric, south-dipping growth faults that sole into intra-Tertiary salt welds marked by high-amplitude reflections continuous with residual salt masses. Salt from the former salt tablets has been loaded and squeezed laterally and downdip. Stepped counter-regional systems, in contrast, comprise large salt domes and adjacent large-displacement, north-dipping growth faults that sole into intra-Tertiary salt welds before stepping down again farther north.

  10. Ferrocyanide-containing waste tanks: Ferrocyanide chemistry and reactivity

    SciTech Connect

    Scheele, R.D.; Burger, L.L.; Tingey, J.M.; Bryan, S.A. (Pacific Northwest Lab., Richland, WA (United States)); Borsheim, G.L.; Simpson, B.C.; Cash, R.J. (Westinghouse Hanford Co., Richland, WA (United States)); Cady, H.H. (Los Alamos National Lab., NM (United States))

    1991-09-01

    The complexing constant for hexacyano-iron complexes, both Fe(2) and Fe(3), are exceptionally large. The derived transition metal salts or double salts containing alkali metal ions are only slightly soluble. The various nickel compounds examined in this study, i.e., those predicted to have been formed in the Hanford waste scavenging program, are typical examples. In spite of their relative stability towards most reagents under ambient conditions, they are all thermodynamically unstable towards oxidation and react explosively with oxidants such as nitrate or nitrate salts when heated to temperatures in excess of 200{degree}C. 42 refs., 5 figs., 3 tabs.

  11. I-NERI-2007-004-K, DEVELOPMENT AND CHARACTERIZATION OF NEW HIGH-LEVEL WASTE FORMS FOR ACHIEVING WASTE MINIMIZATION FROM PYROPROCESSING

    SciTech Connect

    S.M. Frank

    2011-09-01

    Work describe in this report represents the final year activities for the 3-year International Nuclear Energy Research Initiative (I-NERI) project: Development and Characterization of New High-Level Waste Forms for Achieving Waste Minimization from Pyroprocessing. Used electrorefiner salt that contained actinide chlorides and was highly loaded with surrogate fission products was processed into three candidate waste forms. The first waste form, a high-loaded ceramic waste form is a variant to the CWF produced during the treatment of Experimental Breeder Reactor-II used fuel at the Idaho National Laboratory (INL). The two other waste forms were developed by researchers at the Korean Atomic Energy Research Institute (KAERI). These materials are based on a silica-alumina-phosphate matrix and a zinc/titanium oxide matrix. The proposed waste forms, and the processes to fabricate them, were designed to immobilize spent electrorefiner chloride salts containing alkali, alkaline earth, lanthanide, and halide fission products that accumulate in the salt during the processing of used nuclear fuel. This aspect of the I-NERI project was to demonstrate 'hot cell' fabrication and characterization of the proposed waste forms. The outline of the report includes the processing of the spent electrorefiner salt and the fabrication of each of the three waste forms. Also described is the characterization of the waste forms, and chemical durability testing of the material. While waste form fabrication and sample preparation for characterization must be accomplished in a radiological hot cell facility due to hazardous radioactivity levels, smaller quantities of each waste form were removed from the hot cell to perform various analyses. Characterization included density measurement, elemental analysis, x-ray diffraction, scanning electron microscopy and the Product Consistency Test, which is a leaching method to measure chemical durability. Favorable results from this demonstration project will provide additional options for fission product immobilization and waste management associated the electrochemical/pyrometallurgical processing of used nuclear fuel.

  12. Salt dome discoveries mounting in Mississippi

    SciTech Connect

    Ericksen, R.L. [Mississippi Office of Geology, Jackson, MS (United States)

    1996-06-17

    Exploratory drilling around piercement salt domes in Mississippi has met with a string of successes in recent months. Exploration of these salt features is reported to have been initiated through the review of non-proprietary, 2D seismic data and subsurface control. This preliminary data and work were then selectively upgraded by the acquisition of additional, generally higher quality, conventional 2D seismic lines. This current flurry of successful exploration and ensuing development drilling by Amerada Hess Corp. on the flanks of salt domes in Mississippi has resulted in a number of significant Hosston discoveries/producers at: Carson salt dome in Jefferson Davis County; Dry Creek salt dome in Covington County, Midway salt dome in lamar County, Monticello salt dome in Lawrence County, and Prentiss salt dome in Jefferson Davis County. The resulting production from these fields is gas and condensate, with wells being completed on 640 acre production units.

  13. Salt tolerance of grasses for range seeding

    E-print Network

    Hartmann, Francis Stephen

    1973-01-01

    6 A~tin stolonifera L. (Redtop) eithet exclude or excrete large amounts of undesirable salts present in the growth media (Hannon and Newtan, 1972). Halophytes accumulate and excrete high levels of salt through specia'1 glands on plant leaves...

  14. STANDARD OPERATING PROCEDURE HEAVY METAL SALTS (selected)

    E-print Network

    Pawlowski, Wojtek

    12.1 STANDARD OPERATING PROCEDURE for HEAVY METAL SALTS (selected) Location(s): ___________________________________________________ Chemical(s): heavy metal salts: acetates, chlorides, sulfates, nitrates, anhydrides, oxides, hydroxides procedures. Specific instructions: All solids and liquids containing heavy metals must be disposed

  15. Why does salt melt ice?

    NSDL National Science Digital Library

    Fred Senese

    This tutorial on the chemical interaction between salt and ice explains how molecules on the surface of the ice escape into the water (melting), and how molecules of water are captured on the surface of the ice (freezing). It was created by the Chemistry Department at Frostburg State University (no, really).

  16. From Salt Ponds to Wetlands

    NSDL National Science Digital Library

    2012-02-22

    Biologists are working to restore the San Francisco Bay Area salt ponds to healthy wetlands for wildlife in one of the largest restoration projects on the West Coast. In this video from QUEST produced by KQED, students learn why wetlands are important to wildlife.

  17. Coagulation by hydrolysing metal salts

    Microsoft Academic Search

    Jinming Duan; John Gregory

    2003-01-01

    Aluminium and iron salts are widely used as coagulants in water and wastewater treatment and in some other applications. They are effective in removing a broad range of impurities from water, including colloidal particles and dissolved organic substances. Their mode of action is generally explained in terms of two distinct mechanisms: charge neutralisation of negatively charged colloids by cationic hydrolysis

  18. Infrared Spectrometry of Inorganic Salts

    ERIC Educational Resources Information Center

    Ackermann, Martin N.

    1970-01-01

    Describes a general chemistry experiment which uses infrared spectroscopy to analyze inorganic ions and thereby serves to introduce an important instrumental method of analysis. Presents a table of eight anions and the ammonium ion with the frequencies of their normal modes, as well as the spectra of three sulfate salts. (RR)

  19. PROCESSING OF MOLTEN SALT POWER REACTOR FUEL

    Microsoft Academic Search

    D. O. Campbell; G. I. Cathers

    1959-01-01

    ABS> Fuel reprocessing methods are being investigated for molten salt ; nuclear reactors which use LiF--BeFâ salt as a solvent for UFâ and ; ThFâ. A liquid HF dissolution procedure coupled with fluorination has been ; developed for recovery of the uranium and LiF- BeFâ solvent salt which is ; highly enriched in Li⁷. The recovered salt is decontaminated in

  20. Fenofibrate lowers blood pressure in salt-sensitive but not salt-resistant hypertension

    PubMed Central

    Gilbert, Kimberly; Nian, Hui; Yu, Chang; Luther, James M.; Brown, Nancy J.

    2013-01-01

    Objective Peroxisome proliferator-activated receptor ? agonists reduce blood pressure in rodents, but clinical trials provide conflicting data regarding their effects in humans. We tested the hypothesis that the effect of fenofibrate on blood pressure depends on salt sensitivity. Methods Thirty-one hypertensive volunteers (17 salt-resistant, 14 salt-sensitive) completed a randomized, crossover, double-blind protocol with three dietary phases: low salt diet (10 mmol/day) followed by two consecutive high salt diets (200 mmol/day), each for 6 days. During high salt, volunteers were randomized to fenofibrate 160 mg/day or placebo. Hemodynamic and metabolic parameters were measured on the last morning of each treatment arm. Results Fenofibrate reduced triglycerides similarly in salt-sensitive and salt-resistant volunteers. Fenofibrate did not affect blood pressure in salt-resistant volunteers. In salt-sensitive volunteers, fenofibrate significantly decreased diastolic (P =0.02 versus placebo) and mean arterial (P = 0.04 versus placebo) blood pressure during high salt. In all volunteers, the decrease in systolic pressure during fenofibrate correlated inversely with the salt sensitivity of mean arterial pressure as a continuous variable. Fenofibrate significantly decreased heart rate, plasma renin activity, and renal vascular resistance during high salt in salt-sensitive volunteers, but not salt-resistant volunteers. Fenofibrate did not affect sodium excretion or weight gain during high salt. The effect of salt intake and fenofibrate on plasma and urine epoxyeicosatrienoic acid concentrations differed in salt-resistant and salt-sensitive volunteers. Conclusion Fenofibrate reduces blood pressure, heart rate and renal vasoconstriction in salt-sensitive volunteers, but not in salt-resistant volunteers. These findings have implications for the treatment of hyperlipidemia in hypertensive individuals. PMID:23385647

  1. Waste heat

    SciTech Connect

    Moore, N.L.

    1985-07-01

    This is a survey of waste heat recovery in US industry. Future prospects depend on the price of fossil fuels. Fuel and energy consumption in the year 2000 is summarized. Areas of greatest growth in waste heat recovery will be in high-temperature recuperation, heat pumps and cogeneration. (DLC)

  2. Radioactive wastes

    Microsoft Academic Search

    Devarakonda

    1993-01-01

    This paper reviews research and technological progress in radioactive waste management and disposal. The scope of material covered is very broad, ranging from international cooperation in radioactive waste management to evaluation of specific treatment technologies. The issue of safely managing and disposing of the plutonium resulting from the dismantling of weapons across the world is discussed and a series of

  3. INTERSECTION OF 445 NORTH & 1040 EAST, SALT LAKE CITY, ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    INTERSECTION OF 445 NORTH & 1040 EAST, SALT LAKE CITY, UT. VIEW LOOKING SOUTH. REPHOTOGRAPH OF HISTORIC SHIPLER PHOTO # 18272, UTAH STATE HISTORICAL SOCIETY COLLECTION. - Salt Lake City Cemetery, 200 N Street, Salt Lake City, Salt Lake County, UT

  4. 200 MAIN STREET, SALT LAKE CITY, UT. VIEW LOOKING EAST ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    200 MAIN STREET, SALT LAKE CITY, UT. VIEW LOOKING EAST OF "MAIN' STREET. REPHOTOGRAPH OF HISTORIC SHIPLER PHOTO # 18273, UTAH STATE HISTORICAL SOCIETY COLLECTION. - Salt Lake City Cemetery, 200 N Street, Salt Lake City, Salt Lake County, UT

  5. Disparities in Salt Lake County and Salt Lake City Mortgage Outcomes and

    E-print Network

    Feschotte, Cedric

    Disparities in Salt Lake County and Salt Lake City Mortgage Outcomes and Lending Practices Darius of lending practices. This article is an adapted excerpt from the Salt Lake County Regional Analysis impediments in the home mortgage application process. The HMDA data from 2006 to 2011 were compiled for Salt

  6. Salt marsh geomorphology: Physical and ecological effects on landform Keywords: salt marsh geomorphology; AGU Chapman Conference

    E-print Network

    Fagherazzi, Sergio

    Editorial Salt marsh geomorphology: Physical and ecological effects on landform Keywords: salt marsh geomorphology; AGU Chapman Conference Evidence that the three-dimensional structure of salt marsh, and the ratio of marsh edge:marsh interior have all been shown to affect the distribution and density of salt

  7. First Robert Stobie SALT Workshop Science with SALT Workshop Proceedings, Vol. 2, 2004

    E-print Network

    Bershady, Matthew A.

    First Robert Stobie SALT Workshop Science with SALT Workshop Proceedings, Vol. 2, 2004 D.A.H. Buckley Galaxy Kinematics with SALT M. A. Bershady1, M. A. W. Verheijen2, D. R. Andersen3, R. A. Swaters4-gathering power of SALT coupled with the high-throughput performance of the Prime Focus Imaging Spec- trograph

  8. Effects of different pre-salting methods on protein aggregation during heavy salting of cod fillets

    Microsoft Academic Search

    Kristin Anna Thorarinsdottir; Sigurjon Arason; Sjofn Sigurgisladottir; Thora Valsdottir; Eva Tornberg

    2011-01-01

    The use of injection and brining as the first step in heavy salting of cod increases weight yields of the products through both salting and rehydration, compared to other pre-salting methods, like brining only and pickling. This is interesting since salt content of the muscle exceeds 20% NaCl, in all procedures. Therefore, the dissimilarities in yield were presumed to depend

  9. Reactivity of pyrylium salts toward basic reactants

    NASA Technical Reports Server (NTRS)

    Neidlein, R.; Witerzens, P.

    1981-01-01

    The reactivity of some N-acyl and N-sulfonyl-hydrazines 2-4, 10a-10g, 12, 13, 16a, 16b and of hydrazones 18, benzyldihydrazone 21 towards pyrylium salts 1 was examined. By reaction of 2,4,6-trimethyl-pyrylium salt 1 with substituted hydrazines some pyridinium salts were obtained. Relationships between basicity and reactivity were discussed.

  10. 7 CFR 58.437 - Salt.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ...Agriculture 3 2010-01-01 2010-01-01 false Salt. 58.437 Section 58.437 Agriculture Regulations...Quality Specifications for Raw Material § 58.437 Salt. The salt shall be free-flowing, white refined sodium...

  11. 7 CFR 58.328 - Salt.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ...Agriculture 3 2013-01-01 2013-01-01 false Salt. 58.328 Section 58.328 Agriculture Regulations...Quality Specifications for Raw Material § 58.328 Salt. The salt shall be free-flowing, white refined sodium...

  12. 7 CFR 58.328 - Salt.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ...Agriculture 3 2011-01-01 2011-01-01 false Salt. 58.328 Section 58.328 Agriculture Regulations...Quality Specifications for Raw Material § 58.328 Salt. The salt shall be free-flowing, white refined sodium...

  13. 7 CFR 58.328 - Salt.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ...Agriculture 3 2014-01-01 2014-01-01 false Salt. 58.328 Section 58.328 Agriculture Regulations...Quality Specifications for Raw Material § 58.328 Salt. The salt shall be free-flowing, white refined sodium...

  14. 7 CFR 58.437 - Salt.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ...Agriculture 3 2012-01-01 2012-01-01 false Salt. 58.437 Section 58.437 Agriculture Regulations...Quality Specifications for Raw Material § 58.437 Salt. The salt shall be free-flowing, white refined sodium...

  15. Moving salt sills and hydrocarbon maturity

    NASA Astrophysics Data System (ADS)

    Carter, K.; Lerche, I.

    1992-09-01

    Salt sills have been observed in the Gulf Coast. The contrast in the thermal conductivity between salt and detrital sediments means that a salt sill focuses heat around its leading edge, resulting in the devlopment of an anomalous temperature pattern in the vicinity of the salt sill. The consequent anomaly in thermal maturity pattern for hydrocarbons is related to four parameters: the salt sill thickness; the subsurface depth of the sill; the inclination of the sill; and the salt speed through the sediments. The excess maturity in the vicinity of the salt sill is shown to be dominantly dependent on the velocity of the salt sill. The positional influence of the hydrocarbon maturity relative to the salt is also examined and it is shown that the alteration of sedimentary burial paths by the inserted salt also causes a thermal anomaly. Both thermal focusing of heat by salt and sediment burial to a different thermal regime caused by passage of inserted salt produce thermal maturity effects comparable in magnitude, and neither may be ignored.

  16. 3, 499527, 2006 Salt intrusion in

    E-print Network

    Paris-Sud XI, Université de

    HESSD 3, 499­527, 2006 Salt intrusion in multi-channel estuaries A. D. Nguyen and H. H. G. Savenije System Sciences Salt intrusion in multi-channel estuaries: a case study in the Mekong Delta, Vietnam A. D­527, 2006 Salt intrusion in multi-channel estuaries A. D. Nguyen and H. H. G. Savenije Title Page Abstract

  17. DEVELOPING INDICATORS OF SALT MARSH HEALTH

    EPA Science Inventory

    We relate plant zonation in salt marshes to key ecosystem services such as erosion control and wildlife habitat. Ten salt marshes in Narragansett Bay, with similar geological bedrock and sea exchange, were identified to examine plant zonation. Sub-watersheds adjacent to the salt ...

  18. Reactions of alkynylselenonium salts with sodium benzenesulfinate

    Microsoft Academic Search

    Tadashi Kataoka; Yoshihiro Banno; Shin-ichi Watanabe; Tatunori Iwamura; Hiroshi Shimizu

    1997-01-01

    Alkynylselenonium salts 2 and 5 were synthesized and treated with benzenesulfinic acid or its sodium salt in an alcohol. The reactions with sodium benzenesulfinate gave (Z)-?-alkoxyvinylsulfones 6 as main products, while the reactions with benzenesulfinic acid afforded the ?-sulfonylvinylselenonium salts 11 and 12 in good yields.

  19. Correlation of theoretical calculations and experimental measurements of damage around a shaft in salt

    SciTech Connect

    Munson, D.E.; Holcomb, D.J. [Sandia National Labs., Albuquerque, NM (United States); DeVries, K.L.; Brodsky, N.S. [RE/SPEC, Inc., Rapid City, SD (United States); Chan, K.S. [Southwest Research Inst., San Antonio, TX (United States)

    1994-12-31

    Cross-hole ultrasonic measurements were made in the immediate wall of the Air Intake Shaft of the Waste Isolation Pilot Plant facility. These measurements show that compressional wave speed markedly decreases at the shaft wall and then increases with radial distance from the shaft to eventually become that of solid or undamaged salt. This behavior is indicative of deformation damage or microfractures in the salt. These in situ data are compared to both laboratory measurements of wave speed as a function of volume dilatancy and to calculations based on the Multimechanism Deformation Coupled Fracture model, with reasonable agreement.

  20. Thermal energy storage – overview and specific insight into nitrate salts for sensible and latent heat storage

    PubMed Central

    Bauer, Thomas; Martin, Claudia; Eck, Markus; Wörner, Antje

    2015-01-01

    Summary Thermal energy storage (TES) is capable to reduce the demand of conventional energy sources for two reasons: First, they prevent the mismatch between the energy supply and the power demand when generating electricity from renewable energy sources. Second, utilization of waste heat in industrial processes by thermal energy storage reduces the final energy consumption. This review focuses mainly on material aspects of alkali nitrate salts. They include thermal properties, thermal decomposition processes as well as a new method to develop optimized salt systems. PMID:26199853

  1. Bases, Assumptions, and Results of the Flowsheet Calculations for the Decision Phase Salt Disposition Alternatives

    SciTech Connect

    Dimenna, R.A.; Jacobs, R.A.; Taylor, G.A.; Durate, O.E.; Paul, P.K.; Elder, H.H.; Pike, J.A.; Fowler, J.R.; Rutland, P.L.; Gregory, M.V.; Smith III, F.G.; Hang, T.; Subosits, S.G.; Campbell, S.G.

    2001-03-26

    The High Level Waste (HLW) Salt Disposition Systems Engineering Team was formed on March 13, 1998, and chartered to identify options, evaluate alternatives, and recommend a selected alternative(s) for processing HLW salt to a permitted wasteform. This requirement arises because the existing In-Tank Precipitation process at the Savannah River Site, as currently configured, cannot simultaneously meet the HLW production and Authorization Basis safety requirements. This engineering study was performed in four phases. This document provides the technical bases, assumptions, and results of this engineering study.

  2. Separation and Fixation of Toxic Components in Salt Brines Using a Water-Based Process

    SciTech Connect

    Franks, C.; Quach, A.; Birnie III, D.; Ela, W.; Saez, A.E.; Zelinski, B.; Smith, H.; Smith, G.

    2004-01-01

    Efforts to implement new water quality standards, increase water reuse and reclamation, and minimize the cost of waste storage motivate the development of new processes for stabilizing wastewater residuals that minimize waste volume, water content and the long-term environmental risk from related by-products. This work explores the use of an aqueous-based emulsion process to create an epoxy/rubber matrix for separating and encapsulating waste components from salt laden, arsenic contaminated, amorphous iron hydrate sludges. Such sludges are generated from conventional water purification precipitation/adsorption processes, used to convert aqueous brine streams to semi-solid waste streams, such as ion exchange/membrane separation, and from other precipitative heavy metal removal operations. In this study, epoxy and polystyrene butadiene (PSB) rubber emulsions are mixed together and then combined with a surrogate sludge. The surrogate sludge consists of amorphous iron hydrate with 1 part arsenic fixed to the surface of the hydrate per 10 parts iron mixed with sodium nitrate and chloride salts and water. The resulting emulsion is cured and dried at 80 °C to remove water. Microstructure characterization by electron microscopy confirms that the epoxy/PSB matrix surrounds and encapsulates the arsenic laden amorphous iron hydrate phase while allowing the salt to migrate to internal and external surfaces of the sample. Salt extraction studies indicate that the porous nature of the resulting matrix promotes the separation and removal of as much as 90% of the original salt content in only one hour. Long term leaching studies based on the use of the infinite slab diffusion model reveal no evidence of iron migration or, by inference, arsenic migration, and demonstrate that the diffusion coefficients of the unextracted salt yield leachability indices within regulations for non-hazardous landfill disposal. Because salt is the most mobile species, it is inferred that arsenic leaches from the host material at an even slower rate, making the waste forms amenable to unregulated land disposal options. These results indicate that the environmentally-benign, water-based emulsion processing of epoxy/PSB polymeric hosts show great promise as a separation and fixation technology for treating brine streams from wastewater treatment facilities.

  3. Neutralized current acid waste consolidation management plan

    SciTech Connect

    Powell, W.J.; Brown, R.G.; Galbraith, J.; Jensen, C.; Place, D.E.; Reddick, G.W.; Zuroff, W. [Westinghouse Hanford Co., Richland, WA (United States); Brothers, A.J. [Pacific Northwest National Lab., Richland, WA (United States)

    1996-01-01

    The scope of this evaluation is to recommend a management plan for the high-heat tank waste, including neutralized current acid waste (NCAW) in AY and AZ Tank Farms, and tank C-106 waste. The movement of solids, liquids and salt cake in the designated tank farms is included. Decision analysis techniques were used to determine a recommended alternative. The recommended course of action was replacement of a 75-hp mixer pump in tank AY-102 and in-tank concentration of tank AZ-102 supernate. The alternative includes transfer fo tank C-106 sludge to tank AY-102, then transfer to tank AY-102 and tank C-106 sludge to tank AZ-101 using the new 75-hp mixer pump installed in tank AY-102. Tank AZ-101 becomes a storage tank for high-level waste (HLW) sludge, with the capacity to mix and transfer sludge as desired.

  4. Polyethylene solidification of low-level wastes

    SciTech Connect

    Kalb, P.D.; Colombo, P.

    1985-02-01

    This topical report describes the results of an investigation on the solidification of low-level radioactive waste in polyethylene. Waste streams selected for this study included those which result from advanced volume reduction technologies (dry evaporator concentrate salts and incinerator ash) and those which remain problematic for solidification using contemporary agents (ion exchange resins). Four types of commercially available low-density polyethylenes were employed which encompass a range of processing and property characteristics. Process development studies were conducted to ascertain optimal process control parameters for successful solidification. Maximum waste loadings were determined for each waste and polyethylene type. Property evaluation testing was performed on laboratory-scale specimens to assess the potential behavior of actual waste forms in a disposal environment. Waste form property tests included water immersion, deformation under compressive load, thermal cycling and radionuclide leaching. Recommended waste loadings of 70 wt % sodium sulfate, 50 wt % boric acid, 40 wt % incinerator ash, and 30 wt % ion exchange resins, which are based on process control and waste form performance considerations are reported. 37 refs., 33 figs., 22 tabs.

  5. NUCLEAR WASTE GLASSES CONTINUOUS MELTING AND BULK VITRIFICAITON

    SciTech Connect

    KRUGER AA; HRMA PR

    2008-03-24

    This contribution addresses various aspects of nuclear waste vitrification. Nuclear wastes have a variety of components and composition ranges. For each waste composition, the glass must be formulated to possess acceptable processing and product behavior defined in terms of physical and chemical properties that guarantee the glass can be easily made and resist environmental degradation. Glass formulation is facilitated by developing property-composition models, and the strategy of model development and application is reviewed. However, the large variability of waste compositions presents numerous additional challenges: insoluble solids and molten salts may segregate; foam may hinder heat transfer and slow down the process; molten salts may accumulate in container refractory walls; the glass on cooling may precipitate crystalline phases. These problems need targeted exploratory research. Examples of specific problems and their possible solutions are discussed.

  6. Organic tanks safety program FY96 waste aging studies

    SciTech Connect

    Camaioni, D.M.; Samuels, W.D.; Linehan, J.C.; Clauss, S.A.; Sharma, A.K.; Wahl, K.L.; Campbell, J.A.

    1996-10-01

    Uranium and plutonium production at the Hanford Site produced large quantities of radioactive by-products and contaminated process chemicals, which are stored in underground tanks awaiting treatment and disposal. Having been made strongly alkaline and then subjected to successive water evaporation campaigns to increase storage capacity, the wastes now exist in the physical forms of salt cakes, metal oxide sludges, and partially saturated aqueous brine solutions. The tanks that contain organic process chemicals mixed with nitrate/nitrite salt wastes may be at risk for fuel- nitrate combustion accidents. The purpose of the Waste Aging Task is to elucidate how chemical and radiological processes will have aged or degraded the organic compounds stored in the tanks. Ultimately, the task seeks to develop quantitative measures of how aging changes the energetic properties of the wastes. This information will directly support efforts to evaluate the hazard as well as to develop potential control and mitigation strategies.

  7. Advanced waste management technology evaluation

    NASA Technical Reports Server (NTRS)

    Couch, H.; Birbara, P.

    1996-01-01

    The purpose of this program is to evaluate the feasibility of steam reforming spacecraft wastes into simple recyclable inorganic salts, carbon dioxide and water. Model waste compounds included cellulose, urea, methionine, Igapon TC-42, and high density polyethylenes. These are compounds found in urine, feces, hygiene water, etc. The gasification and steam reforming process used the addition of heat and low quantities of oxygen to oxidize and reduce the model compounds.The studied reactions were aimed at recovery of inorganic residues that can be recycled into a closed biologic system. Results indicate that even at very low concentrations of oxygen (less than 3%) the formation of a carbonaceous residue was suppressed. The use of a nickel/cobalt reforming catalyst at reaction temperature of 1600 degrees yielded an efficient destruction of the organic effluents, including methane and ammonia. Additionally, the reforming process with nickel/cobalt catalyst diminished the noxious odors associated with butyric acid, methionine and plastics.

  8. Waste incineration and heat recovery

    SciTech Connect

    Ward, J.E.; Ting, A.P.

    1982-02-01

    A recent project includes the incineration of organic and aqueous waste streams. The waste streams represent a gross heating valyue of 26 million kcal/h (100 million Btu/h). A system designed to generate approximately 36,000 kg/h (79,366 lb/h) of 1138 kPa (165 psig) steam for plant use, would save $5.5 million a year if the steam produced is valued at $20/1000 kg ($9/1000 lb). The presence of certain components, such as inorganic salts, chlorinated and nitrogen-containing organic compounds, sulfur compounds, and phospho-organics, is critical to the design, and each deserves special considerations, as described in this paper.

  9. Blending of Radioactive Salt Solutions in Million Gallon Tanks - 13002

    SciTech Connect

    Leishear, Robert A.; Lee, Si Y.; Fowley, Mark D.; Poirier, Michael R. [Savannah River National Laboratory, Aiken. S.C., 29808 (United States)] [Savannah River National Laboratory, Aiken. S.C., 29808 (United States)

    2013-07-01

    Research was completed at Savannah River National Laboratory (SRNL) to investigate processes related to the blending of radioactive, liquid waste, salt solutions in 4920 cubic meter, 25.9 meter diameter storage tanks. One process was the blending of large salt solution batches (up to 1135 - 3028 cubic meters), using submerged centrifugal pumps. A second process was the disturbance of a settled layer of solids, or sludge, on the tank bottom. And a third investigated process was the settling rate of sludge solids if suspended into slurries by the blending pump. To investigate these processes, experiments, CFD models (computational fluid dynamics), and theory were applied. Experiments were performed using simulated, non-radioactive, salt solutions referred to as supernates, and a layer of settled solids referred to as sludge. Blending experiments were performed in a 2.44 meter diameter pilot scale tank, and flow rate measurements and settling tests were performed at both pilot scale and full scale. A summary of the research is presented here to demonstrate the adage that, 'One good experiment fixes a lot of good theory'. Experimental testing was required to benchmark CFD models, or the models would have been incorrectly used. In fact, CFD safety factors were established by this research to predict full-scale blending performance. CFD models were used to determine pump design requirements, predict blending times, and cut costs several million dollars by reducing the number of required blending pumps. This research contributed to DOE missions to permanently close the remaining 47 of 51 SRS waste storage tanks. (authors)

  10. Dry Creek salt dome, Mississippi Interior Salt basin

    SciTech Connect

    Montgomery, S.L.; Ericksen, R.L.

    1997-03-01

    Recent drilling of salt dome flanks in the Mississippi Salt basin has resulted in important new discoveries and the opening of a frontier play. This play is focused on gas/condensate reserves in several Cretaceous formations, most notably the Upper Cretaceous Eutaw and lower Tuscaloosa intervals and Lower Cretaceous Paluxy and Hosston formations. As many as eight domes have been drilled thus far; sandstones in the upper Hosston Formation comprise the primary target. Production has been as high as 3-5 Mcf and 500-1200 bbl of condensate per day, with estimated ultimate reserves in the range of 0.2 to 1.5 MBOE (million barrels oil equivalent) per well. As typified by discovery at Dry Creek salt dome, traps are related to faulting, unconformities, and updip loss of permeability. Previous drilling at Dry Creek, and in the basin generally, avoided the flank areas of most domes, due to geologic models that predicted latestage (Tertiary) piercement and breached accumulations. Recent data from Dry Creek and other productive domes suggest that growth was episodic and that piercement of Tertiary strata did not affect deeper reservoirs charged with hydrocarbons in the Late Cretaceous.

  11. Quaternary subrosion and transformation of Stassfurt potash seam (Zechstein 2) at top of Gorleben salt dome, Federal Republic of Germany

    SciTech Connect

    Bornemann, O.; Fischbeck, R.

    1989-03-01

    The Gorleben salt dome is located in the eastern part of Lower Saxony in northern Germany. The dome consists of salt layers of cycles 2, 3, and 4 (z2-z4) of the Zechstein. Above-ground studies have been conducted since 1979 to determine whether the Gorleben salt dome is suited for the permanent disposal of radioactive waste. During the Elster glacial stage, the Gorleben salt dome was covered by up to 1000 m-thick ice. The meltwater eroded up to 300-m deep runoff channels into the rock beneath the glacier. One of these Quaternary channels runs across the salt dome; locally, the channel cuts the cap rock down to the rock salt. The Stassfurt potash seam cuts across at the bottom of this channel under Quaternary sediments. Between 90 and 170 m below the top of the salt dome, the potash seam was encountered in different stages of transformation. The sequence from bottom to top was as follows: unchanged carnallitic rock, followed by a zone of kainitic rock, ending with a potash-free halitic rock containing clastic material from the overlying sediments. Diagenesis of the clastic Elsterian sediments interbedded in the rock salt blocked further migration of solutions into the potash seam. No evidence has been found for further subrosion of the potash seam since the Elsterian (i.e., the last 300,000 years).

  12. Community solar salt production in Goa, India

    PubMed Central

    2012-01-01

    Traditional salt farming in Goa, India has been practised for the past 1,500?years by a few communities. Goa’s riverine estuaries, easy access to sea water and favourable climatic conditions makes salt production attractive during summer. Salt produced through this natural evaporation process also played an important role in the economy of Goa even during the Portuguese rule as salt was the chief export commodity. In the past there were 36 villages involved in salt production, which is now reduced to 9. Low income, lack of skilled labour, competition from industrially produced salt, losses incurred on the yearly damage of embankments are the major reasons responsible for the reduction in the number of salt pans. Salt pans (Mithagar or Mithache agor) form a part of the reclaimed waterlogged khazan lands, which are also utilised for aquaculture, pisciculture and agriculture. Salt pans in Goa experience three phases namely, the ceased phase during monsoon period of June to October, preparatory phase from December to January, and salt harvesting phase, from February to June. After the monsoons, the salt pans are prepared manually for salt production. During high tide, an influx of sea water occurs, which enters the reservoir pans through sluice gates. The sea water after 1–2?days on attaining a salinity of approximately 5ºBé, is released into the evaporator pans and kept till it attains a salinity of 23 - 25ºBé. The brine is then released to crystallizer pans, where the salt crystallises out 25 - 27ºBé and is then harvested. Salt pans form a unique ecosystem where succession of different organisms with varying environmental conditions occurs. Organisms ranging from bacteria, archaea to fungi, algae, etc., are known to colonise salt pans and may influence the quality of salt produced. The aim of this review is to describe salt farming in Goa’s history, importance of salt production as a community activity, traditional method of salt production and the biota associated with salt pans. PMID:23198813

  13. Waste isolation pilot plant disposal room model

    SciTech Connect

    Butcher, B.M.

    1997-08-01

    This paper describes development of the conceptual and mathematical models for the part of the Waste Isolation Pilot Plant (WIPP) repository performance assessment that is concerned with what happens to the waste over long times after the repository is decommissioned. These models, collectively referred to as the {open_quotes}Disposal Room Model,{close_quotes} describe the repository closure process during which deformation of the surrounding salt consolidates the waste. First, the relationship of repository closure to demonstration of compliance with the Environmental Protection Agency (EPA) standard (40 CFR 191 Appendix C) and how sensitive performance results are to it are examined. Next, a detailed description is provided of the elements of the disposal region, and properties selected for the salt, waste, and other potential disposal features such as backfill. Included in the discussion is an explanation of how the various models were developed over time. Other aspects of closure analysis, such as the waste flow model and method of analysis, are also described. Finally, the closure predictions used in the final performance assessment analysis for the WIPP Compliance Certification Application are summarized.

  14. Nuclear waste

    SciTech Connect

    Not Available

    1991-09-01

    Radioactive waste is mounting at U.S. nuclear power plants at a rate of more than 2,000 metric tons a year. Pursuant to statute and anticipating that a geologic repository would be available in 1998, the Department of Energy (DOE) entered into disposal contracts with nuclear utilities. Now, however, DOE does not expect the repository to be ready before 2010. For this reason, DOE does not want to develop a facility for monitored retrievable storage (MRS) by 1998. This book is concerned about how best to store the waste until a repository is available, congressional requesters asked GAO to review the alternatives of continued storage at utilities' reactor sites or transferring waste to an MRS facility, GAO assessed the likelihood of an MRSA facility operating by 1998, legal implications if DOE is not able to take delivery of wastes in 1998, propriety of using the Nuclear Waste Fund-from which DOE's waste program costs are paid-to pay utilities for on-site storage capacity added after 1998, ability of utilities to store their waste on-site until a repository is operating, and relative costs and safety of the two storage alternatives.

  15. Waste processing

    SciTech Connect

    Heidenreich, P.; Kearley, J.; Kenny, G.

    1988-07-01

    The benefits of ridding solid waste steams of paper, bottles, cans and heavy metal products are well known, smaller, safer and less expensive landfills, less toxic incinerator emissions and ashes, and conservation of resources. A fourth advantage - increased BTU values for waste-to-energy facilities - is less know, but may be the boost that both waste-to-energy and resource recovery industries are seeking. Results from DOE-sponsored research at the Nashville Thermal Transfer Corporations shows BTU increases of up to 20% for waste stripped of aluminum, glass and heavy metals. The state of New Jersey is looking into possible BTU decreases when recyclable paper is taken from the waste stream, a common concern within the waste-to-energy community. All but eight states have some type of curbside recycling program, though some are as minimal as litter control bills and used oil recycling. Discarding litter and oil, 32 states have recycling programs. Nine states have ''bottle bill'' legislation, while 34 have federally funded programs. Only three states - New Jersey, Connectictut and Rhode Island - have mandated waste reduction. These programs have boosted the materials recycling industry.

  16. Estimating Rheological Parameters of Anhydrite from Folded Evaporite sequences: Implications for Internal Dynamics of Salt Structure

    NASA Astrophysics Data System (ADS)

    Adamuszek, Marta; Dabrowski, Marcin; Schmalholz, Stefan M.; Urai, Janos L.; Raith, Alexander

    2015-04-01

    Salt structures have been identified as a potential target for hydrocarbon, CO2, or radioactive waste storage. The most suitable locations for magazines are considered in the thick and relatively homogeneous rock salt layers. However, salt structures often consist of the evaporite sequence including rock salt intercalated with other rock types e.g.: anhydrite, gypsum, potassium and magnesium salt, calcite, dolomite, or shale. The presence of such heterogeneities causes a serious disturbance in the structure management. Detailed analysis of the internal architecture and internal dynamics of the salt structure are crucial for evaluating them as suitable repositories and also their long-term stability. The goal of this study is to analyse the influence of the presence of anhydrite layers on the internal dynamics of salt structures. Anhydrite is a common rock in evaporite sequences. Its physical and mechanical properties strongly differ from the properties of rock salt. The density of anhydrite is much higher than the density of salt, thus anhydrite is likely to sink in salt causing the disturbance of the surrounding structures. This suggestion was the starting point to the discussion about the long-term stability of the magazines in salt structures [1]. However, the other important parameter that has to be taken into account is the viscosity of anhydrite. The high viscosity ratio between salt and anhydrite can restrain the layer from sinking. The rheological behaviour of anhydrite has been studied in laboratory experiments [2], but the results only provide information about the short-term behaviour. The long-term behaviour can be best predicted using indirect methods e.g. based on the analysis of natural structures that developed over geological time scale. One of the most promising are fold structures, the shape of which is very sensitive to the rheological parameters of the deforming materials. Folds can develop in mechanically stratified materials during layer parallel shortening. Mechanical model have been developed to rigorously correlate rheological properties of rock to the fold shape. A quantitative fold shape analysis combined with the folding theory allows deciphering the rock rheology. In this study, we analyse anhydrite layers embedded in the rock salt from the Upper Permian Zechstein salt formation from Dutch offshore. The anhydrite layers are common intercalation in the sequence. Their thickness varies between few millimetres up to hundred meters. The layers are strongly deformed often forming fold structures, which can be observed on a wide range of scales: in core samples, mine galleries, and also in the seismic sections. For our analysis, we select single layer fold trains. Quantitative fold shape analysis is carried out using Fold Geometry Toolbox [3], which allows deciphering the viscosity ratio between anhydrite and salt. The results indicate that anhydrite layer is ca. 10 to 30 times more viscous than the embedding salt. Further, we use the estimated rheological parameters of anhydrite in the numerical analysis of the internal salt dynamics. We solve an incompressible Stokes equation in the presence of the gravity using the finite element method solver MILAMIN [4]. We show that the presence of denser and more viscous anhydrite layers in the tectonically stable regime is insignificant for the internal stability of the salt structures. [1] Chemia, Z., Koyi, H., Schmeling, H. 2008. Numerical modelling of rise and fall of a dense layer in salt diapirs. Geophysical Journal International, 172: 798-816. [2] Muller, W.H., Briegel, U. 1978. The rheological behaviour of polycrystalline Anhydrite. Eclogae Geol. Helv, 71(2): 397-407 [3] Adamuszek M., Schmid D.W., Dabrowski M. 2011. Fold geometry toolbox - Automated determination of fold shape, shortening, and material properties, Journal of Structural Geology, 33: 1406-1416. [4] Dabrowski, M., Krotkiewski, M., and Schmid, D. W. 2008. MILAMIN: MATLAB-based finite element method solver for large problems. Geochemistry Geophysics Geosystems, 9: Q04030.

  17. The Mixed Waste Management Facility monthly report August 1995

    SciTech Connect

    Streit, R.D.

    1995-09-01

    The project is concerned with the design of a mixed waste facility to prepare solid and liquid wastes for processing by electrochemical oxidation, molten salt oxidation, wet oxidation, or UV photolysis. The facility will have a receiving and shipping unit, preparation and processing units, off-gas scrubbing, analytical services, water treatment, and transport and storage facilities. This monthly report give task summaries for 25 tasks which are part of the overall design effort.

  18. Properties of Saltstone Prepared Containing H-Canyon Waste

    Microsoft Academic Search

    Cozzi

    2005-01-01

    Saltstone slurries were prepared from solutions made from H-Canyon waste and evaluated for processing properties. Salt solutions prepared with a 1:1 ratio of Tank 50H simulant and H-Canyon blended waste produced slurries that met the processing requirements in Table 2 of the Task Technical and Quality Assurance Plan (TTQAP). Additions of set retarder and antifoam were necessary to meet these

  19. Biological production of ethanol from waste gases with Clostridium ljungdahlii

    DOEpatents

    Gaddy, James L. (Fayetteville, AR)

    2000-01-01

    A method and apparatus for converting waste gases from industrial processes such as oil refining, carbon black, coke, ammonia, and methanol production, into useful products is disclosed. The method includes introducing the waste gases into a bioreactor where they are fermented to various product, such as organic acids, alcohols H.sub.2, SCP, and salts of organic acids by anaerobic bacteria within the bioreactor. These valuable end products are then recovered, separated and purified.

  20. Polyethylene waste form: Evaluation of explosion and fire hazards

    Microsoft Academic Search

    A. Block-Bolten; D. Olson; P. A. Persson; F. Sandstrom

    1991-01-01

    A Proposed polyethylene waste form consists of a hot-extruded, non-porous mix of equal weights of polyethylene and granular sodium nitrate, slightly contaminated with heavy metal salts. The experiments and theoretical analysis detailed in this report were done to evaluate the risks for self-accelerating thermal decomposition, explosion, and detonation of polyethylene mixed with sodium nitrate. The study included the proposed waste

  1. Bile salts as semiochemicals in fish

    USGS Publications Warehouse

    Buchinger, Tyler J.; Li, Weiming; Johnson, Nicholas S.

    2014-01-01

    Bile salts are potent olfactory stimuli in fishes; however the biological functions driving such sensitivity remain poorly understood. We provide an integrative review of bile salts as semiochemicals in fish. First, we present characteristics of bile salt structure, metabolism, and function that are particularly relevant to chemical communication. Bile salts display a systematic pattern of structural variation across taxa, are efficiently synthesized, and are stable in the environment. Bile salts are released into the water via the intestine, urinary tract, or gills, and are highly water soluble. Second, we consider the potential role of bile salts as semiochemicals in the contexts of detecting nearby fish, foraging, assessing risk, migrating, and spawning. Lastly, we suggest future studies on bile salts as semiochemicals further characterize release into the environment, behavioral responses by receivers, and directly test the biological contexts underlying olfactory sensitivity.

  2. Desulphurization Characteristics of Waste Compound Desulfurizer

    Microsoft Academic Search

    Zheng Bin; Ji Lixia

    2010-01-01

    Desulphurization characteristics of waste compound desulfurizers were studied by means of gas analyzer and high temperature tube reactor. When red mud is added into white clay, carbide slag and limestone, the sulfur capture abilities of them increase at 900°C. Their best mixing ratios are 2:8, 2:8 and 3:7 respectively. When salt slurry is added into carbide slag, the sulfur capture

  3. Evaluation of potential crushed-salt constitutive models

    SciTech Connect

    Callahan, G.D.; Loken, M.C.; Sambeek, L.L. Van; Chen, R.; Pfeifle, T.W.; Nieland, J.D. [RE/SPEC Inc., Rapid City, SD (United States); Hansen, F.D. [Sandia National Labs., Albuquerque, NM (United States). Repository Isolation Systems Dept.

    1995-12-01

    Constitutive models describing the deformation of crushed salt are presented in this report. Ten constitutive models with potential to describe the phenomenological and micromechanical processes for crushed salt were selected from a literature search. Three of these ten constitutive models, termed Sjaardema-Krieg, Zeuch, and Spiers models, were adopted as candidate constitutive models. The candidate constitutive models were generalized in a consistent manner to three-dimensional states of stress and modified to include the effects of temperature, grain size, and moisture content. A database including hydrostatic consolidation and shear consolidation tests conducted on Waste Isolation Pilot Plant and southeastern New Mexico salt was used to determine material parameters for the candidate constitutive models. Nonlinear least-squares model fitting to data from the hydrostatic consolidation tests, the shear consolidation tests, and a combination of the shear and hydrostatic tests produces three sets of material parameter values for the candidate models. The change in material parameter values from test group to test group indicates the empirical nature of the models. To evaluate the predictive capability of the candidate models, each parameter value set was used to predict each of the tests in the database. Based on the fitting statistics and the ability of the models to predict the test data, the Spiers model appeared to perform slightly better than the other two candidate models. The work reported here is a first-of-its kind evaluation of constitutive models for reconsolidation of crushed salt. Questions remain to be answered. Deficiencies in models and databases are identified and recommendations for future work are made. 85 refs.

  4. Renal arteriolar injury by salt intake contributes to salt memory for the development of hypertension.

    PubMed

    Oguchi, Hideyo; Sasamura, Hiroyuki; Shinoda, Kazunobu; Morita, Shinya; Kono, Hidaka; Nakagawa, Ken; Ishiguro, Kimiko; Hayashi, Kaori; Nakamura, Mari; Azegami, Tatsuhiko; Oya, Mototsugu; Itoh, Hiroshi

    2014-10-01

    The role of salt intake in the development of hypertension is prominent, but its mechanism has not been fully elucidated. Our aim was to examine the effect of transient salt intake during the prehypertensive period in hypertensive model animals. Dahl salt-sensitive rats and spontaneously hypertensive rats were fed from 6 to 14 weeks with low-salt (0.12% NaCl), normal-salt (0.8% NaCl), high-salt (7% NaCl), or high-sodium/normal-chloride diet and returned to normal-salt diet for 3 months. Rats in the high-salt group saw elevations in blood pressure (BP) not only during the treatment period but also for the 3 months after returning to normal-salt diet. We named this phenomenon salt memory. Renal arteriolar injury was found in the high-salt group at the end of experiment. Dahl salt-sensitive rats were fed from 6 to 14 weeks with high-salt diet with angiotensin receptor blocker, vasodilator, calcium channel blocker, and calcium channel blocker+angiotensin receptor blocker and returned to normal-salt diet. Although BP was suppressed to control levels by vasodilator or calcium channel blocker, elevated renal angiotensin II and renal arteriolar injury were observed, and salt memory did not disappear because of sustained renal arteriolar injury. Calcium channel blocker+angiotensin receptor blocker suppressed renal arteriolar injury, resulting in the disappearance of salt memory. Cross-transplantation of kidneys from Dahl salt-sensitive rats on high salt to control rats caused increase of BP, whereas control kidneys caused reduction in BP of hypertensive rats, inducing the central role of the kidney. These results suggest that renal arteriolar injury through BP and renal angiotensin II elevation plays important roles in the development of salt memory for hypertension. PMID:24980670

  5. Beryllium Interactions in Molten Salts

    SciTech Connect

    G. S. Smolik; M. F. Simpson; P. J. Pinhero; M. Hara; Y. Hatano; R. A. Anderl; J. P. Sharpe; T. Terai; S. Tanaka; D. A. Petti; D.-K. Sze

    2006-01-01

    Molten flibe (2LiF·BeF2) is a candidate as a cooling and tritium breeding media for future fusion power plants. Neutron interactions with the salt will produce tritium and release excess free fluorine ions. Beryllium metal has been demonstrated as an effective redox control agent to prevent free fluorine, or HF species, from reacting with structural metal components. The extent and rate of beryllium solubility in a pot design experiments to suppress continuously supplied hydrogen fluoride gas has been measured and modeled[ ]. This paper presents evidence of beryllium loss from specimens, a dependence of the loss upon bi-metal coupling, i.e., galvanic effect, and the partitioning of the beryllium to the salt and container materials. Various posttest investigative methods, viz., scanning electron microscopy (SEM), Auger electron spectroscopy (AES) and x-ray photoelectron spectroscopy (XPS) were used to explore this behavior.

  6. Salt: Up Close and Personal

    NSDL National Science Digital Library

    In this lesson, students will view salt under varied magnifications and begin to construct the understanding that materials may be composed of parts that are too small to be seen without magnification. They will observe salt with the naked eye, and then under a hand lens, microscope, and the electron microscope (the electron image is via the Internet). In order to complete this lesson, it is important that students have previous experience working with hand lenses and microscopes. This sort of detailed observation provides an opportunity for students to keep written records of their discoveries and analyze the collected data. As part of the process of recording and discussing observations, students will be required to make predictions and note differences.

  7. Deliberate overdose with Epsom salts.

    PubMed

    Milne, Helen; Dean, Pamela; Hughes, Martin

    2009-01-01

    Epsom salts contains the active compound magnesium sulfate and is used most commonly as a laxative. There are potential serious toxic effects, including cardiac arrest, when the serum concentration rises above therapeutic values. We present a case of deliberate self poisoning with a large quantity of Epsom salts, resulting in a toxic serum magnesium concentration of 9.7 mmol/l (0.70-1.0 mmol/l). Clinical features included limb weakness, vomiting and confusion, with a subsequent rapid deterioration in level of consciousness and bradydysrhythmia. There was no significant response to calcium gluconate, so haemodialysis was urgently arranged. The patient made a full recovery. Hypermagnesaemia is unusual in patients with normal renal function. Although clinical severity does not always correlate with serum magnesium values, risk of cardiac arrest occurs with concentrations >6 mmol/l. Initial treatment is supportive. Dialysis should be considered when life threatening features or renal impairment are present. PMID:21686733

  8. Innovative technologies for managing oil field waste.

    SciTech Connect

    Veil, J. A.; Environmental Assessment

    2003-09-01

    Each year, the oil industry generates millions of barrels of wastes that need to be properly managed. For many years, most oil field wastes were disposed of at a significant cost. However, over the past decade, the industry has developed many processes and technologies to minimize the generation of wastes and to more safely and economically dispose of the waste that is generated. Many companies follow a three-tiered waste management approach. First, companies try to minimize waste generation when possible. Next, they try to find ways to reuse or recycle the wastes that are generated. Finally, the wastes that cannot be reused or recycled must be disposed of. Argonne National Laboratory (Argonne) has evaluated the feasibility of various oil field waste management technologies for the U.S. Department of Energy. This paper describes four of the technologies Argonne has reviewed. In the area of waste minimization, the industry has developed synthetic-based drilling muds (SBMs) that have the desired drilling properties of oil-based muds without the accompanying adverse environmental impacts. Use of SBMs avoids significant air pollution from work boats hauling offshore cuttings to shore for disposal and provides more efficient drilling than can be achieved with water-based muds. Downhole oil/water separators have been developed to separate produced water from oil at the bottom of wells. The produced water is directly injected to an underground formation without ever being lifted to the surface, thereby avoiding potential for groundwater or soil contamination. In the area of reuse/recycle, Argonne has worked with Southeastern Louisiana University and industry to develop a process to use treated drill cuttings to restore wetlands in coastal Louisiana. Finally, in an example of treatment and disposal, Argonne has conducted a series of four baseline studies to characterize the use of salt caverns for safe and economic disposal of oil field wastes.

  9. Concentrate This! Sugar or Salt...

    NSDL National Science Digital Library

    2013-03-20

    Students investigate the property dependence between concentrations and boiling point. First, they investigate the boiling point of various liquid solutions. Then they analyze data collected from the entire class to generate two boiling point curves, one for salt solutions and one for sugar solutions. Finally, students use the data they have analyzed to design cost-effective solutions with particular boiling points---similar to the everyday work of chemical engineers.

  10. Salt of the Early Earth

    NSDL National Science Digital Library

    Mullen, Leslie

    This astrobiology news article analyzes the role salt played in the evolution of life on Earth. It explains why scientists have long assumed that life originated in the sea and describes the history of water on Earth in relation to the origin of life. Leading scientists contribute information about the significance of anaerobes, halophiles, methanogens, and the depositional environments of sedimentary rocks that hold Precambrian microfossils. They also suggest that we should extend our search to Mars.

  11. Concentrate This! Sugar or Salt...

    NSDL National Science Digital Library

    CREAM GK-12 Program, Engineering Education Research Center, College of Engineering and Architecture,

    Students investigate the property dependence between concentrations and boiling point. In section 1, students first investigate the boiling point of various liquid solutions. In section 2, they analyze data collected by the entire class to generate two boiling point curves, one for salt solutions and one for sugar solutions. Finally, in section 3, students use the data they have analyzed to determine how to create a solution that has a particular boiling point and is a cost-effective design.

  12. Tetrazolium salts: a consumer's guide

    Microsoft Academic Search

    F. P. Altman

    1976-01-01

    Synopsis  The purities of seven tetrazolium salts, obtained from various commercial sources, have been assessed by thin layer chromatography, relative extinction coefficients, and melting points. MTT and INT were largely homogeneous on thin layer chromatography, although significant variations occurred in the melting point behaviour. All the samples of TT examined were contaminated to a small extent with non-tetrazolium u.v.-absorbing material. TNBT

  13. Salt of the Early Earth

    NSDL National Science Digital Library

    2002-06-11

    This astrobiology news article analyzes the role salt played in the evolution of life on Earth. It explains why scientists have long assumed that life originated in the sea and describes the history of water on Earth in relation to the origin of life. Leading scientists contribute information about the significance of anaerobes, halophiles, methanogens, and the depositional environments of sedimentary rocks that hold Precambrian microfossils. They also suggest that we should extend our search to Mars.

  14. Salt stains from evaporating droplets

    PubMed Central

    Shahidzadeh, Noushine; Schut, Marthe F. L.; Desarnaud, Julie; Prat, Marc; Bonn, Daniel

    2015-01-01

    The study of the behavior of sessile droplets on solid substrates is not only associated with common everyday phenomena, such as the coffee stain effect, limescale deposits on our bathroom walls , but also very important in many applications such as purification of pharmaceuticals, de-icing of airplanes, inkjet printing and coating applications. In many of these processes, a phase change happens within the drop because of solvent evaporation, temperature changes or chemical reactions, which consequently lead to liquid to solid transitions in the droplets. Here we show that crystallization patterns of evaporating of water drops containing dissolved salts are different from the stains reported for evaporating colloidal suspensions. This happens because during the solvent evaporation, the salts crystallize and grow during the drying. Our results show that the patterns of the resulting salt crystal stains are mainly governed by wetting properties of the emerging crystal as well as the pathway of nucleation and growth, and are independent of the evaporation rate and thermal conductivity of the substrates. PMID:26012481

  15. Salt stains from evaporating droplets.

    PubMed

    Shahidzadeh, Noushine; Schut, Marthe F L; Desarnaud, Julie; Prat, Marc; Bonn, Daniel

    2015-01-01

    The study of the behavior of sessile droplets on solid substrates is not only associated with common everyday phenomena, such as the coffee stain effect, limescale deposits on our bathroom walls , but also very important in many applications such as purification of pharmaceuticals, de-icing of airplanes, inkjet printing and coating applications. In many of these processes, a phase change happens within the drop because of solvent evaporation, temperature changes or chemical reactions, which consequently lead to liquid to solid transitions in the droplets. Here we show that crystallization patterns of evaporating of water drops containing dissolved salts are different from the stains reported for evaporating colloidal suspensions. This happens because during the solvent evaporation, the salts crystallize and grow during the drying. Our results show that the patterns of the resulting salt crystal stains are mainly governed by wetting properties of the emerging crystal as well as the pathway of nucleation and growth, and are independent of the evaporation rate and thermal conductivity of the substrates. PMID:26012481

  16. Selenium Waste

    NSDL National Science Digital Library

    This site provides general information about selenium including its occurrence, industrial applications, toxicology, and regulations and practices regarding industrial waste disposal. The site also features links to more detailed information about each of these topics.

  17. Treatment of high-level wastes from the IFR fuel cycle

    SciTech Connect

    Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

    1992-08-01

    The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

  18. Treatment of high-level wastes from the IFR fuel cycle

    SciTech Connect

    Johnson, T.R.; Lewis, M.A.; Newman, A.E.; Laidler, J.J.

    1992-01-01

    The Integral Fast Reactor (IFR) is being developed as a future commercial power source that promises to have important advantages over present reactors, including improved resource conservation and waste management. The spent metal alloy fuels from an IFR will be processed in an electrochemical cell operating at 500{degree}C with a molten chloride salt electrolyte and cadmium metal anode. After the actinides have been recovered from several batches of core and blanket fuels, the salt cadmium in this electrorefiner will be treated to separate fission products from residual transuranic elements. This treatment produces a waste salt that contains the alkali metal, alkaline earth, and halide fission products; some of the rare earths; and less than 100 nCi/g of alpha activity. The treated metal wastes contain the rest of the fission products (except T, Kr, and Xe) small amounts of uranium, and only trace amounts of transuranic elements. The current concept for the salt waste form is an aluminosilicate matrix, and the concept for the metal waste form is a corrosion-resistant metal alloy. The processes and equipment being developed to treat and immobilize the salt and metal wastes are described.

  19. Hazardous Waste

    NSDL National Science Digital Library

    Harris, Kathryn Louise.

    Given media attention to the US Navy's recent problems with the disposal of a large amount of napalm, an incendiary compound, this week's In the News examines the issue of hazardous waste and materials. The eight resources discussed provide information on various aspects of the topic. Due to the large number of companies specializing in the management and remediation of hazardous waste contamination, private firms will not be noted.

  20. I-NERI ANNUAL TECHNICAL PROGRESS REPORT: 2006-002-K, Separation of Fission Products from Molten LiCl-KCl Salt Used for Electrorefining of Metal Fuels

    SciTech Connect

    S. Frank

    2009-09-01

    An attractive alternative to the once-through disposal of electrorefiner salt is to selectively remove the active fission products from the salt and recycle the salt back to the electrorefiner (ER). This would allow salt reuse for some number of cycles before ultimate disposal of the salt in a ceramic waste form. Reuse of ER salt would, thus, greatly reduce the volume of ceramic waste produced during the pyroprocessing of spent nuclear fuel. This final portion of the joint I-NERI research project is to demonstrate the separation of fission products from molten ER salt by two methods previously selected during phase two (FY-08) of this project. The two methods selected were salt/zeolite contacting and rare-earth fission product precipitation by oxygen bubbling. The ER salt used in these tests came from the Mark-IV electrorefiner used to anodically dissolved driver fuel from the EBR-II reactor on the INL site. The tests were performed using the Hot Fuel Dissolution Apparatus (HFDA) located in the main cell of the Hot Fuels Examination Facility (HFEF) at the Materials and Fuels complex on the INL site. Results from these tests were evaluated during a joint meeting of KAERI and INL investigators to provide recommendations as to the future direction of fission product removal from electrorefiner salt that accumulate during spent fuel treatment. Additionally, work continued on kinetic measurements of surrogate quaternary salt systems to provide fundamental kinetics on the ion exchange system and to expand the equilibrium model system developed during the first two phases of this project. The specific objectives of the FY09 I-NERI research activities at the INL include the following: • Perform demonstration tests of the selected KAERI precipitation and INL salt/zeolite contacting processes for fission product removal using radioactive, fission product loaded ER salt • Continue kinetic studies of the quaternary Cs/Sr-LiCl-KCl system to determine the rate of ion exchange during the salt/zeolite contacting process • Compare the adsorption models to experimentally obtained, ER salt results • Evaluate results obtained from the oxygen precipitation and salt/zeolite ion exchange studies to determine the best processes for selective fission-product removal from electrorefiner salt.

  1. A strategy for resolving high-priority Hanford Site radioactive waste storage tank safety issues

    SciTech Connect

    Babad, H.; DeFigh-Price, C.; Fulton, J.C.

    1993-02-01

    High-activity radioactive waste has been stored in large underground storage tanks at the US Department of Energy`s (DOE) Hanford Site in Eastern Washington State since 1944. Since then, more than 227,000 m{sup 3} (60 Mgal) of waste have been accumulated in 177 tanks. These caustic wastes consist of many different chemicals. The waste forms include liquids, slurries, salt cakes, and sludges. A number of safety issues have been raised about these wastes, and resolution of these issues is a top priority of DOE. A Waste Tank Safety Program has been established to resolve these high-priority safety issues. This paper will deal with three of these issues. The issues described are the release of flammable vapors from single- and double-shell tanks, the existence of organic chemicals, and/or ferrocyanide ion-containing fuel-rich mixtures of nitrate and nitrite salts in single-shell tanks.

  2. Extension of the M-D model for treating stress drops in salt

    SciTech Connect

    Munson, D.E. [Sandia National Labs., Albuquerque, NM (United States); DeVries, K.L.; Fossum, A.F.; Callahan, G.D. [RE/SPEC Inc., Rapid City, SD (US)

    1993-07-01

    Development of the multimechanism deformation (M-D) constitutive model for steady state creep, which incorporates irreversible workhardening and recovery transient strains, was motivated by the need to predict very long term closures in underground rooms for radioactive waste repositories in salt. The multimechanism deformation model for the creep deformation of salt is extended to treat the response of salt to imposed stress drops. Stress drop tests produce a very distinctive behavior where both reversible elastic strain and reversible time dependent strain occur. These transient strains are negative compared to the positive transient strains produced by the normal creep workhardening and recovery processes. A simple micromechanical evolutionary process is defined to account for the accumulation of these reversible strains, and their subsequent release with decreases in stress. A number of experimental stress drop tests for various stress drop magnitudes and temperatures are adequately simulated with the model.

  3. Inhibition kinetics of salt-affected wetland for municipal wastewater treatment.

    PubMed

    Nitisoravut, Suwanchai; Klomjek, Pantip

    2005-11-01

    A mathematical model was developed in order to describe the system behavior and performance of a constructed wetland (CW) treatment under salt-affected conditions. The rate of biodegradation of organic wastes was modeled using the first-order kinetics while the effect of salt concentrations was accounted by growth inhibition. Experimental data were used to determine model constants of the mathematical model. The experimental units were planted with cattail (Typha angustifolia) and fed with spiked municipal wastewater. The hydraulic retention time varied from 12 to 120 h and wastewater conductivity was in the range of 4-32 mS/cm. At specified conditions the model was found to well describe the trend of the experimental data in terms of BOD removal with the Pearson correlation of 0.872. The model also permits construction of a nomograph which can be used to aid the design and prediction of CW treatment under salt-affected conditions. PMID:16236342

  4. Salt restrains maturation in subsalt plays

    SciTech Connect

    Mello, U.T. (Petroleo Brasileiro Inc., Rio de Janeiro (Brazil)); Anderson, R.N.; Karner, G.D. (Columbia Univ., Palisades, NY (United States). Lamont-Doherty Earth Observatory)

    1994-01-31

    The thermal positive anomaly associated with the top of salt diapirs has attracted significant attention in modifying the temperature structure and history of a sedimentary basin. Here the authors explore the role of the negative thermal anomaly beneath salt in modifying the maturation history of the source rocks in subsalt sediments. Organic matter maturation is believed to follow temperature dependent chemical reactions. Therefore, any temperature anomaly associated with salt masses affects the nearby maturation of potential source rocks. The level of maturity of source rocks close to salt diapirs will differ from that predicted based on regional trends. The impact of the thermal anomaly on a given point will depend on the duration and distance of the thermal anomaly to this particular point. Consequently, the maturation history of source rocks in salt basins is closely related to the salt motion history, implying that a transient thermal analysis is necessary to evaluate the sure impact on maturation of the thermal anomalies associated with salt diapirism. The paper describes vitrinite kinetics, salt in evolving basins, correlation of salt and temperature, salt dome heat drains, and restrained maturation.

  5. Savannah River Site Waste Removal Program - Past, Present and Future

    SciTech Connect

    Saldivar, E.

    2002-02-25

    The Savannah River Site has fifty-one high level waste tanks in various phases of operation and closure. These tanks were originally constructed to receive, store, and treat the high level waste (HLW) created in support of the missions assigned by the Department of Energy (DOE). The Federal Facilities Agreement (FFA) requires the high level waste to be removed from the tanks and stabilized into a final waste form. Additionally, closure of the tanks following waste removal must be completed. The SRS HLW System Plan identifies the interfaces of safe storage, waste removal, and stabilization of the high level waste and the schedule for the closure of each tank. HLW results from the dissolution of irradiated fuel components. Desired nuclear materials are recovered and the byproducts are neutralized with NaOH and sent to the High Level Waste Tank Farms at the SRS. The HLW process waste clarifies in the tanks as the sludge settles, resulting in a layer of dense sludge with salt supernate settling above the sludge. Salt supernate is concentrated via evaporation into saltcake and NaOH liquor. This paper discusses the history of SRS waste removal systems, recent waste removal experiences, and the challenges facing future removal operations to enhance efficiency and cost effectiveness. Specifically, topics will include the evolution and efficiency of systems used in the 1960's which required large volumes of water to current systems of large centrifugal slurry pumps, with significant supporting infrastructure and safety measures. Interactions of this equipment with the waste tank farm operations requirements will also be discussed. The cost and time improvements associated with these present-day systems is a primary focus for the HLW Program.

  6. Equipment and techniques for remote sampling of stored radioactive waste

    SciTech Connect

    Nance, T.A. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1996-11-20

    Several tools have been developed at the Savannah River Site (SRS) to remotely sample stored radioactive waste. These sampling tools have been developed to determine the chemical characteristics of the waste prior to processing. The processing of waste material varies according to the chemical characteristics of the waste, which change due to additions, settling, mixing, and chemical reactions during storage. Once the waste has been sampled to identify its characteristics, the chemical composition of the waste can then be altered if needed to prepare for processing. Various types of waste material in several types of containment must be sampled at SRS. Stored waste materials consist of liquids, floating organics, sludge, salt and solids. Waste is stored in four basic types of tanks with different means of access and interior obstructions. The waste tanks can only be accessed by small openings: access ports, risers and downcomers. Requirements for sampling depend on the type of tank being accessed, the waste within the tank, and the particular location in the tank desired for taking the sample. Sampling devices have been developed to sample all of the waste material forms found in the SRS tank farms. The fluid type samplers are capable of sampling surface liquid, subsurface liquid at varying depth, surface sludge, subsurface sludge, and floating organics. The solid type samplers are capable of sampling salt, sampling a solid layer on the bottom of the tank, and capturing a small solid mass on the tank bottom. The sampling devices are all designed to access the tanks through small access ports. The samplers are reusable and are designed to allow quick transfer of the samples to shielded packaging for transport, reducing the amount of radiation exposure to sampling personnel. The samplers weigh less than 100 lb. and are designed in sections to allow easy disassembly for storage and transport by personnel. (Abstract Truncated)

  7. RECENT PROGRESS IN DOE WASTE TANK CLOSURE

    SciTech Connect

    Langton, C

    2008-02-01

    The USDOE complex currently has over 330 underground storage tanks that have been used to process and store radioactive waste generated from the production of weapons materials. These tanks contain over 380 million liters of high-level and low-level radioactive waste. The waste consists of radioactively contaminated sludge, supernate, salt cake or calcine. Most of the waste exists at four USDOE locations, the Hanford Site, the Savannah River Site, the Idaho Nuclear Technology and Engineering Center and the West Valley Demonstration Project. A summary of the DOE tank closure activities was first issued in 2001. Since then, regulatory changes have taken place that affect some of the sites and considerable progress has been made in closing tanks. This paper presents an overview of the current regulatory changes and drivers and a summary of the progress in tank closures at the various sites over the intervening six years. A number of areas are addressed including closure strategies, characterization of bulk waste and residual heel material, waste removal technologies for bulk waste, heel residuals and annuli, tank fill materials, closure system modeling and performance assessment programs, lessons learned, and external reviews.

  8. MUNICIPAL WASTE COMBUSTION ASSESSMENT: WASTE CO- FIRING

    EPA Science Inventory

    The report is an overview of waste co-firing and auxiliary fuel fired technology and identifies the extent to which co-firing and auxiliary fuel firing are practised. Waste co-firing is defined as the combustion of wastes (e. g., sewage sludge, medical waste, wood waste, and agri...

  9. Effects of salt stress on root plasma membrane characteristics of salt-tolerant and salt-sensitive buffalograss clones

    Microsoft Academic Search

    Hong Lin; Lin Wu

    1996-01-01

    To test the hypothesis that differences in plasma membrane chemical characters exist between a salt-tolerant and a salt-sensitive buffalograss clone, plasma membrane H+-ATPase activity, membrane phospholipid composition, and corresponding fatty acyl chains were studied for root plasma membrane of two buffalograss (Buchloe dactyloides (Nutt.)) clones. Salt stress caused greater reductions of plasma membrane H+-ATPase activity and total plasma membrane protein

  10. Regeneration of waste chemicals from liquid redox processes

    Microsoft Academic Search

    John A. Ciriacks; James F. Lafond

    1991-01-01

    To avoid the increasingly costly disposal of the waste stream (blowdown) from liquid redox processes used to clean hydrogen sulfide form gases, a reductive burning recovery (RBR) process has been developed. The RBR system concentrates spent chemicals which are primarily sodium thiosulfate and sodium sulfate. The spent chemicals are then thermally destroyed in a reactor. The regenerated salts flow from

  11. Occupational Exposure of Veterinarians to Waste Anesthetic Gases

    Microsoft Academic Search

    David Lionel Potts; Bobby F. Craft

    1988-01-01

    An evaluation of anesthetic waste gas exposures was conducted in small private practice animal clinics throughout the Salt Lake Valley. The two most frequently used anesthetic gases, methoxyflurane and halothane, were chosen to be studied. Exposures during 38 surgeries were studied in a total of 10 facilities involving 13 veterinarians. Veterinarian breathing zones were sampled on a real-time basis with

  12. Mass Wasting

    NSDL National Science Digital Library

    First, Professor Stephen Nelson at Tulane University provides a straightforward description of mass wasting and recent disasters around the world (1). Visitors can find helpful illustrations of slumps and rock slides as well as a chart depicting the different processes that occur with varying velocities and water content. The second website, provided by Pamela Gore at Georgia Perimeter College, presents the factors involved with mass wasting and mass wasting processes (2). Visitors can find excellent real-life images of creep, rock slides, and talus slopes. Next, North Dakota State University illustrates creep, earthflow, slope failure, and slumps (3). The website furnishes images of mass wasting processes and explains the physical characteristics of the landscape. Fourth, the California State University at Long Beach discusses the causes, prevention, and types of mass wasting (4). Visitors can learn about the mass wasting disasters that occurred at La Conchita, Portuguese Bend, Mount Huascaran, Cable Canyon, and Vaiont Dam. Next, Professor Pidwirny at Okanagan University College offers an online text describing hillslope stability and mass movement (5). Students can learn about soil creep through a simple animation. The sixth website, developed by Natural Resources Canada, furnishes an interactive map of landslides in Canada (6). Users can select to view historic landslides, bedrock geology, surficial geology, and more. Next, the USGS offers information on the National Landslides Hazards Program, the National Landslide Information Center, and recent landslide events (7). Users can find a tutorial on landslides, real-time monitoring active of landslides, and related research projects. Lastly, at the Oswego State University of New York visitors can test their knowledge of mass wasting processes through a short quiz (8).

  13. Hazard Evaluation for a Salt Well Centrifugal Pump Design Using Service Water for Lubrication and Cooling

    SciTech Connect

    GRAMS, W.H.

    2000-10-09

    This report documents the results of a preliminary hazard analysis (PHA) covering the new salt well pump design. The PHA identified ten hazardous conditions mapped to four analyzed accidents: flammable gas deflagrations, fire in contaminated area, tank failure due to excessive loads, and waste transfer leaks. This document also presents the results of the control decision/allocation process. A backflow preventer and associated limiting condition were assigned.

  14. Fish Gills: Mechanisms of Salt Transfer in Fresh Water and Sea Water

    Microsoft Academic Search

    J. Maetz

    1971-01-01

    The teleostean gill is a multi-purpose organ, specialized for respiratory gas exchanges, clearance of waste products of nitrogenous metabolism and maintenance of acid-base and mineral balances. Structural studies reveal a complex epithelium. The 'chloride-cells are almost certainly the site of ion exchange in relation to salt balance. Functional studies show that the gill is responsible for the net absorption of

  15. Recovering distilled water and pure salt products from industrial wastewater: Three case studies

    SciTech Connect

    Schooley, K.E.; Ludlum, R.S. [Ionics RCC, Bellevue, WA (United States)

    1996-08-01

    Industry is slowly moving beyond the concept of zero liquid discharge toward the ideal of zero waste discharge. While zero liquid discharge means no liquids are discharged off site, the tons of dry solids removed from treated wastewater are often hauled to landfills off site if they cannot be stored at the plant. In recent years, some plants have opted to recover valuable salts and chemicals from wastewater to reduce the cost of hauling away useless mixed salts. Some plants even recover some of the cost of wastewater treatment by selling recovered salt. This paper will discuss three industrial sites where all wastewater is treated and recycled and most salts removed from the wastewater are turned into saleable products. The case studies will be a coal mine in Poland, where distilled water and sodium chloride are recovered from mine drainage; a uranium mine in the Czech Republic, where distilled water and ammonium alum are recovered from acid waste; and a power plant in New York, where distilled water and calcium chloride are recovered from scrubber blowdown.

  16. Summary report for the WIPP (Waste Isolation Pilot Plant) technology development program for isolation of radioactive waste

    Microsoft Academic Search

    L. D. Tyler; R. V. Matalucci; M. A. Molecke; D. E. Munson; E. J. Nowak; J. C. Stormont

    1988-01-01

    The technology experiments have been managed in three broad categories: Thermal\\/Structural Interactions (TSI), Plugging and Sealing Performance and Design (PandS), and Waste Package Performance (WPP). The history and major progress in each of these areas is summarized in this report. The TSI program has established the fact that the WIPP salt creep rate, and therefore closure of WIPP rooms, is

  17. Plasma 24,25-dihydroxyvitamin D concentration of Dahl salt-sensitive rats decreases during high salt intake

    Microsoft Academic Search

    Myrtle Thierry-Palmer; Teclemicael K. Tewolde; Camille Forté; Min Wang; Mohamed A. Bayorh; Nerimiah L. Emmett; Jolanda White; Keri Griffin

    2002-01-01

    Dahl salt-sensitive rats, but not salt-resistant rats, develop hypertension in response to high salt intake. We have previously shown an inverse relationship between plasma 25-hydroxyvitamin D (25-OHD) concentration and blood pressure of Dahl salt-sensitive rats during high salt intake. In this study, we report on the relationship between high salt intake and plasma 24,25-dihydroxyvitamin D (24,25-(OH)2D) concentration of Dahl salt-sensitive

  18. Advanced salt receiver for solar power towers

    SciTech Connect

    Romero, M.; Sanchez, M.; Barrera, G. [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Madrid (Spain). Instituto de Energias Renovables/Direccion de Tecnologia; Leon, J.; Sanchez, M. [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Tabernas (Spain). Plataforma Solar de Almeria

    1995-11-01

    Falling Film receivers constitute an alternative to the traditional Salt in Tube receivers, widely used and tested in the Central Receiver Systems. This report presents an innovative concept of Internal Film Receiver (IFR), in which a film made of a eutectic mixture of molten salts flows down the back side of a stainless steel panel. The installation with 550 kW nominal power, molten salt inlet temperature 300 C and outlet temperature 550 C is described.

  19. Determining Salt Tolerance Among Sunflower Genotypes 

    E-print Network

    Masor, Laura Lee

    2012-02-14

    quality water (Beltr?n, 1999). Shannon (1997) estimates that 7 irrigation can add up to 60 tons of salt to a hectare of land in one year. In poorly drained areas, shallow saline water tables can be created by crop irrigation (Maas and Grattan, 1999... tolerant and tolerant (Maas and Hoffman, 1976). Halophytic plants grow well in medium that contains high salt concentrations while glycophytes are not naturally adapted. Some dicotyledonous halophytic plants will only grow at high salt concentrations...

  20. International Society for Salt Lake Research

    NSDL National Science Digital Library

    Robert Jellison

    This site is home of the International Society for Salt Lake Research (ISSLR), an organization founded to establish effective liaison between persons interested in any aspect of inland saline waters, to encourage these interests, and to educate the public in the scientific use, management, and conservation of salt lakes. It includes: related news articles and journal publications; an open forum; international member directory; extensive bibliography; a list of salt lakes; and a list of related web sites.