Sample records for basins sludge treatment

  1. Maintenance and Operations study for K basins sludge treatment

    SciTech Connect (OSTI)

    WESTRA, A.G.

    1998-11-30T23:59:59.000Z

    This study evaluates maintenance and operating concepts for the chemical treatment of sludge from the 100 K Basins at Hanford. The sludge treatment equipment that will require remote operation or maintenance was identified. Then various maintenance and operating concepts used in the nuclear industry were evaluated for applicability to sludge treatment. A hot cell or cells is recommended as the best maintenance and operating concept for a sludge treatment facility.

  2. Hydrothermal Testing of K Basin Sludge and N Reactor Fuel at Sludge Treatment Project Operating Conditions

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.; Thornton, Brenda M.

    2007-03-30T23:59:59.000Z

    The Sludge Treatment Project (STP), managed for the U. S. DOE by Fluor Hanford (FH), was created to design and operate a process to eliminate uranium metal from K Basin sludge prior to packaging for Waste Isolation Pilot Plant (WIPP). The STP process uses high temperature liquid water to accelerate the reaction, produce uranium dioxide from the uranium metal, and safely discharge the hydrogen. Under nominal process conditions, the sludge will be heated in pressurized water at 185°C for as long as 72 hours to assure the complete reaction (corrosion) of up to 0.25-inch diameter uranium metal pieces. Under contract to FH, the Pacific Northwest National Laboratory (PNNL) conducted bench-scale testing of the STP hydrothermal process in November and December 2006. Five tests (~50 ml each) were conducted in sealed, un-agitated reaction vessels under the hydrothermal conditions (e.g., 7 to 72 h at 185°C) of the STP corrosion process using radioactive sludge samples collected from the K East Basin and particles/coupons of N Reactor fuel also taken from the K Basins. The tests were designed to evaluate and understand the chemical changes that may be occurring and the effects that any changes would have on sludge rheological properties. The tests were not designed to evaluate engineering aspects of the process. The hydrothermal treatment affected the chemical and physical properties of the sludge. In each test, significant uranium compound phase changes were identified, resulting from dehydration and chemical reduction reactions. Physical properties of the sludge were significantly altered from their initial, as-settled sludge values, including, shear strength, settled density, weight percent water, and gas retention.

  3. K East Basin sludge volume estimates for integrated water treatment system

    SciTech Connect (OSTI)

    Pitner, A.L.

    1998-08-12T23:59:59.000Z

    Estimates were made of the volume of sludge expected from Integrated Process Strategy (IPS) processing fuel elements and in the fuel storage canisters in K East Basin, These were based on visual observations of fuel element condition in the basin and laboratory measurements of canister sludge density. The estimates, made in early 1997, are reviewed and the basic assumptions used discussed.

  4. K Basins sludge removal temporary sludge storage tank system

    SciTech Connect (OSTI)

    Mclean, M.A.

    1997-06-12T23:59:59.000Z

    Shipment of sludge from the K Basins to a disposal site is now targeted for August 2000. The current path forward for sludge disposal is shipment to Tank AW-105 in the Tank Waste Remediation System (TWRS). Significant issues of the feasibility of this path exist primarily due to criticality concerns and the presence of polychlorinated biphenyls (PCBS) in the sludge at levels that trigger regulation under the Toxic Substance Control Act. Introduction of PCBs into the TWRS processes could potentially involve significant design and operational impacts to both the Spent Nuclear Fuel and TWRS projects if technical and regulatory issues related to PCB treatment cannot be satisfactorily resolved. Concerns of meeting the TWRS acceptance criteria have evolved such that new storage tanks for the K Basins sludge may be the best option for storage prior to vitrification of the sludge. A reconunendation for the final disposition of the sludge is scheduled for June 30, 1997. To support this decision process, this project was developed. This project provides a preconceptual design package including preconceptual designs and cost estimates for the temporary sludge storage tanks. Development of cost estimates for the design and construction of sludge storage systems is required to help evaluate a recommendation for the final disposition of the K Basin sludge.

  5. Preparation and Characterization of Uranium Oxides in Support of the K Basin Sludge Treatment Project

    SciTech Connect (OSTI)

    Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.

    2008-07-08T23:59:59.000Z

    Uraninite (UO2) and metaschoepite (UO3·2H2O) are the uranium phases most frequently observed in K Basin sludge. Uraninite arises from the oxidation of uranium metal by anoxic water and metaschoepite arises from oxidation of uraninite by atmospheric or radiolytic oxygen. Studies of the oxidation of uraninite by oxygen to form metaschoepite were performed at 21°C and 50°C. A uranium oxide oxidation state characterization method based on spectrophotometry of the solution formed by dissolving aqueous slurries in phosphoric acid was developed to follow the extent of reaction. This method may be applied to determine uranium oxide oxidation state distribution in K Basin sludge. The uraninite produced by anoxic corrosion of uranium metal has exceedingly fine particle size (6 nm diameter), forms agglomerates, and has the formula UO2.004±0.007; i.e., is practically stoichiometric UO2. The metaschoepite particles are flatter and wider when prepared at 21°C than the particles prepared at 50°C. These particles are much smaller than the metaschoepite observed in prolonged exposure of actual K Basin sludge to warm moist oxidizing conditions. The uraninite produced by anoxic uranium metal corrosion and the metaschoepite produced by reaction of uraninite aqueous slurries with oxygen may be used in engineering and process development testing. A rapid alternative method to determine uranium metal concentrations in sludge also was identified.

  6. Supplementary information on K-Basin sludges

    SciTech Connect (OSTI)

    MAKENAS, B.J.

    1999-03-15T23:59:59.000Z

    Three previous documents in this series have been published covering the analysis of: K East Basin Floor and Pit Sludge, K East Basin Canister Sludge, and K West Basin Canister Sludge. Since their publication, additional data have been acquired and analyses performed. It is the purpose of this volume to summarize the additional insights gained in the interim time period.

  7. Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

    SciTech Connect (OSTI)

    WESTRA, A.G.

    1999-06-24T23:59:59.000Z

    This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility.

  8. Shear Strength Measurement Benchmarking Tests for K Basin Sludge Simulants

    SciTech Connect (OSTI)

    Burns, Carolyn A.; Daniel, Richard C.; Enderlin, Carl W.; Luna, Maria; Schmidt, Andrew J.

    2009-06-10T23:59:59.000Z

    Equipment development and demonstration testing for sludge retrieval is being conducted by the K Basin Sludge Treatment Project (STP) at the MASF (Maintenance and Storage Facility) using sludge simulants. In testing performed at the Pacific Northwest National Laboratory (under contract with the CH2M Hill Plateau Remediation Company), the performance of the Geovane instrument was successfully benchmarked against the M5 Haake rheometer using a series of simulants with shear strengths (?) ranging from about 700 to 22,000 Pa (shaft corrected). Operating steps for obtaining consistent shear strength measurements with the Geovane instrument during the benchmark testing were refined and documented.

  9. Summary status of K Basins sludge characterization

    SciTech Connect (OSTI)

    Baker, R.B.

    1995-01-20T23:59:59.000Z

    A number of activities are underway as part of the Spent Nuclear Fuels Project (SNFP) related to the processing and disposing of sludge in the 105-K Basins (K Basins). Efforts to rigorously define data requirements for these activities are being made using the Data Quality Objectives (DQO) process. Summaries of current sludge characterization data are required to both help support this DQO process and to allow continued progress with on-going engineering activities (e.g., evaluations of disposal alternatives). This document provides the status of K Basins sludge characterization data currently available to the Nuclear Fuel Evaluations group. This group is tasked by the SNFP to help develop and maintain the characterization baseline for the K Basins. The specific objectives of this document are to: (1) provide a current summary (and set of references) of sludge characterization data for use by SNFP initiatives, to avoid unnecessary duplication of effort and to support on-going initiatives; (2) submit these data to an open forum for review and comment, and identify additional sources of significant data that may be available; (3) provide a summary of current data to use as part of the basis to develop requirements for additional sludge characterization data through the DQO process; (4) provide an overview of the intended activities that will be used to develop and maintain the sludge characterization baseline.

  10. CRAD, Engineering - Office of River Protection K Basin Sludge...

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

    Office of River Protection K Basin Sludge Waste System CRAD, Engineering - Office of River Protection K Basin Sludge Waste System May 2004 A section of Appendix C to DOE G 226.1-2...

  11. SLUDGE RETRIEVAL FROM HANFORD K WEST BASIN SETTLER TANKS

    SciTech Connect (OSTI)

    ERPENBECK EG; LESHIKAR GA

    2011-01-13T23:59:59.000Z

    In 2010, an innovative, remotely operated retrieval system was deployed to successfully retrieve over 99.7% of the radioactive sludge from ten submerged tanks in Hanford's K-West Basin. As part of K-West Basin cleanup, the accumulated sludge needed to be removed from the 0.5 meter diameter by 5 meter long settler tanks and transferred approximately 45 meters to an underwater container for sampling and waste treatment. The abrasive, dense, non-homogeneous sludge was the product of the washing process of corroded nuclear fuel. It consists of small (less than 600 micron) particles of uranium metal, uranium oxide, and various other constituents, potentially agglomerated or cohesive after 10 years of storage. The Settler Tank Retrieval System (STRS) was developed to access, mobilize and pump out the sludge from each tank using a standardized process of retrieval head insertion, periodic high pressure water spray, retraction, and continuous pumping of the sludge. Blind operations were guided by monitoring flow rate, radiation levels in the sludge stream, and solids concentration. The technology developed and employed in the STRS can potentially be adapted to similar problematic waste tanks or pipes that must be remotely accessed to achieve mobilization and retrieval of the sludge within.

  12. Feasibility report on criticality issues associated with storage of K Basin sludge in tanks farms

    SciTech Connect (OSTI)

    Vail, T.S.

    1997-05-29T23:59:59.000Z

    This feasibility study provides the technical justification for conclusions about K Basin sludge storage options. The conclusions, solely based on criticality safety considerations, depend on the treatment of the sludge. The two primary conclusions are, (1) untreated sludge must be stored in a critically safe storage tank, and (2) treated sludge (dissolution, precipitation and added neutron absorbers) can be stored in a standard Double Contained Receiver Tank (DCRT) or 241-AW-105 without future restrictions on tank operations from a criticality safety perspective.

  13. K Basin sludge polychlorinated biphenyl removal technology assessment

    SciTech Connect (OSTI)

    Ashworth, S.C.

    1998-08-25T23:59:59.000Z

    The two Hanford K Basins are water-filled concrete pools that contain over 2,100 metric tons of N Reactor fuel elements stored in aluminum or stainless steel canisters. During the time the fuel has been stored, approximately 50 m3 of heterogeneous solid material have accumulated in the basins. This material, referred to as sludge, is a mixture of fuel corrosion products, metallic bits of spent fuel and zirconium clad iron and metal corrosion products and silica from migrating sands. Some of the sludges also contain PCBs. The congener group of PCBs was identified as Aroclor 1254. The maximum concentration of sludge PCBS was found to be 140 ppm (as settled wet basis). However, the distribution of the PCBs is non-uniform throughout the sludge (i.e., there are regions of high and low concentrations and places where no PCBs are present). Higher concentrations could be present at various locations. Aroclors 1016/1242, 1221, 1248, 1254, and 1260 were identified and quantified in K West (KW) Canister sludge. In some of these samples, the concentration of 1260 was higher than 1254. The sludge requires pre-treatment to meet tank farm waste acceptance criteria, Among the numerous requirements, the sludge should be retreated so that it does not contain regulated levels of Toxic Substances Control Act (TSCA) compounds. Because of their stable chemistry and relative insolubility in water, PCBs are difficult to treat. They also resist degradation from heat and electrical charges. This stability has resulted in environmental persistence which has prompted the development of a variety of new cleanup processes including supercritical processes, advanced oxidation, dehalogenation and others. Hopefully, most of the new processes are discussed herein. Information on new processes are being received and will be evaluated in a future revision.

  14. Strength Measurements of Archive K Basin Sludge Using a Soil Penetrometer

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.; Chenault, Jeffrey W.

    2011-12-06T23:59:59.000Z

    Spent fuel radioactive sludge present in the K East and K West spent nuclear fuel storage basins now resides in the KW Basin in six large underwater engineered containers. The sludge will be dispositioned in two phases under the Sludge Treatment Project: (1) hydraulic retrieval into sludge transport and storage containers (STSCs) and transport to interim storage in Central Plateau and (2) retrieval from the STSCs, treatment, and packaging for shipment to the Waste Isolation Pilot Plant. In the years the STSCs are stored, sludge strength is expected to increase through chemical reaction, intergrowth of sludge crystals, and compaction and dewatering by settling. Increased sludge strength can impact the type and operation of the retrieval equipment needed prior to final sludge treatment and packaging. It is important to determine whether water jetting, planned for sludge retrieval from STSCs, will be effective. Shear strength is a property known to correlate with the effectiveness of water jetting. Accordingly, the unconfined compressive strengths (UCS) of archive K Basin sludge samples and sludge blends were measured using a pocket penetrometer modified for hot cell use. Based on known correlations, UCS values can be converted to shear strengths. Twenty-six sludge samples, stored in hot cells for a number of years since last being disturbed, were identified as potential candidates for UCS measurement and valid UCS measurements were made for twelve, each of which was found as moist or water-immersed solids at least 1/2-inch deep. Ten of the twelve samples were relatively weak, having consistencies described as 'very soft' to 'soft'. Two of the twelve samples, KE Pit and KC-4 P250, were strong with 'very stiff' and 'stiff' consistencies described, respectively, as 'can be indented by a thumb nail' or 'can be indented by thumb'. Both of these sludge samples are composites collected from KE Basin floor and Weasel Pit locations. Despite both strong sludges having relatively high iron concentrations, attribution of their high strengths to this factor could not be made with confidence as other measured sludge samples, also from the KE Basin floor and of high iron concentration, were relatively weak. The observed UCS and shear strengths for the two strong sludges were greater than observed in any prior testing of K Basin sludge except for sludge processed at 185 C under hydrothermal conditions.

  15. Gas Generation from K East Basin Sludges - Series II Testing

    SciTech Connect (OSTI)

    Bryan, Samuel A.; Delegard, Calvin H.; Schmidt, Andrew J.; Sell, Rachel L.; Silvers, Kurt L.; Gano, Susan R.; Thornton, Brenda M.

    2001-03-14T23:59:59.000Z

    This report describes work to examine the gas generation behavior of actual K East (KE) Basin floor, pit and canister sludge. Mixed and unmixed and fractionated KE canister sludge were tested, along with floor and pit sludges from areas in the KE Basin not previously sampled. The first report in this series focused on gas generation from KE floor and canister sludge collected using a consolidated sampling technique. The third report will present results of gas generation testing of irradiated uranium fuel fragments with and without sludge addition. The path forward for management of the K Basin Sludge is to retrieve, ship, and store the sludge at T Plant until final processing at some future date. Gas generation will impact the designs and costs of systems associated with retrieval, transportation and storage of sludge.

  16. SLUDGE TREATMENT PROJECT PHASE 1 SLUDGE STORAGE OPTIONS ASSESSMENT OF T PLANT VERSUS ALTERNATE STORAGE FACILITY

    SciTech Connect (OSTI)

    RUTHERFORD WW; GEUTHER WJ; STRANKMAN MR; CONRAD EA; RHOADARMER DD; BLACK DM; POTTMEYER JA

    2009-04-29T23:59:59.000Z

    The CH2M HILL Plateau Remediation Company (CHPRC) has recommended to the U.S. Department of Energy (DOE) a two phase approach for removal and storage (Phase 1) and treatment and packaging for offsite shipment (Phase 2) of the sludge currently stored within the 105-K West Basin. This two phased strategy enables early removal of sludge from the 105-K West Basin by 2015, allowing remediation of historical unplanned releases of waste and closure of the 100-K Area. In Phase 1, the sludge currently stored in the Engineered Containers and Settler Tanks within the 105-K West Basin will be transferred into sludge transport and storage containers (STSCs). The STSCs will be transported to an interim storage facility. In Phase 2, sludge will be processed (treated) to meet shipping and disposal requirements and the sludge will be packaged for final disposal at a geologic repository. The purpose of this study is to evaluate two alternatives for interim Phase 1 storage of K Basin sludge. The cost, schedule, and risks for sludge storage at a newly-constructed Alternate Storage Facility (ASF) are compared to those at T Plant, which has been used previously for sludge storage. Based on the results of the assessment, T Plant is recommended for Phase 1 interim storage of sludge. Key elements that support this recommendation are the following: (1) T Plant has a proven process for storing sludge; (2) T Plant storage can be implemented at a lower incremental cost than the ASF; and (3) T Plant storage has a more favorable schedule profile, which provides more float, than the ASF. Underpinning the recommendation of T Plant for sludge storage is the assumption that T Plant has a durable, extended mission independent of the K Basin sludge interim storage mission. If this assumption cannot be validated and the operating costs of T Plant are borne by the Sludge Treatment Project, the conclusions and recommendations of this study would change. The following decision-making strategy, which is dependent on the confidence that DOE has in the long term mission for T Plant, is proposed: (1) If the confidence level in a durable, extended T Plant mission independent of sludge storage is high, then the Sludge Treatment Project (STP) would continue to implement the path forward previously described in the Alternatives Report (HNF-39744). Risks to the sludge project can be minimized through the establishment of an Interface Control Document (ICD) defining agreed upon responsibilities for both the STP and T Plant Operations regarding the transfer and storage of sludge and ensuring that the T Plant upgrade and operational schedule is well integrated with the sludge storage activities. (2) If the confidence level in a durable, extended T Plant mission independent of sludge storage is uncertain, then the ASF conceptual design should be pursued on a parallel path with preparation of T Plant for sludge storage until those uncertainties are resolved. (3) Finally, if the confidence level in a durable, extended T Plant mission independent of sludge storage is low, then the ASF design should be selected to provide independence from the T Plant mission risk.

  17. COMPARISON OF FINAL TREATMENT & PROCESS METHODS FOR THE PREPARATION & INTERIM STORAGE OF K BASIN KNOCKOUT POT SLUDGE ENGINEERING STUDY

    SciTech Connect (OSTI)

    ERPENBECK, E.G.

    2004-06-22T23:59:59.000Z

    Fluor Hanford (FH) directed British Nuclear Fuels, Inc. (BNFL) to prepare a Knock Out Pot (KOP) study ''using cold vacuum drying (CVD) to dry the KOP sludge with a final disposition to Canister Storage Building (CSB) or evaluate a process to corrode the sludge in water and grout it to meet the end state criteria for the Waste Isolation Pilot Plant (WIPP).'' BNFL initially identified four process options: (1) Incorporate sludges into grout with no pre-conditioning; (2) Corrode the Uranium metal in the sludges then incorporate the resulting sludge into grout; (3) Separate sludge into two streams by washing/size separation with: Larger particle/Uranium metal rich stream being vacuum dried at CVD; and Smaller particle/lower Uranium metal stream being incorporated into grout; and (4) Cold vacuum dry all sludge at CVD. A coarse down selection meeting discounted option 1 as the number of drums required was prohibitive in terms of cost and schedule; and option 4 due to the technical inability of CVD to dry this waste.

  18. PROGRESS WITH K BASINS SLUDGE RETRIEVAL STABILIZATION & PACKAGING AT THE HANFORD NUCLEAR SITE

    SciTech Connect (OSTI)

    KNOLLMEYER, P.M.; PHILLIPS, C; TOWNSON, P.S.

    2006-01-30T23:59:59.000Z

    This paper shows how Fluor Hanford and BNG America have combined nuclear plant skills from the U.S. and the U.K. to devise methods to retrieve and treat the sludge that has accumulated in K Basins at the Hanford Site over many years. Retrieving the sludge is the final stage in removing fuel and sludge from the basins to allow them to be decontaminated and decommissioned, so as to remove the threat of contamination of the Columbia River. A description is given of sludge retrieval using vacuum lances and specially developed nozzles and pumps into Consolidation Containers within the basins. The special attention that had to be paid to the heat generation and potential criticality issues with the irradiated uranium-containing sludge is described. The processes developed to re-mobilize the sludge from the Consolidation Containers and pump it through flexible and transportable hose-in-hose piping to the treatment facility are explained with particular note made of dealing with the abrasive nature of the sludge. The treatment facility, housed in an existing Hanford building, is described, and the uranium-corrosion and grout packaging processes explained. The uranium corrosion process is a robust, tempered process very suitable for dealing with a range of differing sludge compositions. Optimization and simplification of the original sludge corrosion process design is described and the use of transportable and reusable equipment is indicated. The processes and techniques described in the paper are shown to have wide applicability to nuclear cleanup.

  19. Functions and requirements for 105-KE Basin sludge retrieval and packaging

    SciTech Connect (OSTI)

    Feigenbutz, L.V.

    1994-12-16T23:59:59.000Z

    Sludge, and the clouding due to sludge, interferes with basin operation and maintenance activities. This document defines the overall functions and requirements for sludge retrieval and packaging activities to be performed in the 105-KE Basin.

  20. Effects of Time, Heat, and Oxygen on K Basin Sludge Agglomeration, Strength, and Solids Volume

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Sinkov, Sergey I.; Schmidt, Andrew J.; Daniel, Richard C.; Burns, Carolyn A.

    2011-01-04T23:59:59.000Z

    Sludge disposition will be managed in two phases under the K Basin Sludge Treatment Project. The first phase is to retrieve the sludge that currently resides in engineered containers in the K West (KW) Basin pool at ~10 to 18°C. The second phase is to retrieve the sludge from interim storage in the sludge transport and storage containers (STSCs) and treat and package it in preparation for eventual shipment to the Waste Isolation Pilot Plant. The work described in this report was conducted to gain insight into how sludge may change during long-term containerized storage in the STSCs. To accelerate potential physical and chemical changes, the tests were performed at temperatures and oxygen partial pressures significantly greater than those expected in the T Plant canyon cells where the STSCs will be stored. Tests were conducted to determine the effects of 50°C oxygenated water exposure on settled quiescent uraninite (UO2) slurry and a full simulant of KW containerized sludge to determine the effects of oxygen and heat on the composition and mechanical properties of sludge. Shear-strength measurements by vane rheometry also were conducted for UO2 slurry, mixtures of UO2 and metaschoepite (UO3•2H2O), and for simulated KW containerized sludge. The results from these tests and related previous tests are compared to determine whether the settled solids in the K Basin sludge materials change in volume because of oxidation of UO2 by dissolved atmospheric oxygen to form metaschoepite. The test results also are compared to determine if heating or other factors alter sludge volumes and to determine the effects of sludge composition and settling times on sludge shear strength. It has been estimated that the sludge volume will increase with time because of a uranium metal ? uraninite ? metaschoepite oxidation sequence. This increase could increase the number of containers required for storage and increase overall costs of sludge management activities. However, the volume might decrease because of decreases in the water-volume fraction caused by sludge solid reactions, compaction, or intergrowth and recrystallization of metaschoepite. In that case, fewer STSCs may be needed, but the shear strength would increase, and this could challenge recovery by water jet erosion and require more aggressive retrieval methods. Overall, the tests described herein indicate that the settled solids volume remains the same or decreases with time. The only case for which the sludge solids volumes increase with time is for the expansion factor attendant upon the anoxic corrosion of uranium metal to produce UO2 and subsequent reaction with oxygen to form equimolar UO2.25 and UO3•2H2O.

  1. STP K Basin Sludge Sample Archive at the Pacific Northwest National Laboratory FY2014

    SciTech Connect (OSTI)

    Fiskum, Sandra K.; Smoot, Margaret R.; Schmidt, Andrew J.

    2014-06-01T23:59:59.000Z

    The Pacific Northwest National Laboratory (PNNL) currently houses 88 samples (~10.5 kg) of K Basin sludge (81 wet and seven dry samples) on behalf of the Sludge Treatment Project (STP), which is managed for the U.S. Department of Energy (DOE) by the CH2M Hill Plateau Remediation Company (CHPRC). Selected samples are intended to serve, in part, as sentinels to enhance understanding of sludge properties after long-term storage, and thus enhance understanding of sludge behavior following transfer to sludge transfer and storage containers (STSCs) and storage at the Hanford 200 Area central plateau. In addition, remaining samples serve in contingency for future testing requirements. At PNNL, the samples are tracked and maintained under a prescriptive and disciplined monthly sample-monitoring program implemented by PNNL staff. This report updates the status of the K Basin archive sludge sample inventory to April 2014. The previous inventory status report, PNNL 22245 (Fiskum et al. 2013, limited distribution report), was issued in February of 2013. This update incorporates changes in the inventory related to repackaging of 17 samples under test instructions 52578 TI052, K Basin Sludge Sample Repackaging for Continued Long Term Storage, and 52578 TI053, K Basin Sludge Sample Repackaging Post-2014 Shear Strength Measurements. Note that shear strength measurement results acquired in 2014 are provided separately. Specifically, this report provides the following: • a description of the K Basin sludge sample archive program and the sample inventory • a summary and images of the samples that were repackaged in April 2014 • up-to-date images and plots of the settled density and water loss from all applicable samples in the inventory • updated sample pedigree charts, which provide a roadmap of the genesis and processing history of each sample in the inventory • occurrence and deficiency reports associated with sample storage and repackaging

  2. Gas Generation from K East Basin Sludges - Series II Testing

    SciTech Connect (OSTI)

    Bryan, Samuel A.; Delegard, Calvin H.; Schmidt, Andrew J.; Sell, Rachel L.; Silvers, Kurt L.; Gano, Susan R.; Thornton, Brenda M.

    2004-04-26T23:59:59.000Z

    This report describes work to examine the gas generation behavior of actual K East (KE) Basin floor, pit and canister sludge. Mixed and unmixed and fractionated KE canister sludge were tested, along with floor and pit sludges from areas in the KE Basin not previously sampled. The first report in this series focuses on gas generation from KE floor and canister sludge collected using a consolidated sampling technique. The third report presents results of gas generation testing of irradiated uranium fuel fragments with and without sludge addition. The path forward for management of the K Basin Sludge is to retrieve, ship, and store the sludge at T Plant until final processing at some future date. Gas generation will impact the designs and costs of systems associated with retrieval, transportation and storage of sludge. This report was originally published in March 2001. In January 2004, a transcription error was discovered in the value reported for the uranium metal content of KE North Loadout Pit sample FE-3. This revision of the report corrects the U metal content of FE-3 from 0.0013 wt% to 0.013 wt%.

  3. Treatment of dredged sludge by mechanical dehydration

    SciTech Connect (OSTI)

    Maekawa, T.

    1992-03-01T23:59:59.000Z

    Sludge deposits in the water area damage the ecosystems and environments; their elimination has always been an urgent task for human communities. Generally, sludge deposits are dredged out of the bottom of the water area, transported to, and discharged at a large disposal area on land. Recently, however, it has become increasingly difficult to secure disposal areas and routes of speedy transportation for disposal of dredged sludge. Accordingly, there is an urgent need to reduce both the volume of dredged sludge and the size of the disposal area. This mechanical method is different from the conventional engineering dehydration by loading, consolidation, and drainage in that the dredged sludge is separated into sludge cakes and clean water that can be returned to the water area through mechanical centrifugal dehydration. Sludge deposits are distributed thin and wide on the bottom of the water area, and a pump dredge has been proved effective in many cases for dredging the upper layers of sludge deposits accurately and without creating turbidity in water. This mechanical sludge treatment technique can be most efficient when used in combination with a pump dredge. This method offers the following advantages: (a) It requires smaller space for treatment and disposal of dredged sludge than the conventional method. (b) Facilities and costs for transportation can be reduced. (c) Various systems can be adopted for transportation of sludge cakes. (d) This system is transportable and compact and can be constructed anywhere either on land or on water.

  4. SLUDGE TREATMENT PROJECT ENGINEERED CONTAINER RETRIEVAL AND TRANSFER SYSTEM PRELMINARY DESIGN HAZARD AND OPERABILITY STUDY

    SciTech Connect (OSTI)

    CARRO CA

    2011-07-15T23:59:59.000Z

    This Hazard and Operability (HAZOP) study addresses the Sludge Treatment Project (STP) Engineered Container Retrieval and Transfer System (ECRTS) preliminary design for retrieving sludge from underwater engineered containers located in the 105-K West (KW) Basin, transferring the sludge as a sludge-water slurry (hereafter referred to as 'slurry') to a Sludge Transport and Storage Container (STSC) located in a Modified KW Basin Annex, and preparing the STSC for transport to T Plant using the Sludge Transport System (STS). There are six, underwater engineered containers located in the KW Basin that, at the time of sludge retrieval, will contain an estimated volume of 5.2 m{sup 3} of KW Basin floor and pit sludge, 18.4 m{sup 3} of 105-K East (KE) Basin floor, pit, and canister sludge, and 3.5 m{sup 3} of settler tank sludge. The KE and KW Basin sludge consists of fuel corrosion products (including metallic uranium, and fission and activation products), small fuel fragments, iron and aluminum oxide, sand, dirt, operational debris, and biological debris. The settler tank sludge consists of sludge generated by the washing of KE and KW Basin fuel in the Primary Clean Machine. A detailed description of the origin of sludge and its chemical and physical characteristics can be found in HNF-41051, Preliminary STP Container and Settler Sludge Process System Description and Material Balance. In summary, the ECRTS retrieves sludge from the engineered containers and hydraulically transfers it as a slurry into an STSC positioned within a trailer-mounted STS cask located in a Modified KW Basin Annex. The slurry is allowed to settle within the STSC to concentrate the solids and clarify the supernate. After a prescribed settling period the supernate is decanted. The decanted supernate is filtered through a sand filter and returned to the basin. Subsequent batches of slurry are added to the STSC, settled, and excess supernate removed until the prescribed quantity of sludge is collected. The sand filter is then backwashed into the STSC. The STSC and STS cask are then inerted and transported to T Plant.

  5. Formation of aerobic granular sludge biofilms for sustainable wastewater treatment

    E-Print Network [OSTI]

    ENAC/ Formation of aerobic granular sludge biofilms for sustainable wastewater treatment David G Research, Microbiology of Interfaces, Magdeburg (Germany) EDCE 2011 / From activated sludge flocs

  6. Independent Activity Report, Hanford Sludge Treatment Project...

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

    February 2012 Hanford Sludge Treatment Project Operational Awareness Review HIAR-RL-2012-02-27 The U.S. Department of Energy's (DOE) Office of Enforcement and Oversight, within...

  7. K Basin Sludge Conditioning Testing Nitric Acid Dissolution Testing of K East Area Sludge Composite, Small- and Large-Scale Testing

    SciTech Connect (OSTI)

    Carlson, C.D.; Delegard, C.H.; Burgeson, I.E.; Schmidt, A.J.; Silvers, K.L.

    1999-04-02T23:59:59.000Z

    This report describes work performed by Pacific Northwest National Laboratory (PNNL) for Numatec Hanford Corporation (NHC) to support the development of the K Basin Sludge Treatment System. For this work, testing was performed to examine the dissolution behavior of a K East Basin floor and Weasel Pit sludge composite, referred to as K East area sludge composite, in nitric acid at the following concentrations: 2 M, 4 M, 6 M and 7.8 M. With the exception of one high solids loading test the nitric acid was added at 4X the stoichiometric requirement (assuming 100% of the sludge was uranium metal). The dissolution tests were conducted at boiling temperatures for 24 hours. Most of the tests were conducted with {approximately}2.5 g of sludge (dry basis). The high solids loading test was conducted with {approximately}7 g of sludge. A large-scale dissolution test was conducted with 26.5 g of sludge and 620 mL of 6 M nitric acid. The objectives of this test were to (1) generate a sufficient quantity of acid-insoluble residual solids for use in leaching studies, and (2) examine the dissolution behavior of the sludge composite at a larger scale.

  8. Hanford K-Basin Sludge Characterization Overview February 2005

    E-Print Network [OSTI]

    irradiated fuel prior to Spent Nuclear Fuel (SNF) processing. In 1980, irradiated N-Reactor fuel was placed products and uranium. This sludge must be removed and disposed as part of the basin decommissioning) and the definition of High Level Waste (HLW) and Spent Nuclear Fuel (SNF) from the Nuclear Waste Policy Act of 1982

  9. Sludge drying reed beds: a full and pilot-scales study for activated sludge treatment

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Sludge drying reed beds: a full and pilot-scales study for activated sludge treatment S. Troesch.troesch@cemagref.fr, dirk.esser@sint.fr Abstract Sludge drying reed beds have been used for dewatering and mineralization of sludge since the beginning of the 90's, but their insufficient performances in terms of Dry Matter [DM

  10. PROPERTIES OF TREATMENT SLUDGE DURING SEDIMENTATION AND CONSOLIDATION TESTS1

    E-Print Network [OSTI]

    Aubertin, Michel

    PROPERTIES OF TREATMENT SLUDGE DURING SEDIMENTATION AND CONSOLIDATION TESTS1 Lincar Pedroni2 , Jean on sludge produced from an acid mine drainage (AMD) treatment plant. The testing program involved test, physical and geotechnical properties of the resulting sludge were measured. In this paper

  11. NORDIC WASTE WATER TREATMENT SLUDGE TREATMENT

    E-Print Network [OSTI]

    biogas, electricity and fertilizer from 30 000 tons of annually waste. The plant was opened in March 2008 together it an- nually produces 18,9 GWh biogas and around 10 GWh of elec- tricity. The Cambi THP ­process biological sludge, which normally is very difficult to digest and dewater. The THP treats both municipal

  12. SLUDGE TREATMENT PROJECT COST COMPARISON BETWEEN HYDRAULIC LOADING AND SMALL CANISTER LOADING CONCEPTS

    SciTech Connect (OSTI)

    GEUTHER J; CONRAD EA; RHOADARMER D

    2009-08-24T23:59:59.000Z

    The Sludge Treatment Project (STP) is considering two different concepts for the retrieval, loading, transport and interim storage of the K Basin sludge. The two design concepts under consideration are: (1) Hydraulic Loading Concept - In the hydraulic loading concept, the sludge is retrieved from the Engineered Containers directly into the Sludge Transport and Storage Container (STSC) while located in the STS cask in the modified KW Basin Annex. The sludge is loaded via a series of transfer, settle, decant, and filtration return steps until the STSC sludge transportation limits are met. The STSC is then transported to T Plant and placed in storage arrays in the T Plant canyon cells for interim storage. (2) Small Canister Concept - In the small canister concept, the sludge is transferred from the Engineered Containers (ECs) into a settling vessel. After settling and decanting, the sludge is loaded underwater into small canisters. The small canisters are then transferred to the existing Fuel Transport System (FTS) where they are loaded underwater into the FTS Shielded Transfer Cask (STC). The STC is raised from the basin and placed into the Cask Transfer Overpack (CTO), loaded onto the trailer in the KW Basin Annex for transport to T Plant. At T Plant, the CTO is removed from the transport trailer and placed on the canyon deck. The CTO and STC are opened and the small canisters are removed using the canyon crane and placed into an STSC. The STSC is closed, and placed in storage arrays in the T Plant canyon cells for interim storage. The purpose of the cost estimate is to provide a comparison of the two concepts described.

  13. DESIGN OF A SYSTEM TO RETRIEVE SLUDGE FROM THE K EAST SPENT FUEL BASIN AT HANFORD

    SciTech Connect (OSTI)

    Twitchell, A.L.; MacLean, G.T.; Ho, Q.T.; Fort, D.L.

    2003-02-27T23:59:59.000Z

    This paper describes the Sludge Retrieval System (SRS), which was designed to safely remove radioactive sludge from the K East spent fuel basin at the 100 K Area of the Hanford Site. Basin water and sludge have the potential to leak to the environment due to the age and condition of the basins. Since the 100 K Area spent fuel basins are located next to the Columbia River, the Spent Nuclear Fuel Project mission includes the safe removal, containment, and transportation of sludge from the basins to a secure storage location. The scope of the SRS includes: A system capable of retrieving sludge from the K East basin floor, pits, and fuel canisters; Separation of debris from sludge, where debris is defined as any material greater than 0.64 cm (0.25 in.) in diameter; Collection of sludge particles in a container that can be transported away from the basin; Modifications to the K East basin to allow installation of the SRS. The SRS was designed by Fluor Federal Services. Changes to the designed system were made by Fluor Hanford as a result of full-scale testing performed after design. This paper discusses this testing, as well as operation and control of the system. Construction and startup testing was initially scheduled to be complete by the end of December 2002. Startup of the system is now expected in April 2003.

  14. SLUDGE TREATMENT PROJECT ALTERNATIVES ANALYSIS SUMMARY REPORT [VOLUME 1

    SciTech Connect (OSTI)

    FREDERICKSON JR; ROURK RJ; HONEYMAN JO; JOHNSON ME; RAYMOND RE

    2009-01-19T23:59:59.000Z

    Highly radioactive sludge (containing up to 300,000 curies of actinides and fission products) resulting from the storage of degraded spent nuclear fuel is currently stored in temporary containers located in the 105-K West storage basin near the Columbia River. The background, history, and known characteristics of this sludge are discussed in Section 2 of this report. There are many compelling reasons to remove this sludge from the K-Basin. These reasons are discussed in detail in Section1, and they include the following: (1) Reduce the risk to the public (from a potential release of highly radioactive material as fine respirable particles by airborne or waterborn pathways); (2) Reduce the risk overall to the Hanford worker; and (3) Reduce the risk to the environment (the K-Basin is situated above a hazardous chemical contaminant plume and hinders remediation of the plume until the sludge is removed). The DOE-RL has stated that a key DOE objective is to remove the sludge from the K-West Basin and River Corridor as soon as possible, which will reduce risks to the environment, allow for remediation of contaminated areas underlying the basins, and support closure of the 100-KR-4 operable unit. The environmental and nuclear safety risks associated with this sludge have resulted in multiple legal and regulatory remedial action decisions, plans,and commitments that are summarized in Table ES-1 and discussed in more detail in Volume 2, Section 9.

  15. Sludge Treatment Evaluation: 1992 Technical progress

    SciTech Connect (OSTI)

    Silva, L J; Felmy, A R; Ding, E R

    1993-01-01T23:59:59.000Z

    This report documents Fiscal Year 1992 technical progress on the Sludge Treatment Evaluation Task, which is being conducted by Pacific Northwest Laboratory. The objective of this task is to develop a capability to predict the performance of pretreatment processes for mixed radioactive and hazardous waste stored at Hanford and other US Department of Energy (DOE) sites. Significant cost savings can be achieved if radionuclides and other undesirable constituents can be effectively separated from the bulk waste prior to final treatment and disposal. This work is initially focused on chemical equilibrium prediction of water washing and acid or base dissolution of Hanford single-shell tank (SST) sludges, but may also be applied to other steps in pretreatment processes or to other wastes. Although SST wastes contain many chemical species, there are relatively few constituents -- Na, Al, NO[sub 3], NO[sub 2], PO[sub 4], SO[sub 4], and F -- contained in the majority of the waste. These constituents comprise 86% and 74% of samples from B-110 and U-110 SSTS, respectively. The major radionuclides of interest (Cs, Sr, Tc, U) are present in the sludge in small molal quantities. For these constituents, and other important components that are present in small molal quantities, the specific ion-interaction terms used in the Pitzer or NRTL equations may be assumed to be zero for a first approximation. Model development can also be accelerated by considering only the acid or base conditions that apply for the key pretreatment steps. This significantly reduces the number of chemical species and chemical reactions that need to be considered. Therefore, significant progress can be made by developing all the specific ion interactions for a base model and an acid dissolution model.

  16. Development of K-Basin High-Strength Homogeneous Sludge Simulants and Correlations Between Unconfined Compressive Strength and Shear Strength

    SciTech Connect (OSTI)

    Onishi, Yasuo; Baer, Ellen BK; Chun, Jaehun; Yokuda, Satoru T.; Schmidt, Andrew J.; Sande, Susan; Buchmiller, William C.

    2011-02-20T23:59:59.000Z

    K-Basin sludge will be stored in the Sludge Transport and Storage Containers (STSCs) at an interim storage location on Central Plateau before being treated and packaged for disposal. During the storage period, sludge in the STSCs may consolidate/agglomerate, potentially resulting in high-shear-strength material. The Sludge Treatment Project (STP) plans to use water jets to retrieve K-Basin sludge after the interim storage. STP has identified shear strength to be a key parameter that should be bounded to verify the operability and performance of sludge retrieval systems. Determining the range of sludge shear strength is important to gain high confidence that a water-jet retrieval system can mobilize stored K-Basin sludge from the STSCs. The shear strength measurements will provide a basis for bounding sludge properties for mobilization and erosion. Thus, it is also important to develop potential simulants to investigate these phenomena. Long-term sludge storage tests conducted by Pacific Northwest National Laboratory (PNNL) show that high-uranium-content K-Basin sludge can self-cement and form a strong sludge with a bulk shear strength of up to 65 kPa. Some of this sludge has 'paste' and 'chunks' with shear strengths of approximately 3-5 kPa and 380-770 kPa, respectively. High-uranium-content sludge samples subjected to hydrothermal testing (e.g., 185 C, 10 hours) have been observed to form agglomerates with a shear strength up to 170 kPa. These high values were estimated by measured unconfined compressive strength (UCS) obtained with a pocket penetrometer. Due to its ease of use, it is anticipated that a pocket penetrometer will be used to acquire additional shear strength data from archived K-Basin sludge samples stored at the PNNL Radiochemical Processing Laboratory (RPL) hot cells. It is uncertain whether the pocket penetrometer provides accurate shear strength measurements of the material. To assess the bounding material strength and potential for erosion, it is important to compare the measured shear strength to penetrometer measurements and to develop a correlation (or correlations) between UCS measured by a pocket penetrometer and direct shear strength measurements for various homogeneous and heterogeneous simulants. This study developed 11 homogeneous simulants, whose shear strengths vary from 4 to 170 kPa. With these simulants, we developed correlations between UCS measured by a Geotest E-280 pocket penetrometer and shear strength values measured by a Geonor H-60 hand-held vane tester and a more sophisticated bench-top unit, the Haake M5 rheometer. This was achieved with side-by-side measurements of the shear strength and UCS of the homogeneous simulants. The homogeneous simulants developed under this study consist of kaolin clay, plaster of Paris, and amorphous alumina CP-5 with water. The simulants also include modeling clay. The shear strength of most of these simulants is sensitive to various factors, including the simulant size, the intensity of mixing, and the curing time, even with given concentrations of simulant components. Table S.1 summarizes these 11 simulants and their shear strengths.

  17. System design description for the consolidated sludge sampling system for K Basins floor and fuel canisters

    SciTech Connect (OSTI)

    HECHT, S.L.

    1999-02-18T23:59:59.000Z

    This System Design Description describes the Consolidated Sludge Sampling System used in the gathering of sludge samples from K Basin floor and fuel canisters. This document provides additional information on the need for the system, the functions and requirements of the systems, the operations of the system, and the general work plan used in its' design and development.

  18. Determination of Uranium Metal Concentration in Irradiated Fuel Storage Basin Sludge Using Selective Dissolution

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Sinkov, Sergey I.; Chenault, Jeffrey W.; Schmidt, Andrew J.; Welsh, Terri L.; Pool, Karl N.

    2014-03-01T23:59:59.000Z

    Uranium metal corroding in water-saturated sludges now held in the US Department of Energy Hanford Site K West irradiated fuel storage basin can create hazardous hydrogen atmospheres during handling, immobilization, or subsequent transport and storage. Knowledge of uranium metal concentration in sludge thus is essential to safe sludge management and process design, requiring an expeditious routine analytical method to detect uranium metal concentrations as low as 0.03 wt% in sludge even in the presence of 30 wt% or higher total uranium concentrations.

  19. Chemical and Radiochemical Analysis of Consolidated Sludge Samples from the K East Basin

    SciTech Connect (OSTI)

    Elmore, Monte R.; Schmidt, Andrew J.; Silvers, Kurt L.; Thornton, Brenda M.; Gano, Susan R.

    2000-10-31T23:59:59.000Z

    Consolidated sludge samples described in this report were collected from the Hanford K East Basin fuel storage pool in March and April 1999. Material for the samples was collected from both the basin floor and fuel canisters within the basin. Analyses persented include weight percent solids determination, uranium analysis by kinetic phosphorescence (KPA), plutonium isotope analysis by alpha energy analysis (AEA), gross beta analysis, gamma energy analysis (GEA), and metals analysis by inductively coupled plasma atomic emission spectroscopy (ICP-AES).

  20. Final Report - Gas Generation Testing of Uranium Metal in Simulated K Basin Sludge and in Grouted Sludge Waste Forms

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.; Sell, Rachel L.; Sinkov, Sergei I.; Bryan, Samuel A.; Gano, Sue; Thornton, Brenda M.

    2004-08-19T23:59:59.000Z

    The Waste Isolation Pilot Plant (WIPP) is being considered for the disposal of K Basin sludge as RH-TRU. Because the hydrogen gas concentration in the 55-gallon RH-TRU sealed drums to be transported to WIPP is limited by flammability safety, the number of containers and shipments likely will be driven by the rate of hydrogen generated by the uranium metal-water reaction (U + 2 H{sub 2}O {yields} UO{sub 2} + 2 H{sub 2}) in combination with the hydrogen generated from water and organic radiolysis. Gas generation testing was conducted with uranium metal particles of known surface area, in simulated K West (KW) Basin canister sludge and immobilized in candidate grout solidification matrices. This study evaluated potential for Portland cement and magnesium phosphate grouts to inhibit the reaction of water with uranium metal in the sludge and thereby permit higher sludge loading to the disposed waste form. The best of the grouted waste forms decreased the uranium metal-water reaction by a factor of four.

  1. K Basins Sludge Treatment Project Phase 1

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2 OPAM Flash2011-12Approvedof6, 1945: Trinity Test JulyDepartmentJust PlainK

  2. Summary - K Basins Sludge Treatment Process

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic2Uranium Transferon the Passing of AdmiraltheOil and Less CO2CausticNevadaINL,K

  3. Pilot Scale Study of Excess Sludge Production Reduction in Wastewater Treatment by Ozone

    E-Print Network [OSTI]

    Barthelat, Francois

    Pilot Scale Study of Excess Sludge Production Reduction in Wastewater Treatment by Ozone Yuan Ma-scale reactors were operated at the LaPrairie Wastewater Treatment plant (one control and one ozonated) to investigate the sludge reduction potential of partially ozonating sludge return activated sludge (RAS

  4. Test Plan: Sludge Treatment Project Corrosion Process Chemistry Follow-on Testing

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.; Poloski, Adam P.

    2007-08-17T23:59:59.000Z

    This test plan was prepared by the Pacific Northwest National Laboratory (PNNL) under contract with Fluor Hanford (FH). The test plan describes the scope and conditions to be used to perform laboratory-scale testing of the Sludge Treatment Project (STP) hydrothermal treatment of K Basin sludge. The STP, managed for the U. S. Department of Energy (DOE) by FH, was created to design and operate a process to eliminate uranium metal from the sludge prior to packaging for Waste Isolation Pilot Plant (WIPP) by using high temperature liquid water to accelerate the reaction, produce uranium dioxide from the uranium metal, and safely discharge the hydrogen. The proposed testing builds on the approach and laboratory test findings for both K Basin sludge and simulated sludge garnered during prior testing from September 2006 to March 2007. The outlined testing in this plan is designed to yield further understanding of the nature of the chemical reactions, the effects of compositional and process variations and the effectiveness of various strategies to mitigate the observed high shear strength phenomenon observed during the prior testing. These tests are designed to provide process validation and refinement vs. process development and design input. The expected outcome is to establish a level of understanding of the chemistry such that successful operating strategies and parameters can be implemented within the confines of the existing STP corrosion vessel design. In July 2007, the DOE provided direction to FH regarding significant changes to the scope of the overall STP. As a result of the changes, FH directed PNNL to stop work on most of the planned activities covered in this test plan. Therefore, it is unlikely the testing described here will be performed. However, to preserve the test strategy and details developed to date, the test plan has been published.

  5. Management Of Hanford KW Basin Knockout Pot Sludge As Spent Nuclear Fuel

    SciTech Connect (OSTI)

    Raymond, R. E. [CH2M HIll Plateau Remediation Company, Richland, WA (United States); Evans, K. M. [AREVA, Avignon (France)

    2012-10-22T23:59:59.000Z

    CH2M HILL Plateau Remediation Company (CHPRC) and AREVA Federal Services, LLC (AFS) have been working collaboratively to develop and deploy technologies to remove, transport, and interim store remote-handled sludge from the 10S-K West Reactor Fuel Storage Basin on the U.S. Department of Energy (DOE) Hanford Site near Richland, WA, USA. Two disposal paths exist for the different types of sludge found in the K West (KW) Basin. One path is to be managed as Spent Nuclear Fuel (SNF) with eventual disposal at an SNF at a yet to be licensed repository. The second path will be disposed as remote-handled transuranic (RH-TRU) waste at the Waste Isolation Pilot Plant (WIPP) in Carlsbad, NM. This paper describes the systems developed and executed by the Knockout Pot (KOP) Disposition Subproject for processing and interim storage of the sludge managed as SNF, (i.e., KOP material).

  6. Particle Size (Sieving) and Enthalpy (Acid Calorimetry) Analysis of Single-Pull K East Basin Floor and Pit Sludges

    SciTech Connect (OSTI)

    Bredt, Paul R. (BATTELLE (PACIFIC NW LAB)); Delegard, Calvin H. (BATTELLE (PACIFIC NW LAB)); Schmidt, Andrew J. (BATTELLE (PACIFIC NW LAB)); Silvers, Kurt L. (BATTELLE (PACIFIC NW LAB)); Thornton, Brenda M. (BATTELLE (PACIFIC NW LAB)); Gano, Sue (BATTELLE (PACIFIC NW LAB))

    2000-10-31T23:59:59.000Z

    This report discusses particle size and calorimetry analyses performed on single-pull sludge samples collected from the Hanford K East Basin floor and pits. This study was conducted by the Pacific Northwest National Laboratory (PNNL) in support of the baseline sludge management plan, which calls for the sludge to be packaged, shipped and stored at T Plant in the Hanford 200 West Area until final processing as a future date. These analyses were needed to better understand the K Basin sludge inventory and chemical reactivity.

  7. CRAD, Conduct of Operations- Office of River Protection K Basin Sludge Waste System

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2004 assessment of the Conduct of Operations program at the Office of River Protection, K Basin Sludge Waste System.

  8. CRAD, Management- Office of River Protection K Basin Sludge Waste System

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2004 assessment of the Management at the Office of River Protection K Basin Sludge Waste System.

  9. CRAD, Occupational Safety & Health- Office of River Protection K Basin Sludge Waste System

    Broader source: Energy.gov [DOE]

    A section of Appendix C to DOE G 226.1-2 "Federal Line Management Oversight of Department of Energy Nuclear Facilities." Consists of Criteria Review and Approach Documents (CRADs) used for a May 2004 assessment of the Environment, Safety and Health program at the Office of River Protection K Basin Sludge Waste System.

  10. DEVELOPMENT OF DATABASE ON FECAL SLUDGE COLLECTION, TREATMENT AND DISPOSAL IN THACHIN,

    E-Print Network [OSTI]

    Richner, Heinz

    i DEVELOPMENT OF DATABASE ON FECAL SLUDGE COLLECTION, TREATMENT AND DISPOSAL IN THACHIN, CHAOPRAYA Sludge (FS) management and lacking of data on FS collection, treatment and disposal. Nevertheless, FS

  11. K Basin Sludge Conditioning Process Testing Project Results from Test 4, ''Acid Digestion of Mixed-Bed Ion Exchange Resin''

    SciTech Connect (OSTI)

    Pool, K.H.; Delegard, C.H.; Schmidt, A.J.; Thornton, B.M.; Silvers, K.L.

    1999-04-02T23:59:59.000Z

    Approximately 73 m{sup 3} of heterogeneous solid material, ''sludge,'' (upper bound estimate, Packer 1997) have accumulated at the bottom of the K Basins in the 100 K Area of the Hanford Site. This sludge is a mixture of spent fuel element corrosion products, ion exchange materials (organic and inorganic), graphite-based gasket materials, iron and aluminum metal corrosion products, sand, and debris (Makenas et al. 1996, 1997). In addition, small amounts of polychlorinated biphenyls (PCBs) have been found. Ultimately, it is planned to transfer the K Basins sludge to the Hanford double shell tanks (DSTs). The Hanford Spent Nuclear Fuel (HSNF) project has conducted a number of evaluations to examine technology and processing alternatives to pretreat K Basin sludge to meet storage and disposal requirements. From these evaluations, chemical pretreatment has been selected to address criticality issues, reactivity, and the destruction or removal of PCBs before the K Basin sludge can be transferred to the DSTs. Chemical pretreatment, referred to as the K Basin sludge conditioning process, includes nitric acid dissolution of the sludge (with removal of acid insoluble solids), neutrons absorber addition, neutralization, and reprecipitation. Laboratory testing is being conducted by the Pacific Northwest National Laboratory (PNNL) to provide data necessary to develop the sludge conditioning process.

  12. Assessment of Jet Erosion for Potential Post-Retrieval K-Basin Settled Sludge

    SciTech Connect (OSTI)

    Wells, Beric E.; Enderlin, Carl W.; Gauglitz, Phillip A.; Peterson, Reid A.

    2009-09-29T23:59:59.000Z

    Packaged K-Basin sludge will be transported to the T Plant on the Hanford Site where it will be interim stored. The sludge will be retrieved from the storage containers and processed for disposal. A sample of high uranium content canister sludge, designated 96-13, "self-cemented" during laboratory storage. This sample was uncharacteristically strong compared to expected K-Basin material. The purpose for this work is to evaluate the potential retrieval of such sludge after storage at the T Plant via jet erosion. The specific objectives of this report are to determine the modes of erosion and the methods used to measure/assess the erodibility parameters of sludge and identify those parameters applicable to jet erosion. The erodibility parameters of sample 96-13 are characterized to the extent possible. These objectives have been met based on literature review, past experience at Pacific Northwest National Laboratory, and observation of sample 96-13 video during hot-cell activities.

  13. Gas Generation from K East Basin Sludges and Irradiated Metallic Uranium Fuel Particles Series III Testing

    SciTech Connect (OSTI)

    Schmidt, Andrew J.; Delegard, Calvin H.; Bryan, Samuel A.; Elmore, Monte R.; Sell, Rachel L.; Silvers, Kurt L.; Gano, Susan R.; Thornton, Brenda M.

    2003-08-01T23:59:59.000Z

    The path forward for managing of Hanford K Basin sludge calls for it to be packaged, shipped, and stored at T Plant until final processing at a future date. An important consideration for the design and cost of retrieval, transportation, and storage systems is the potential for heat and gas generation through oxidation reactions between uranium metal and water. This report, the third in a series (Series III), describes work performed at the Pacific Northwest National Laboratory (PNNL) to assess corrosion and gas generation from irradiated metallic uranium particles (fuel particles) with and without K Basin sludge addition. The testing described in this report consisted of 12 tests. In 10 of the tests, 4.3 to 26.4 g of fuel particles of selected size distribution were placed into 60- or 800-ml reaction vessels with 0 to 100 g settled sludge. In another test, a single 3.72-g fuel fragment (i.e., 7150-mm particle) was placed in a 60 ml reaction vessel with no added sludge. The twelfth test contained only sludge. The fuel particles were prepared by crushing archived coupons (samples) from an irradiated metallic uranium fuel element. After loading the sludge materials (whether fuel particles, mixtures of fuel particles and sludge, or sludge-only) into reaction vessels, the solids were covered with an excess of K Basin water, the vessels closed and connected to a gas measurement manifold, and the vessels back-flushed with inert neon cover gas. The vessels were then heated to a constant temperature. The gas pressures and temperatures were monitored continuously from the times the vessels were purged. Gas samples were collected at various times during the tests, and the samples analyzed by mass spectrometry. Data on the reaction rates of uranium metal fuel particles with water as a function of temperature and particle size were generated. The data were compared with published studies on metallic uranium corrosion kinetics. The effects of an intimate overlying sludge layer (''blanket'') on the uranium metal corrosion rates were also evaluated.

  14. 15th International Conference Ramiran, May 3-6, 2013, Versailles Accounting GHG emissions from sludge treatment and disposal routes

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    sludge treatment and disposal routes ­ methodological problems focused on sludge land spreading% of sewage sludge is directly land spreading or composted before land spreading. Sludge application to quantify GHG emissions emitted during sludge treatment and disposal routes. This paper aims to present how

  15. A nonlinear observer design for an activated sludge wastewater treatment process

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    A nonlinear observer design for an activated sludge wastewater treatment process B. Boulkrounea , M of the proposed observer are shown through the application to an activated sludge process model. Keywords : Activated sludge, wastewater treatment process, Lyapunov function, Lips- chitz singular discrete

  16. Mitigation of Hydrogen Gas Generation from the Reaction of Uranium Metal with Water in K Basin Sludge and Sludge Waste Forms

    SciTech Connect (OSTI)

    Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.

    2011-06-08T23:59:59.000Z

    Prior laboratory testing identified sodium nitrate and nitrite to be the most promising agents to minimize hydrogen generation from uranium metal aqueous corrosion in Hanford Site K Basin sludge. Of the two, nitrate was determined to be better because of higher chemical capacity, lower toxicity, more reliable efficacy, and fewer side reactions than nitrite. The present lab tests were run to determine if nitrate’s beneficial effects to lower H2 generation in simulated and genuine sludge continued for simulated sludge mixed with agents to immobilize water to help meet the Waste Isolation Pilot Plant (WIPP) waste acceptance drainable liquid criterion. Tests were run at ~60°C, 80°C, and 95°C using near spherical high-purity uranium metal beads and simulated sludge to emulate uranium-rich KW containerized sludge currently residing in engineered containers KW-210 and KW-220. Immobilization agents tested were Portland cement (PC), a commercial blend of PC with sepiolite clay (Aquaset II H), granulated sepiolite clay (Aquaset II G), and sepiolite clay powder (Aquaset II). In all cases except tests with Aquaset II G, the simulated sludge was mixed intimately with the immobilization agent before testing commenced. For the granulated Aquaset II G clay was added to the top of the settled sludge/solution mixture according to manufacturer application directions. The gas volumes and compositions, uranium metal corrosion mass losses, and nitrite, ammonia, and hydroxide concentrations in the interstitial solutions were measured. Uranium metal corrosion rates were compared with rates forecast from the known uranium metal anoxic water corrosion rate law. The ratios of the forecast to the observed rates were calculated to find the corrosion rate attenuation factors. Hydrogen quantities also were measured and compared with quantities expected based on non-attenuated H2 generation at the full forecast anoxic corrosion rate to arrive at H2 attenuation factors. The uranium metal corrosion rates in water alone and in simulated sludge were near or slightly below the metal-in-water rate while nitrate-free sludge/Aquaset II decreased rates by about a factor of 3. Addition of 1 M nitrate to simulated sludge decreased the corrosion rate by a factor of ~5 while 1 M nitrate in sludge/Aquaset II mixtures decreased the corrosion rate by ~2.5 compared with the nitrate-free analogues. Mixtures of simulated sludge with Aquaset II treated with 1 M nitrate had uranium corrosion rates about a factor of 8 to 10 lower than the water-only rate law. Nitrate was found to provide substantial hydrogen mitigation for immobilized simulant sludge waste forms containing Aquaset II or Aquaset II G clay. Hydrogen attenuation factors of 1000 or greater were determined at 60°C for sludge-clay mixtures at 1 M nitrate. Hydrogen mitigation for tests with PC and Aquaset II H (which contains PC) were inconclusive because of suspected failure to overcome induction times and fully enter into anoxic corrosion. Lessening of hydrogen attenuation at ~80°C and ~95°C for simulated sludge and Aquaset II was observed with attenuation factors around 100 to 200 at 1 M nitrate. Valuable additional information has been obtained on the ability of nitrate to attenuate hydrogen gas generation from solution, simulant K Basin sludge, and simulant sludge with immobilization agents. Details on characteristics of the associated reactions were also obtained. The present testing confirms prior work which indicates that nitrate is an effective agent to attenuate hydrogen from uranium metal corrosion in water and simulated K Basin sludge to show that it is also effective in potential candidate solidified K Basin waste forms for WIPP disposal. The hydrogen mitigation afforded by nitrate appears to be sufficient to meet the hydrogen generation limits for shipping various sludge waste streams based on uranium metal concentrations and assumed waste form loadings.

  17. Evaluation of Ion Exchange Materials in K Basin Floor Sludge and Potential Solvents for PCB Extraction from Ion Exchange Materials

    SciTech Connect (OSTI)

    Schmidt, A.J.; Klinger, G.S.; Bredt, P.R.

    1999-04-10T23:59:59.000Z

    Approximately 73 m{sup 3} of heterogeneous solid material, ''sludge,'' (upper bound estimate, Packer 1997) have accumulated at the bottom of the K Basins in the 100 K Area of the Hanford Site. This sludge is a mixture of spent fuel element corrosion products, ion exchange materials (organic and inorganic), graphite-based gasket materials, iron and aluminum metal corrosion products, sand, and debris (Makenas et al. 1996, 1997). In addition, small amounts of polychlorinated biphenyls (PCBs) have been found. These small amounts are significant from a regulatory standpoint. Ultimately, it is planned to transfer the K Basins sludge to the Hanford double shell tanks (DSTs). Chemical pretreatment is required to address criticality issues and the destruction or removal of PCBs before the K Basin sludge can be transferred to the DSTs. Eleven technologies have been evaluated (Papp 1997) as potential pretreatment methods. Based on the evaluations and engineering studies and limited testing, Fluor Daniel Hanford recommended solvent washing of the K Basin sludge, followed by nitric acid dissolution and, potentially, peroxide addition (FDH 1997). The solvent washing (extraction) and peroxide addition would be used to facilitate PCB removal and destruction. Following solvent extraction, the PCBs could be distilled and concentrated for disposal as a low-level waste. The purpose of the work reported here was to continue investigating solvent extraction, first by better identifying the ion exchange materials in the actual sludge samples and then evaluating various solvents for removing the PCBs or possibly dissolving the resins. This report documents some of the process knowledge on ion exchange materials used and spilled in the K Basins and describes the materials identified from wet sieving KE Basin floor and canister sludge and the results of other analyses. Several photographs are included to compare materials and illustrate material behavior. A summary of previous tests on solvent extraction of PCB surrogates from simulant K Basin sludge is also given.

  18. Technical Issues and Characterization for Fuel and Sludge in Hanford K Basins

    SciTech Connect (OSTI)

    MAKENAS, B.J.

    2000-06-01T23:59:59.000Z

    Technical Issues for the interim dry storage of N Reactor Spent Nuclear Fuel (SNF) are discussed. Characterization data from fuel, to support resolution of these issues, are reviewed and new results for the oxidation of fuel in a moist atmosphere and the drying of whole fuel elements are presented. Characterization of associated K basin sludge is also discussed in light of a newly adopted disposal pathway.

  19. Fermentation and chemical treatment of pulp and paper mill sludge

    DOE Patents [OSTI]

    Lee, Yoon Y; Wang, Wei; Kang, Li

    2014-12-02T23:59:59.000Z

    A method of chemically treating partially de-ashed pulp and/or paper mill sludge to obtain products of value comprising taking a sample of primary sludge from a Kraft paper mill process, partially de-ashing the primary sludge by physical means, and further treating the primary sludge to obtain the products of value, including further treating the resulting sludge and using the resulting sludge as a substrate to produce cellulase in an efficient manner using the resulting sludge as the only carbon source and mixtures of inorganic salts as the primary nitrogen source, and including further treating the resulting sludge and using the resulting sludge to produce ethanol.

  20. ESTABoues, a decision tool to assess greenhouse gases of sewage sludge treatment and di

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    ORBIT2012 G ESTABoues, a decision tool to assess greenhouse gases of sewage sludge treatment and di-laure.reverdy@irstea.fr EXECUTIVE SUMMARY Sewage sludge production increases continuously reaching almost 20% (946 700 t 1 118 795% was incinerated (with or without household wastes) or landfilled. Nowadays, sludge reduction is a major concern

  1. Optimal Siting of Regional Fecal Sludge Treatment Facilities: St. Elizabeth, Jamaica

    E-Print Network [OSTI]

    Vogel, Richard M.

    Optimal Siting of Regional Fecal Sludge Treatment Facilities: St. Elizabeth, Jamaica Ana Martha- ated with their mismanagement and deterioration. Historically, fecal sludge management has been-9496 2008 134:1 55 CE Database subject headings: Sludge; System analysis; Waste stabilization ponds

  2. Treatment of septage in sludge drying reed beds: a case study on pilot-scale beds

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Treatment of septage in sludge drying reed beds: a case study on pilot-scale beds S. Troesch***, A systems by local authorities. This will result in a large increase of the quantity of sludge from septic to treat this sludge because they may have reached their nominal load or they are not so numerous in rural

  3. Sludge Treatment and Extraction Technology Development: Results of FY 1993 studies

    SciTech Connect (OSTI)

    Lumetta, G.J.; Wagner, M.J.; Barrington, R.J.; Rapko, B.M.; Carlson, C.D.

    1994-03-01T23:59:59.000Z

    This report describes experimental results from work conducted in FY 1993 under the Sludge Treatment and Extraction Technology Development Task of the Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project at Pacific Northwest Laboratory (PNL). Experiments were conducted in the following six general areas: (1) sludge washing, (2) sludge leaching, (3) sludge dissolution, (4) actinide separation by solvent extraction and extraction chromatography, (5) Sr separation by solvent extraction, and (6) extraction of Cs from acidic solution.

  4. New developments in microwave treatment of steel mill sludges

    SciTech Connect (OSTI)

    Goodwill, J.E.; Schmitt, R.J. [EPRI Center for Materials Production, Pittsburgh, PA (United States); Purta, D.A. [Carnegie Mellon Research Inst., Pittsburgh, PA (United States)

    1996-02-01T23:59:59.000Z

    Steel mills in the US generate approximately 1 million tons of sludge annually. This is mainly a residue of cooling water, lubricating oils, and metallic fines from hot strip rolling mills and other operations. Currently, the separation of sludge from the liquid requires large settling tanks, takes several hours of time and produces a residue that must be disposed of at high cost. The EPRI Center for Materials Production, sponsored by the Electric Power Research Institute (EPRI), has supported development of a microwave-based treatment system. This new process, developed by Carnegie Mellon Research Institute, and patented by EPRI is 30 times faster, requires 90% less space and eliminates land-filling by producing materials of value. Electricity usage is only 0.5 kwhr/gal. A review by the American Iron and Steel Institute Waste Recycle Technology Task Force concluded that further work on the microwave technology was justified. Subsequently, additional work was undertaken toward optimizing the process for treating metallic waste sludges containing lime and polymers. This effort, cofunded by EPRI and AISI, was successfully concluded in late 1994. EPRI/CMP is proceeding to license and commercialize this technology, and to continue research to improve efficiency. A follow-on project is now being organized by CMP to confirm long term recyclability of the oil-release agent and to conduct a large scale (25-ton sample) test of the process.

  5. ASSESSING GHG EMISSIONS FROM SLUDGE TREATMENT AND DISPOSAL ROUTES THE METHOD BEHIND GESTABOUES TOOL

    E-Print Network [OSTI]

    Boyer, Edmond

    stakeholders to better understand the carbon footprint of sludge treatment and disposal options, we developed by a wastewater treatment plant of x per-captia-equivalents (PCE) during one year. The carbon footprint method we developed is adapted to sludge treatment and disposal processes and based on the "Bilan Carbone® " method

  6. BEHAVIOR CANOLA (BRASSICA NAPUS) FOLLOWING A SEWAGE SLUDGE TREATMENT

    E-Print Network [OSTI]

    Boyer, Edmond

    especially Zn. Key words: heavy metals, accumulation, Brassica Napus, urban sludge, industrial sludge. 1. When purifying wastewater, heavy metals accumulate in the sludge. Thus, the sludge contains significant activities, heavy metals (Cu, Pb, Cr) actually raise issues of particular concern. These non

  7. Choices of canisters and elements for the first fuel and canister sludge shipment from K East Basin

    SciTech Connect (OSTI)

    Makenas, B.J.

    1996-03-22T23:59:59.000Z

    The K East Basin contains open-top canisters with up to fourteen N Reactor fuel assemblies distributed between the two barrels of each canister. Each fuel assembly generally consists of inner and outer concentric elements fabricated from uranium metal with zirconium alloy cladding. The canisters also contain varying amounts of accumulated sludge. Retrieval of sample fuel elements and associated sludge for examination is scheduled to occur in the near future. The purpose of this document is to specify particular canisters and elements of interest as candidate sources of fuel and sludge to be shipped to laboratories.

  8. LESSONS LEARNED FROM CLEANING OUT THE SLUDGE FROM THE SPENT FUEL STORAGE BASINS AT HANFORD ICEM-07

    SciTech Connect (OSTI)

    KNOLLMEYER PM

    2007-08-31T23:59:59.000Z

    Until 2004, the K Basins at Hanford, in southeastern Washington State, held the largest collection of spent nuclear fuel in the United States Department of Energy (DOE) complex. The K East and K West Basins are massive pools each holding more than 4 million liters of water - that sit less than 450 meters from the Columbia River. In a significant multi-year campaign that ended in 2004, Fluor Hanford removed all of the fuel from the two Basins, over 2,300 metric tons (4.6 million pounds), dried it, and then placed it into dry storage in a specially designed facility away from the River. Removing the fuel, however, did not finish the cleanup work at the K Basins. The years of underwater storage had corroded the metallic uranium fuel, leaving behind a thick and sometimes hard-packed layer of sludge that coated the walls, floors and equipment inside the Basins. In places, the depth of the sludge was measured in feet rather than inches, and its composition was definitely not uniform. Together the Basins held an estimated 50 cubic meters of sludge (42 cubic meters in K East and 8 cubic meters in K West). The K East sludge retrieval and transfer work was completed in May 2007. Vacuuming up the sludge into large underwater containers in each of the Basins and then consolidating it all in containers in the K West Basin have presented significant challenges, some unexpected. This paper documents some of those challenges and presents the lessons learned so that other nuclear cleanup projects can benefit from the experience at Hanford.

  9. SLUDGE TREATMENT PROJECT ENGINEERED CONTAINER RETRIEVAL AND TRANSFER SYSTEM PRELIMINARY DESIGN HAZARD ANALYSIS SUPPLEMENT 1

    SciTech Connect (OSTI)

    FRANZ GR; MEICHLE RH

    2011-07-18T23:59:59.000Z

    This 'What/If' Hazards Analysis addresses hazards affecting the Sludge Treatment Project Engineered Container Retrieval and Transfer System (ECRTS) NPH and external events at the preliminary design stage. In addition, the hazards of the operation sequence steps for the mechanical handling operations in preparation of Sludge Transport and Storage Container (STSC), disconnect STSC and prepare STSC and Sludge Transport System (STS) for shipping are addressed.

  10. BULKING SLUDGE TREATMENT BY MICROSCOPIC OBSERVATION AND MECHANICAL TREATMENT

    E-Print Network [OSTI]

    for the operation of the biological stage of waste water treatment plants. If the threatening extensive growth of wastewater treatment plants often need a complex control for the optimal processing. The measurement status and for the regulation of biological parts in waste water treatment plants. Furthermore, e

  11. LESSONS LEARNED IN OPERATING THE HOSE-IN-HOSE SYSTEM FOR TRANSFSERRING SLUDGE AT HANFORDS K-BASINS

    SciTech Connect (OSTI)

    PERES MW

    2008-01-07T23:59:59.000Z

    In May 2007, the Department of Energy and the Fluor Hanford K Basin Closure Project completed transferring sludge from the K East Basin to new containers in the K West Basin using a Hose-in-Hose system. This project presented a number of complex and unique technical, operational, and management challenges that had to be resolved to complete the required transfers and satisfy project milestones. The project team (including DOE; regulators; and Fluor management, operations, maintenance, engineering and all other support organizations) found innovative solutions to each challenge. This paper records lessons learned during the operational phase of the sludge transfer via the Hose-In-Hose system. The subject is limited to the operational phase and does not cover design, development, testing or turnover. A discussion of the situation or problem encountered is provided, along with the lesson learned as applicable to a future program or project.

  12. Improvement of the activated sludge treatment by its combination with electro Fenton for the mineralization of sulfamethazine

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Improvement of the activated sludge treatment by its combination with electro Fenton and quantified intermediates are proposed. In a second part, biological treatments with fresh activated sludge the relevance of the proposed combined process. Keywords: Activated sludge; Combined process; Degradation

  13. Treatment of nitrous off-gas from dissolution of sludges

    SciTech Connect (OSTI)

    Flament, T.A.

    1998-08-25T23:59:59.000Z

    Several configurations have been reviewed for the NO{sub x} removal of dissolver off-gas. A predesign has been performed and operating conditions have been optimized. Simple absorption columns seems to be sufficient. NHC is in charge of the treatment of sludges containing mainly uranium dioxide and metallic uranium. The process is based on the following processing steps a dissolution step to oxidize the pyrophoric materials and to dissolve radionuclides (uranium, plutonium, americium and fission products), a solid/liquid separation to get rid of the insoluble solids (to be disposed at ERDF), an adjustment of the acid liquor with neutronic poisons, and neutralization of the acid liquor with caustic soda. The dissolution step generates a flow of nitrous fumes which was evaluated in a previous study. This NO{sub x} flow has to be treated. The purpose of this report is to study the treatment process of the nitrous vapors and to 0482 perform a preliminary design. Several treatment configurations are studied and the most effective process option with respect to the authorized level of discharge into atmosphere is discussed. As a conclusion, recommendations concerning the unit preliminary design are given.

  14. Mitigation of Hydrogen Gas Generation from the Reaction of Water with Uranium Metal in K Basins Sludge

    SciTech Connect (OSTI)

    Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.

    2010-01-29T23:59:59.000Z

    Means to decrease the rate of hydrogen gas generation from the chemical reaction of uranium metal with water were identified by surveying the technical literature. The underlying chemistry and potential side reactions were explored by conducting 61 principal experiments. Several methods achieved significant hydrogen gas generation rate mitigation. Gas-generating side reactions from interactions of organics or sludge constituents with mitigating agents were observed. Further testing is recommended to develop deeper knowledge of the underlying chemistry and to advance the technology aturation level. Uranium metal reacts with water in K Basin sludge to form uranium hydride (UH3), uranium dioxide or uraninite (UO2), and diatomic hydrogen (H2). Mechanistic studies show that hydrogen radicals (H·) and UH3 serve as intermediates in the reaction of uranium metal with water to produce H2 and UO2. Because H2 is flammable, its release into the gas phase above K Basin sludge during sludge storage, processing, immobilization, shipment, and disposal is a concern to the safety of those operations. Findings from the technical literature and from experimental investigations with simple chemical systems (including uranium metal in water), in the presence of individual sludge simulant components, with complete sludge simulants, and with actual K Basin sludge are presented in this report. Based on the literature review and intermediate lab test results, sodium nitrate, sodium nitrite, Nochar Acid Bond N960, disodium hydrogen phosphate, and hexavalent uranium [U(VI)] were tested for their effects in decreasing the rate of hydrogen generation from the reaction of uranium metal with water. Nitrate and nitrite each were effective, decreasing hydrogen generation rates in actual sludge by factors of about 100 to 1000 when used at 0.5 molar (M) concentrations. Higher attenuation factors were achieved in tests with aqueous solutions alone. Nochar N960, a water sorbent, decreased hydrogen generation by no more than a factor of three while disodium phosphate increased the corrosion and hydrogen generation rates slightly. U(VI) showed some promise in attenuating hydrogen but only initial testing was completed. Uranium metal corrosion rates also were measured. Under many conditions showing high hydrogen gas attenuation, uranium metal continued to corrode at rates approaching those observed without additives. This combination of high hydrogen attenuation with relatively unabated uranium metal corrosion is significant as it provides a means to eliminate uranium metal by its corrosion in water without the accompanying hazards otherwise presented by hydrogen generation.

  15. System Description for the KW Basin Integrated Water Treatment System (IWTS) (70.3)

    SciTech Connect (OSTI)

    DERUSSEAU, R.R.

    2000-04-18T23:59:59.000Z

    This is a description of the system that collects and processes the sludge and radioactive ions released by the spent nuclear fuel (SNF) processing operations conducted in the 105 KW Basin. The system screens, settles, filters, and conditions the basin water for reuse. Sludge and most radioactive ions are removed before the water is distributed back to the basin pool. This system is part of the Spent Nuclear Fuel Project (SNFP).

  16. CONTROL OF AN IDEAL ACTIVATED SLUDGE PROCESS IN WASTEWATER TREATMENT VIA AN ODE-PDE MODEL

    E-Print Network [OSTI]

    Diehl, Stefan

    CONTROL OF AN IDEAL ACTIVATED SLUDGE PROCESS IN WASTEWATER TREATMENT VIA AN ODE-PDE MODEL STEFAN treatment plants, consists basically of a biological reactor followed by a sedi- mentation tank, which has. 1. Introduction The need for efficient wastewater treatment plants in terms of low effluent con

  17. K-Basin sludge treatment facility pump test report

    SciTech Connect (OSTI)

    SQUIER, D.M.

    1999-06-02T23:59:59.000Z

    Tests of a disc pump and a dual diaphragm pump are stymied by pumping a metal laden fluid. Auxiliary systems added to a diaphragm pump might enable the transfer of such fluids, but the additional system complexity is not desirable for remotely operated and maintained systems.

  18. K Basins Sludge Treatment Process | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122Commercial602 1,39732on ArmedManufacturingJune 17, 2015 - SEAB Meeting JuneProcess K

  19. K Basins Sludge Treatment Project Phase 1 | Department of Energy

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 111 1,613 122Commercial602 1,39732on ArmedManufacturingJune 17, 2015 - SEAB Meeting JuneProcess

  20. TECHNOLOGY DEVELOPMENT AND DEPLOYMENT OF SYSTEMS FOR THE RETRIEVAL AND PROCESSING OF REMOTE-HANDLED SLUDGE FROM HANFORD K-WEST FUEL STORAGE BASIN

    SciTech Connect (OSTI)

    RAYMOND RE

    2011-12-27T23:59:59.000Z

    In 2011, significant progress was made in developing and deploying technologies to remove, transport, and interim store remote-handled sludge from the 105-K West Fuel Storage Basin on the Hanford Site in south-central Washington State. The sludge in the 105-K West Basin is an accumulation of degraded spent nuclear fuel and other debris that collected during long-term underwater storage of the spent fuel. In 2010, an innovative, remotely operated retrieval system was used to successfully retrieve over 99.7% of the radioactive sludge from 10 submerged temporary storage containers in the K West Basin. In 2011, a full-scale prototype facility was completed for use in technology development, design qualification testing, and operator training on systems used to retrieve, transport, and store highly radioactive K Basin sludge. In this facility, three separate systems for characterizing, retrieving, pretreating, and processing remote-handled sludge were developed. Two of these systems were successfully deployed in 2011. One of these systems was used to pretreat knockout pot sludge as part of the 105-K West Basin cleanup. Knockout pot sludge contains pieces of degraded uranium fuel ranging in size from 600 {mu}m to 6350 {mu}m mixed with pieces of inert material, such as aluminum wire and graphite, in the same size range. The 2011 pretreatment campaign successfully removed most of the inert material from the sludge stream and significantly reduced the remaining volume of knockout pot product material. Removing the inert material significantly minimized the waste stream and reduced costs by reducing the number of transportation and storage containers. Removing the inert material also improved worker safety by reducing the number of remote-handled shipments. Also in 2011, technology development and final design were completed on the system to remove knockout pot material from the basin and transport the material to an onsite facility for interim storage. This system is scheduled for deployment in 2012. The prototype facility also was used to develop technology for systems to retrieve remote-handled transuranic sludge smaller than 6350 {mu}m being stored in underwater containers. After retrieving the sludge, the system will be used to load and transport the sludge for interim storage. During 2011, full-scale prototype systems were developed and tested to a Technology Readiness Level 6 as defined by U.S. Department of Energy standards. This system is scheduled for deployment in 2013. Operations also are scheduled for completion in 2014.

  1. Evaluation of Shear Strength Threshold of Concern for Retrieval of Interim-Stored K-Basin Sludge in the Hanford Site

    SciTech Connect (OSTI)

    Onishi, Yasuo; Yokuda, Satoru T.; Schmidt, Andrew J.

    2010-11-01T23:59:59.000Z

    K-Basin sludge will be recovered into the Sludge Transport and Storage Containers (STSCs) and will be stored in the T Plant for interim storage (at least 10 years). Long-term sludge storage tests conducted by Pacific Northwest National Laboratory show that high uranium content K Basin sludge can self-cement and form a strong sludge with a bulk shear strength of up to 65 kPa. Some of this sludge has "paste" and "chunks" with shear strengths of approximately 3~5 kPa and 380 ~ 770 kPa, respectively. High uranium content sludge samples subjected to hydrothermal testing (e.g., 185°C, 10 h) have been observed to form agglomerates with a shear strength up to 170 kPa. After interim storage at T Plant, the sludge in the STSCs will be mobilized by water jets impinging the sludge. The objective of the evaluation was to determine the range of sludge shear strength for which there is high confidence that a water-jet retrieval system can mobilize stored K-Basin sludge from STSCs. The shear strength at which the sludge can be retrieved is defined as the "shear strength threshold of concern." If the sludge shear strength is greater than the value of the shear strength threshold of concern, a water-jet retrieval system will be unlikely to mobilize the sludge up to the container’s walls. The shear strength threshold of concern can be compared with the range of possible shear strengths of K-Basin stored sludge to determine if the current post interim-storage, water-jet retrieval method is adequate. Fourteen effective cleaning radius (ECR) models were reviewed, and their validity was examined by applying them to Hanford 241-SY-101 and 241-AZ-101 Tanks to reproduce the measured ECR produced by the mixer pumps. The validation test identified that the Powell-3 and Crowe-2 ECR models are more accurate than other ECR models reviewed. These ECR models were used to address a question as to whether the effective cleaning radius of a water jet is sufficient or if it can be readily expanded to cover the range of possible shear strengths. These results will assist CH2M HILL Plateau Remediation Company (CHPRC) to establish the technical basis of the feasibility of the sludge retrieval and storage plan and to develop an adequate water jet system to retrieve the stored K-Basin sludge in the STSCs. The STSCs are 2:1 elliptical-head vessels, 58 inches in diameter and 105 inches tall. Each STSC will contain 0.5 to 2.1 m3 of settled sludge with the specific loading dependent upon sludge type.

  2. DEVELOPMENT OF WET-OXIDATION TREATMENT SYSTEM FOR FILTER BACKWASH SLUDGE AND ION EXCHANGE RESINS

    SciTech Connect (OSTI)

    Miyamoto, T.; Motoyama, M.; Shibuya, M.; Wada, H.; Yamazaki, K.

    2003-02-27T23:59:59.000Z

    Decomposition of organic compounds contained in filter backwash sludge and spent ion exchange resins is considered effective in reducing the waste volume. A system using the wet-oxidation process has been studied for the treatment of the sludge and resins stored at Tsuruga Power Station Unit 1, 357MWe BWR, owned by The Japan Atomic Power Company. Compared with various processes for treating sludge and resin, the wet-oxidation system is rather simple and the process conditions are mild. Waste samples collected from storage tanks were processed by wet-oxidation and appropriate decomposition of the organic compounds was verified. After the decomposition the residue can be solidified with cement or bitumen for final disposal. When compared with direct solidification without decomposition, the number of waste packages can be reduced by a factor of a few dozens for the sludge and three for the resin. Additional measures for conditioning secondary waste products have also been studied, and their applicability to the Tsuruga Power Station was verified. Some of the conditions studied were specific to the Tsuruga Power Station, but it is expected that the system will provide an effective solution for sludge and resin treatment at other NPPs.

  3. MWIP: Surrogate formulations for thermal treatment of low-level mixed waste. Part 4, Wastewater treatment sludges

    SciTech Connect (OSTI)

    Bostick, W.D.; Hoffmann, D.P.; Stevenson, R.J.; Richmond, A.A. [Oak Ridge National Lab., TN (United States); Bickford, D.F. [Westinghouse Savannah River Co., Aiken, SC (United States)

    1994-01-01T23:59:59.000Z

    The category of sludges, filter cakes, and other waste processing residuals represent the largest volume of low-level mixed (hazardous and radioactive) wastes within the US Department of Energy (DOE) complex. Treatment of these wastes to minimize the mobility of contaminants, and to eliminate the presence of free water, is required under the Federal Facility Compliance Act agreements between DOE and the Environmental Protection Agency. In the text, we summarize the currently available data for several of the high priority mixed-waste sludge inventories within DOE. Los Alamos National Laboratory TA-50 Sludge and Rocky Flats Plant By-Pass Sludge are transuranic (TRU)-contaminated sludges that were isolated with the use of silica-based filter aids. The Oak Ridge Y-12 Plant West End Treatment Facility Sludge is predominantly calcium carbonate and biomass. The Oak Ridge K-25 Site Pond Waste is a large-volume waste stream, containing clay, silt, and other debris in addition to precipitated metal hydroxides. We formulate ``simulants`` for the waste streams described above, using cerium oxide as a surrogate for the uranium or plutonium present in the authentic material. Use of nonradiological surrogates greatly simplifies material handling requirements for initial treatability studies. The use of synthetic mixtures for initial treatability testing will facilitate compositional variation for use in conjunction with statistical design experiments; this approach may help to identify any ``operating window`` limitations. The initial treatability testing demonstrations utilizing these ``simulants`` will be based upon vitrification, although the materials are also amenable to testing grout-based and other stabilization procedures. After the feasibility of treatment and the initial evaluation of treatment performance has been demonstrated, performance must be verified using authentic samples of the candidate waste stream.

  4. SLUDGE TREATMENT PROJECT KOP DISPOSITION - THERMAL AND GAS ANALYSIS FOR THE COLD VACUUM DRYING FACILITY

    SciTech Connect (OSTI)

    SWENSON JA; CROWE RD; APTHORPE R; PLYS MG

    2010-03-09T23:59:59.000Z

    The purpose of this document is to present conceptual design phase thermal process calculations that support the process design and process safety basis for the cold vacuum drying of K Basin KOP material. This document is intended to demonstrate that the conceptual approach: (1) Represents a workable process design that is suitable for development in preliminary design; and (2) Will support formal safety documentation to be prepared during the definitive design phase to establish an acceptable safety basis. The Sludge Treatment Project (STP) is responsible for the disposition of Knock Out Pot (KOP) sludge within the 105-K West (KW) Basin. KOP sludge consists of size segregated material (primarily canister particulate) from the fuel and scrap cleaning process used in the Spent Nuclear Fuel process at K Basin. The KOP sludge will be pre-treated to remove fines and some of the constituents containing chemically bound water, after which it is referred to as KOP material. The KOP material will then be loaded into a Multi-Canister Overpack (MCO), dried at the Cold Vacuum Drying Facility (CVDF) and stored in the Canister Storage Building (CSB). This process is patterned after the successful drying of 2100 metric tons of spent fuel, and uses the same facilities and much of the same equipment that was used for drying fuel and scrap. Table ES-l present similarities and differences between KOP material and fuel and between MCOs loaded with these materials. The potential content of bound water bearing constituents limits the mass ofKOP material in an MCO load to a fraction of that in an MCO containing fuel and scrap; however, the small particle size of the KOP material causes the surface area to be significantly higher. This relatively large reactive surface area represents an input to the KOP thermal calculations that is significantly different from the calculations for fuel MCOs. The conceptual design provides for a copper insert block that limits the volume available to receive KOP material, enhances heat conduction, and functions as a heat source and sink during drying operations. This use of the copper insert represents a significant change to the thermal model compared to that used for the fuel calculations. A number of cases were run representing a spectrum of normal and upset conditions for the drying process. Dozens of cases have been run on cold vacuum drying of fuel MCOs. Analysis of these previous calculations identified four cases that provide a solid basis for judgments on the behavior of MCO in drying operations. These four cases are: (1) Normal Process; (2) Degraded vacuum pumping; (3) Open MCO with loss of annulus water; and (4) Cool down after vacuum drying. The four cases were run for two sets of input parameters for KOP MCOs: (1) a set of parameters drawn from safety basis values from the technical data book and (2) a sensitivity set using parameters selected to evaluate the impact of lower void volume and smaller particle size on MCO behavior. Results of the calculations for the drying phase cases are shown in Table ES-2. Cases using data book safety basis values showed dry out in 9.7 hours and heat rejection sufficient to hold temperature rise to less than 25 C. Sensitivity cases which included unrealistically small particle sizes and corresponding high reactive surface area showed higher temperature increases that were limited by water consumption. In this document and in the attachment (Apthorpe, R. and M.G. Plys, 2010) cases using Technical Databook safety basis values are referred to as nominal cases. In future calculations such cases will be called safety basis cases. Also in these documents cases using parameters that are less favorable to acceptable performance than databook safety values are referred to as safety cases. In future calculations such cases will be called sensitivity cases or sensitivity evaluations Calculations to be performed in support of the detailed design and formal safety basis documentation will expand the calculations presented in this document to include: additional features of th

  5. A rational approach for evaluation and screening of treatment and disposal options for the solar pond sludges at Rocky Flats

    SciTech Connect (OSTI)

    Dickerson, K.S.

    1995-12-31T23:59:59.000Z

    This document consists of information about the treatment options for the sludge that is located in the evaporation ponds at the Rocky Flats Plant. The sludges are mixed low-level radioactive wastes whose composition and character were variable. Sludges similar to these are typically treated prior to ultimate disposal. Disposal of treated sludges includes both on-site and off-site options. The rational approach described in this paper is useful for technology evaluation and screening because it provides a format for developing objectives, listing alternatives, and weighing the alternatives against the objectives and against each other.

  6. STP-ECRTS - THERMAL AND GAS ANALYSES FOR SLUDGE TRANSPORT AND STORAGE CONTAINER (STSC) STORAGE AT T PLANT

    SciTech Connect (OSTI)

    CROWE RD; APTHORPE R; LEE SJ; PLYS MG

    2010-04-29T23:59:59.000Z

    The Sludge Treatment Project (STP) is responsible for the disposition of sludge contained in the six engineered containers and Settler tank within the 105-K West (KW) Basin. The STP is retrieving and transferring sludge from the Settler tank into engineered container SCS-CON-230. Then, the STP will retrieve and transfer sludge from the six engineered containers in the KW Basin directly into a Sludge Transport and Storage Containers (STSC) contained in a Sludge Transport System (STS) cask. The STSC/STS cask will be transported to T Plant for interim storage of the STSC. The STS cask will be loaded with an empty STSC and returned to the KW Basin for loading of additional sludge for transportation and interim storage at T Plant. CH2MHILL Plateau Remediation Company (CHPRC) contracted with Fauske & Associates, LLC (FAI) to perform thermal and gas generation analyses for interim storage of STP sludge in the Sludge Transport and Storage Container (STSCs) at T Plant. The sludge types considered are settler sludge and sludge originating from the floor of the KW Basin and stored in containers 210 and 220, which are bounding compositions. The conditions specified by CHPRC for analysis are provided in Section 5. The FAI report (FAI/10-83, Thermal and Gas Analyses for a Sludge Transport and Storage Container (STSC) at T Plant) (refer to Attachment 1) documents the analyses. The process considered was passive, interim storage of sludge in various cells at T Plant. The FATE{trademark} code is used for the calculation. The results are shown in terms of the peak sludge temperature and hydrogen concentrations in the STSC and the T Plant cell. In particular, the concerns addressed were the thermal stability of the sludge and the potential for flammable gas mixtures. This work was performed with preliminary design information and a preliminary software configuration.

  7. alkaline sludge treatment: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental impacts...

  8. activated sludge treatment: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  9. Remote Handled Transuranic Sludge Retrieval Transfer And Storage System At Hanford

    SciTech Connect (OSTI)

    Raymond, Rick E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Frederickson, James R. [AREVA, Avignon (France); Criddle, James [AREVA, Avignon (France); Hamilton, Dennis [CH2M HILL Plateau Remediation Company, Richland, WA (United States); Johnson, Mike W. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2012-10-18T23:59:59.000Z

    This paper describes the systems developed for processing and interim storage of the sludge managed as remote-handled transuranic (RH-TRU). An experienced, integrated CH2M HILL/AFS team was formed to design and build systems to retrieve, interim store, and treat for disposal the K West Basin sludge, namely the Sludge Treatment Project (STP). A system has been designed and is being constructed for retrieval and interim storage, namely the Engineered Container Retrieval, Transfer and Storage System (ECRTS).

  10. Aeration control in a full-scale activated sludge wastewater treatment plant: impact on performances, energy consumption

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    for stratospheric ozone [1]. In biological wastewater treatment, microbial processes such as hydroxylamine oxidationAeration control in a full-scale activated sludge wastewater treatment plant: impact strategy on energy consumption and nitrous oxide (N2O) emission in a full-scale wastewater treatment plant

  11. Mercury-contaminated sludge treatment by dredging in Minamata Bay

    SciTech Connect (OSTI)

    Yoshinaga, Kiyoto [Ministry of Transport, Niigata (Japan)

    1995-12-31T23:59:59.000Z

    To eradicate Minamata Disease, caused by the discharge of sewage containing methyl mercury and its accumulation in fish and shellfish through the food cycle, a large-scale sediment disposal project was conducted with special care taken to prevent new pollution resulting from the project itself. The basic approach to sediment disposal was to construct a highly watertight revetment to reclaim the inner area of the bay and then confine sediment dredged from the remaining contaminated area in the reclamation area through surface treatment. Before sediment disposal, boundary nets were installed to enclose the work area to prevent the mixing of contaminated and noncontaminated fish. Dredging work was successfully carried out by using four cutterless suction dredgers, newly developed in advance for minimizing resuspension of sediments. Dredged material was discharged into the reclamation area, filled up to sea level, and covered with a sandproof membrane, lightweight volcanic ash earth, and mountain soil.

  12. CRAD, Emergency Management - Office of River Protection K Basin...

    Energy Savers [EERE]

    CRAD, Emergency Management - Office of River Protection K Basin Sludge Waste System CRAD, Emergency Management - Office of River Protection K Basin Sludge Waste System May 2004 A...

  13. SLUDGE PARTICLE SEPAPATION EFFICIENCIES DURING SETTLER TANK RETRIEVAL INTO SCS-CON-230

    SciTech Connect (OSTI)

    DEARING JI; EPSTEIN M; PLYS MG

    2009-07-16T23:59:59.000Z

    The purpose of this document is to release, into the Hanford Document Control System, FA1/0991, Sludge Particle Separation Efficiencies for the Rectangular SCS-CON-230 Container, by M. Epstein and M. G. Plys, Fauske & Associates, LLC, June 2009. The Sludge Treatment Project (STP) will retrieve sludge from the 105-K West Integrated Water Treatment System (IWTS) Settler Tanks and transfer it to container SCS-CON-230 using the Settler Tank Retrieval System (STRS). The sludge will enter the container through two distributors. The container will have a filtration system that is designed to minimize the overflow of sludge fines from the container to the basin. FAI/09-91 was performed to quantify the effect of the STRS on sludge distribution inside of and overflow out of SCS-CON-230. Selected results of the analysis and a system description are discussed. The principal result of the analysis is that the STRS filtration system reduces the overflow of sludge from SCS-CON-230 to the basin by roughly a factor of 10. Some turbidity can be expected in the center bay where the container is located. The exact amount of overflow and subsequent turbidity is dependent on the density of the sludge (which will vary with location in the Settler Tanks) and the thermal gradient between the SCS-CON-230 and the basin. Attachment A presents the full analytical results. These results are applicable specifically to SCS-CON-230 and the STRS filtration system's expected operating duty cycles.

  14. INTEC CPP-603 Basin Water Treatment System Closure: Process Design

    SciTech Connect (OSTI)

    Kimmitt, Raymond Rodney; Faultersack, Wendell Gale; Foster, Jonathan Kay; Berry, Stephen Michael

    2002-09-01T23:59:59.000Z

    This document describes the engineering activities that have been completed in support of the closure plan for the Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603 Basin Water Treatment System. This effort includes detailed assessments of methods and equipment for performing work in four areas: 1. A cold (nonradioactive) mockup system for testing equipment and procedures for vessel cleanout and vessel demolition. 2. Cleanout of process vessels to meet standards identified in the closure plan. 3. Dismantlement and removal of vessels, should it not be possible to clean them to required standards in the closure plan. 4. Cleanout or removal of pipelines and pumps associated with the CPP-603 basin water treatment system. Cleanout standards for the pipes will be the same as those used for the process vessels.

  15. Characteristics of STP Pre-2004 Archived KE Basin Sludge Samples Before and After Re-Jarring in the RPL - April 2012

    SciTech Connect (OSTI)

    Sinkov, Sergey I.; Delegard, Calvin H.; Schmidt, Andrew J.; Chenault, Jeffrey W.

    2012-09-28T23:59:59.000Z

    This report describes results of work performed in the Shielded Analytical Laboratory (SAL) at the Pacific Northwest National Laboratory’s (PNNL) Radiochemical Processing Laboratory (RPL) with archive K East (KE) Basin sludge samples obtained before the year 2004, with some of them composited and initially characterized five years ago (Delegard et al. 2011). The previously performed testing included the physical properties determinations for selected samples (settled and particle densities, water and solids concentrations), the pH, as well as identification of crystalline phases by X-ray diffractometry (XRD) for selected samples. Another objective of the previous characterization and testing campaign was to transfer some sludge composites and individual samples into new storage containers to overcome the embrittlement effect which develops in original glass containers as a result of extended exposure to high radiation fields and which increases probability of sample loss.

  16. XRF and leaching characterization of waste glasses derived from wastewater treatment sludges

    SciTech Connect (OSTI)

    Ragsdale, R.G., Jr

    1994-12-01T23:59:59.000Z

    Purpose of this study was to investigate use of XRF (x-ray fluorescence spectrometry) as a near real-time method to determine melter glass compositions. A range of glasses derived from wastewater treatment sludges associated with DOE sites was prepared. They were analyzed by XRF and wet chemistry digestion with atomic absorption/inductively coupled emission spectrometry. Results indicated good correlation between these two methods. A rapid sample preparation and analysis technique was developed and demonstrated by acquiring a sample from a pilot-scale simulated waste glass melter and analyzing it by XRF within one hour. From the results, XRF shows excellent potential as a process control tool for waste glass vitrification. Glasses prepared for this study were further analyzed for durability by toxicity characteristic leaching procedure and product consistency test and results are presented.

  17. Properties and potential uses of water treatment sludge from the Neches River of southeast Texas

    E-Print Network [OSTI]

    Kan, Weiqun

    1995-01-01T23:59:59.000Z

    sludge due to its huge amount and increasing public concern. However, only a few studies were focused on potential use of WTP sludge. The characteristics and potential use of WTP sludge are still not well understood. Previous studies of WTP alum sludge... plants that coagulate, filter, and oxidize a surface water for removal of turbidity, color, bacteria, algae, organic compounds, and iron or manganese. These plants generally use alum Al~(SO4) or iron FeC13 salts for coagulation and produce alum or iron...

  18. Delisting petition for 300-M saltstone (treated F006 sludge) from the 300-M liquid effluent treatment facility

    SciTech Connect (OSTI)

    Not Available

    1989-04-04T23:59:59.000Z

    This petition seeks exclusion for stabilized and solidified sludge material generated by treatment of wastewater from the 300-M aluminum forming and metal finishing processes. The waste contains both hazardous and radioactive components and is classified as a mixed waste. The objective of this petition is to demonstrate that the stabilized sludge material (saltstone), when properly disposed, will not exceed the health-based standards for the hazardous constituents. This petition contains sampling and analytical data which justify the request for exclusion. The results show that when the data are applied to the EPA Vertical and Horizontal Spread (VHS) Model, health-based standards for all hazardous waste constituents will not be exceeded during worst case operating and environmental conditions. Disposal of the stabilized sludge material in concrete vaults will meet the requirements pertaining to Waste Management Activities for Groundwater Protection at the Savannah River Site in Aiken, S.C. Documents set forth performance objectives and disposal options for low-level radioactive waste disposal. Concrete vaults specified for disposal of 300-M saltstone (treated F006 sludge) assure that these performance objectives will be met.

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

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.

    2008-09-25T23:59:59.000Z

    This report summarizes information and data on the reaction behavior of uranium metal in water, in water-saturated simulated and genuine K Basin sludge, and in grout matrices. This information and data are used to establish the technical basis for metallic uranium reaction behavior for the K Basin Sludge Treatment Project (STP). The specific objective of this report is to consolidate the various sources of information into a concise document to serve as a high-level reference and road map for customers, regulators, and interested parties outside the STP (e.g., external reviewers, other DOE sites) to clearly understand the current basis for the corrosion of uranium metal in water, sludge, and grout.

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

    SciTech Connect (OSTI)

    Delegard, Calvin H.; Schmidt, Andrew J.

    2009-05-27T23:59:59.000Z

    This report summarizes information and data on the reaction behavior of uranium metal in water, in water-saturated simulated and genuine K Basin sludge, and in grout matrices. This information and data are used to establish the technical basis for metallic uranium reaction behavior for the K Basin Sludge Treatment Project (STP). The specific objective of this report is to consolidate the various sources of information into a concise document to serve as a high-level reference and road map for customers, regulators, and interested parties outside the STP (e.g., external reviewers, other DOE sites) to clearly understand the current basis for the corrosion of uranium metal in water, sludge, and grout.

  1. Concentrations of Heavy Metals in Soil and Cassava Plant on Sewage Sludge Dump

    E-Print Network [OSTI]

    Igbozuruike, Chris Washington Ifeanyi Mr.; Opara-Nadi, Achilihu Oliver Prof; Okorie, Ikechukwu Kennedy DR

    2009-01-01T23:59:59.000Z

    JM. (1989). Assessment of sludge regulation assumptions: AMunicipal Wasteland and Sludge on Land. Univ. of California,1998). Effects of sewage sludge pre-treatment on microbial

  2. Safety evaluation for packaging for the transport of K Basin sludge samples in the PAS-1 cask

    SciTech Connect (OSTI)

    SMITH, R.J.

    1998-11-17T23:59:59.000Z

    This safety evaluation for packaging authorizes the shipment of up to two 4-L sludge samples to and from the 325 Lab or 222-S Lab for characterization. The safety of this shipment is based on the current U.S. Department of Energy Certification of Compliance (CoC) for the PAS-1 cask, USA/9184/B(U) (DOE).

  3. Evaluation of solidification/stabilization for treatment of a petroleum hydrocarbon contaminated sludge from Fort Polk Army Installation, Louisiana. Final report

    SciTech Connect (OSTI)

    Channell, M.G.; Preston, K.T.

    1996-09-01T23:59:59.000Z

    In the course of normal operations and training, soldiers and civilian personnel operate many Army vehicles on a day-today basis. These vehicles must be cleaned before they can be returned to the motor pool area of an Army base. The cleaning of these vehicles bas posed a problem with the operation and maintenance of oil/water separators located at vehicle washrack facilities. An oily sludge forms in the oil/water separator and is hard to handle and cannot be disposed of in an ordinary manner. This study used solidification/stabilization to treat the oily sludge found in the vehicle washrack oil/water separators. Solidification/stabilization is usually used to treat soils and sludges that contain heavy metals. Organic compounds, such as petroleum hydrocarbons found in the sludge, interfere with the setting of the solidification binding materials and thus produce a material that is not desirable for a treatment alternative. This study incorporates the use of dicalcium silicate as an additive to the solidification process to increase the strength and reduce the leachability of the petroleum hydrocarbons found in the sludge. This study shows that dicalcium silicate improves the handling characteristics of the sludge and reduces the leachability of the contaminants from the washrack sludge.

  4. International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry

    E-Print Network [OSTI]

    Hasanbeigi, Ali

    2013-01-01T23:59:59.000Z

    2008. “Utilization of sewage sludge in EU application of old2007. “Cost evaluation of sludge treatment options andwastewater treatment plant sludge treating leather tanning

  5. Physical-chemical characterization of sludge and granular materials from a vertical flow constructed wetland for municipal wastewater treatment

    E-Print Network [OSTI]

    Boyer, Edmond

    Physical-chemical characterization of sludge and granular materials from a vertical flow considered for phosphorus removal as well. In this article, sludge and granular materials sampled from analyses showed that phosphorus was predominantly captured in the sludge layer accumulated at the surface

  6. Wastewater sludge management options for Honduras

    E-Print Network [OSTI]

    Bhattacharya, Mahua, M. Eng. Massachusetts Institute of Technology.

    2009-01-01T23:59:59.000Z

    Sludge management is a fundamental area of concern across wastewater treatment systems in Honduras. The lack of timely sludge removal has led to declining plant performance in many facilities throughout the country. In ...

  7. Radioactive air emissions notice of construction debris removal 105-KE basin

    SciTech Connect (OSTI)

    HAYS, C.B.

    1999-10-06T23:59:59.000Z

    The 105-KE Basin contains 1,150 Metric Tonnes of Uranium (MTU) of N Reactor fuel, along with less than half a MTU of single pass reactor (SPR) fuel. In addition to the spent nuclear fuel (SNF) in the 105-KE Basin, extensive quantities of debris and a substantial amount of sludge have accumulated in the basin. The 105-KE Basin fuel and sludge are not encapsulated and, as a result, corroding fuel has produced contamination products that are deposited on the basin walls, floor, and equipment. contamination products produce radiation dose exposures to the workers. To decrease worker exposures, this Notice of Construction (NOC) describes dose reduction modifications under consideration to mitigate worker radiation exposure from the basin walls and exposed piping. The major equipment egress paths from the basin (the dummy elevator pit and the south loadout pit) are blocked completely with debris and/or empty canisters. Therefore in addition to dose reduction, this NOC also describes debris removal activities and equipment. Recently, the primary water treatment system has been without mechanical filtration capabilities. This NOC describes planned modifications to the primary water treatment system to restore mechanical filtration by restarting the cartridge filters. The proposed modifications described in this NOC are expected to commence in the Fall of 1995. Finally, the NOC describes two other basin activities, fuel and sludge movement, that are expected to be routine in the future.

  8. Preliminary design report for the K basins integrated water treatment system

    SciTech Connect (OSTI)

    Pauly, T.R., Westinghouse Hanford

    1996-08-12T23:59:59.000Z

    This Preliminary Design Report (PDR) provides a revised concept for the K Basins Integrated Water Treatment Systems (IWTS). This PDR incorporates the 11 recommendations made in a May 1996 Value Engineering session into the Conceptual Design, and provides new flow diagrams, hazard category assessment, cost estimate, and schedule for the IWTS Subproject.

  9. Statement of work for definitive design of the K basins integrated water treatment system project

    SciTech Connect (OSTI)

    Pauly, T.R., Westinghouse Hanford

    1996-07-16T23:59:59.000Z

    This Statement of Work (SOW) identifies the scope of work and schedule requirements for completing definitive design of the K Basins Integrated Water Treatment Systems (IWTS) Subproject. This SOW shall form the contractual basis between WHC and the Design Agent for the Definitive Design.

  10. K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations

    SciTech Connect (OSTI)

    RITTMANN, P.D.

    1999-10-07T23:59:59.000Z

    Three bounding accidents postdated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing, and a hydrogen explosion. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

  11. The effect of chemical composition on the PCT durability of mixed waste glasses from wastewater treatment sludges

    SciTech Connect (OSTI)

    Resce, J.L.; Ragsdale, R.G.; Overcamp, T.J. [Clemson Univ., SC (United States); Bickford, D.F.; Cicero, C.A. [Savannah River Technology Center, Aiken, SC (United States)

    1995-01-25T23:59:59.000Z

    An experimental program has been designed to examine the chemical durability of glass compositions derived from the vitrification of simulated wastewater treatment sludges. These sludges represent the majority of low-level mixed wastes currently in need of treatment by the US DOE. The major oxides in these model glasses included SiO{sub 2}, Al{sub 2}O{sub 3}, B{sub 2}O{sub 3}, Na{sub 2}O, CaO and Fe{sub 2}O{sub 3}. In addition, three minor oxides, BaO, NiO, and PbO, were added as hazardous metals. The major oxides were each varied at two levels resulting in 32 experimental glasses. The chemical durability was measured by the 7-Day Product Consistency Test (PCT). The normalized sodium release rates (NRR{sub Na}) of these glasses ranged from 0.01 to 4.99 g/m{sup 2}. The molar ratio of the glass-former to glass-modifier (F/M) was found to have the greatest effect on PCT durability. Glass-formers included SiO{sub 2}, Al{sub 2}O{sub 3}, and B{sub 2}O{sub 3}, while Na{sub 2}O, CaO, BaO, NiO, and PbO were glass-modifiers. As this ratio increased from 0.75 to 2.0, NRR{sub Na} was found to decrease between one and two orders of magnitude. Another important effect on NRR{sub Na} was the Na{sub 2}O/CaO ratio. As this ratio increased from 0.5 to 2.0, NRR{sub Na} increased up to two orders of magnitude for the glasses with the low F/M ratio but almost no effect was observed for the glasses with the high F/M ratio. Increasing the iron oxide content from 2 to 18 mole% was found to decrease NRR{sub Na} one order of magnitude for the glasses with low F/M but iron had little effect on the glasses with the high F/M ratio. The durability also increased when 10 mole percent Al{sub 2}O{sub 3} was included in low iron oxide glasses but no effect was observed with the high iron glasses. The addition of B{sub 2}O{sub 3} had little effect on durability. The effects of other composition parameters on durability are discussed as well.

  12. K-Basin gel formation studies

    SciTech Connect (OSTI)

    Beck, M.A.

    1998-07-23T23:59:59.000Z

    A key part of the proposed waste treatment for K Basin sludge is the elimination of reactive uranium metal by dissolution in nitric acid (Fkirnent, 1998). It has been found (Delegard, 1998a) that upon nitric acid dissolution of the sludge, a gel sometimes forms. Gels are known to sometimes impair solid/liquid separation and/or material transfer. The purpose of the work reported here is to determine the cause(s) of the gel formation and to determine operating parameters for the sludge dissolution that avoid formation of gel. This work and related work were planned in (Fkunent, 1998), (Jewett, 1998) and (Beck, 1998a). This report describes the results of the tests in (Beck, 1998a) with non-radioactive surrogates.

  13. FIELD PERFORMANCE OF GEOTEXTILE REINFORCED SLUDGE CAPS AHMET H. AYDILEK

    E-Print Network [OSTI]

    Aydilek, Ahmet

    589 FIELD PERFORMANCE OF GEOTEXTILE REINFORCED SLUDGE CAPS AHMET H. AYDILEK UNIVERSITY OF WISCONSIN the filtration performance of sludge-geotextile systems and investigate their durability, ten sludge lagoon test be effectively used in filtering contaminated wastewater treatment sludges. Considering the constructability

  14. Sludge drying reed beds for septage treatment: towards design and operation recommendations

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    : the future of the septage. The aim of this paper is to assess the feasibility of septage treatment by SDRB). Nowadays, septic tank facilities have a widespread distribution, providing a first treatment to household effluent consisting of a solid/liquid separation. Operation efficiency of these systems is subject

  15. Assessment of sludge management options in a waste water treatment plant

    E-Print Network [OSTI]

    Lim, Jong hyun, M. Eng. Massachusetts Institute of Technology

    2012-01-01T23:59:59.000Z

    This thesis is part of a larger project which began in response to a request by the Spanish water agengy, Cadagua, for advice on life cycle assessment (LCA) and environmental impacts of Cadagua operated wastewater treatment ...

  16. Radionuclide Leaching from Residual Solids Remaining after Acid Dissolution of Composite K East Canister Sludge

    SciTech Connect (OSTI)

    Delegard, C.H.; Rinehart, D.E.; Soderquist, C.Z.; Fadeff, S.K.

    1999-04-02T23:59:59.000Z

    Laboratory tests were performed to examine mixed nitric/hydrofluoric acid leach treatments for decontaminating dissolver residual solids (KECDVSR24H-2) produced during a 20- to 24-hr dissolution of a composite K East (KE) Basin canister sludge in 95 C 6 M nitric acid (HNO{sub 3}). The scope of this testing has been described in Section 4.5 of ''Testing Strategy to Support the Development of K Basin Sludge Treatment Process'' (Flament 1998). Radionuclides sorbed or associated with the residual solids generated in the K Basin sludge treatment process can restrict disposal of this solid to the Environmental Restoration Disposal Facility (ERDF). The starting dissolver residual solid for this testing, KECDVSR24H-2, contains radionuclides at concentrations which exceed the ERDF Waste Acceptance Criteria for TRU by about a factor of 70, for {sup 239}Pu by a factor of 200, and for {sup 241}Am by a factor of 50. The solids also exceed the ERDF criterion for {sup 137}Cs by a factor of 2 and uranium by a factor of 5. Therefore, the radionuclides of greatest interest in this leaching study are first {sup 239}Pu and {sup 241}Am (both components of TRU) and then uranium and {sup 137}Cs.

  17. Sludge sampler

    DOE Patents [OSTI]

    Ward, Ralph C. (Los Alamos, NM)

    1983-01-01T23:59:59.000Z

    The disclosure relates to a sludge sampler comprising an elongated generally cylindrical housing containing a baffle containing an aperture. Connected to the aperture is a flexible tubing having a valve for maintaining and releasing pressure in the lower end of the housing and exiting the upper end of the housing. The lower end of the housing contains a ball check valve maintained in closed position by pressure. When the lower end of the device contacts the sludge bed, the pressure valve is opened, enabling sludge to enter the lower end of the housing. After the sample is collected the valve is closed. An upsetting pin opens the valve to empty a sludge sample after the sample is removed from the fluid.

  18. Sludge sampler

    DOE Patents [OSTI]

    Ward, R.C.

    1981-06-25T23:59:59.000Z

    The disclosure relates to a sludge sampler comprising an elongated generally cylindrical housing containing a baffle containing an aperture. Connected to the aperture is a flexible tubing having a valve for maintaining and releasing pressure in the lower end of the housing and exiting the upper end of the housing. The lower end of the housing contains a ball check valve maintained in closed position by pressure. When the lower end of the device contacts the sludge bed, the pressure valve is opened, enabling sludge to enter the lower end of the housing. After the sample is collected the valve is closed. An upsetting pin opens the valve to empty a sludge sample after the sample is removed from the fluid.

  19. Sewage Sludge (Maryland)

    Broader source: Energy.gov [DOE]

    Sewage sludge utilization permits are required prior to the use, processing, and disposal of sewage sludge in Maryland.

  20. HWMA/RCRA Closure Plan for the Basin Facility Basin Water Treatment System - Voluntary Consent Order NEW-CPP-016 Action Plan

    SciTech Connect (OSTI)

    Evans, S. K.

    2007-11-07T23:59:59.000Z

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan for the Basin Water Treatment System located in the Basin Facility (CPP-603), Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Laboratory Site, was developed to meet future milestones established under the Voluntary Consent Order. The system to be closed includes units and associated ancillary equipment included in the Voluntary Consent Order NEW-CPP-016 Action Plan and Voluntary Consent Order SITE-TANK-005 Tank Systems INTEC-077 and INTEC-078 that were determined to have managed hazardous waste. The Basin Water Treatment System will be closed in accordance with the requirements of the Hazardous Waste Management Act/Resource Conservation and Recovery Act, as implemented by the Idaho Administrative Procedures Act 58.01.05.009 and 40 Code of Federal Regulations 265, to achieve "clean closure" of the tank system. This closure plan presents the closure performance standards and methods of achieving those standards for the Basin Water Treatment Systems.

  1. Cold test data for equipment acceptance into 105-KE Basin

    SciTech Connect (OSTI)

    Packer, M.J.

    1994-11-09T23:59:59.000Z

    This document provides acceptance testing of equipment to be installed in the 105-KE Basin for pumping sludge to support the discharge chute barrier doors installation.

  2. Selective hydrolysis of wastewater sludge Part 1, September 2007

    E-Print Network [OSTI]

    the production of biogas based power and heat besides reduce the power consumption from handling and treatment of sludge as if established at the existing sludge digester system. The Esbjerg Renseanlæg Vest is a traditional build plant base don the activated sludge concept besides traditional digester technology

  3. Sludge digester

    SciTech Connect (OSTI)

    Wight, J.L.; Cook, L.W.

    1993-08-24T23:59:59.000Z

    A ballasted, gas-holding, liquid sludge digester is described comprising: a main liquid sludge tank having a bottom wall and upwardly projecting sidewall; a cover having a top and depending side skirt structure which telescopes with respect to the upwardly projecting sidewall of the main tank; ballast supported near the lower edge of said side skirt; a ballast-engaging, liquid-containing well joined to said sidewall of said main tank such that said cover provides a gas-tight seal when said ballast interacts with liquid in said well so as to be partially emerged or fully submerged in the liquid; liquid fill means interacting with said well to maintain a predetermined liquid level in the well when said ballast is at least partially emerged from the liquid in said well; and overflow means interacting with said well to maintain a predetermined liquid level in the well when said ballast is submerged in the liquid in the well.

  4. International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry

    E-Print Network [OSTI]

    Hasanbeigi, Ali

    2013-01-01T23:59:59.000Z

    Sludge treatment to increase biogas production. Available atal. , no date) Use of biogas from anaerobic sludge digestionsludge are mass reduction, biogas production, and improved

  5. Measurement and Treatment of Nuisance Odors at Wastewater Treatment Plants

    E-Print Network [OSTI]

    Abraham, Samantha Margaret

    2014-01-01T23:59:59.000Z

    oil refineries, and waste treatment operations such as composting, sludgeoil refineries, and waste treatment operations such as composting, sludge

  6. Biotechnology to separate and treat metals in sludge and wastewater: A literature review. Final report

    SciTech Connect (OSTI)

    Kim, B.; Cha, D.K.; Song, J.S.

    1995-09-01T23:59:59.000Z

    Army industrial sludge may be classified as a hazardous waste when it contains oil and grease, metals, and energetic compounds. Biologic separation/treatment of metals from industrial sludge has been identified as a possible alternative to conventional technologies for treating industrial sludge. Biologic treatment of sludge uses naturally occurring biochemical reactions in which pollutants can be used as resources. The process offers a low-cost, highly efficient alternative to existing sludge treatment methods. This report summarizes a literature review that examined the development and status of biotechnology to separate and treat metals in sludge and wastewater.

  7. Integrated Water Treatment System (IWTS) Process Flow Diagram Mass Balance Calculations for K West Basin

    SciTech Connect (OSTI)

    REED, A.V.

    2000-02-28T23:59:59.000Z

    The purpose of this calculation is to develop the rational for the material balances that are documented in the KW Basin water system Level 1 process flow diagrams.

  8. Integrating BES in the wastewater and sludge

    E-Print Network [OSTI]

    Angenent, Lars T.

    , denitrification, and anaerobic digester treatment systems, while chemical methods include phosphate removal, dye of WAS, including treatment of influent or the accumulated sludge with anaerobic digesters (Rulkens 2008; Seghezzo et al. 1998). This is a more sustainable treatment method because methane in biogas can partly

  9. Pretreatment of microbial sludges

    DOE Patents [OSTI]

    Rivard, Christopher J. (Lakewood, CO); Nagle, Nicholas J. (Louisville, CO)

    1995-01-01T23:59:59.000Z

    Methods are described for pretreating microbial sludges to break cells and disrupt organic matter. One method involves the use of sonication, and another method involves the use of shear forces. The pretreatment of sludge enhances bioconversion of the organic fraction. This allows for efficient dewatering of the sludge and reduces the cost for final disposal of the waste.

  10. Pretreatment of microbial sludges

    DOE Patents [OSTI]

    Rivard, C.J.; Nagle, N.J.

    1995-01-10T23:59:59.000Z

    Methods are described for pretreating microbial sludges to break cells and disrupt organic matter. One method involves the use of sonication, and another method involves the use of shear forces. The pretreatment of sludge enhances bioconversion of the organic fraction. This allows for efficient dewatering of the sludge and reduces the cost for final disposal of the waste.

  11. K Basin safety analysis

    SciTech Connect (OSTI)

    Porten, D.R.; Crowe, R.D.

    1994-12-16T23:59:59.000Z

    The purpose of this accident safety analysis is to document in detail, analyses whose results were reported in summary form in the K Basins Safety Analysis Report WHC-SD-SNF-SAR-001. The safety analysis addressed the potential for release of radioactive and non-radioactive hazardous material located in the K Basins and their supporting facilities. The safety analysis covers the hazards associated with normal K Basin fuel storage and handling operations, fuel encapsulation, sludge encapsulation, and canister clean-up and disposal. After a review of the Criticality Safety Evaluation of the K Basin activities, the following postulated events were evaluated: Crane failure and casks dropped into loadout pit; Design basis earthquake; Hypothetical loss of basin water accident analysis; Combustion of uranium fuel following dryout; Crane failure and cask dropped onto floor of transfer area; Spent ion exchange shipment for burial; Hydrogen deflagration in ion exchange modules and filters; Release of Chlorine; Power availability and reliability; and Ashfall.

  12. Adsorption of Chromium (VI) by metal hydroxide sludge from the metal finishing

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Adsorption of Chromium (VI) by metal hydroxide sludge from the metal finishing Loïc Perrin Ecole sludge (MHS) during the treatment of their liquid effluents charged with heavy metals. Generally, a small part of these sludge is valorized because of their important metal fickleness. Consequently

  13. IMPACT OF HEAVY METALS IN SEWAGE SLUDGE ON SOIL AND PLANTS (COLZA and WHEAT)

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    IMPACT OF HEAVY METALS IN SEWAGE SLUDGE ON SOIL AND PLANTS (COLZA and WHEAT) Najla LASSOUED1@emse.fr Abstract We are testing the impact of heavy metals in sludge from urban and industrial wastewater treatment> Cu> Ni> Co> Cd The contents of heavy metals in the sludge is made very high and exceed European

  14. Location and chemical composition of microbially induced phosphorus precipitates in anaerobic and aerobic granular sludge

    E-Print Network [OSTI]

    Boyer, Edmond

    and aerobic granular sludge A. Mañasa,b,c,e , M. Spérandioa,b,c , F. Deckerd and B. Biscanse aINSA, UPS, INP X-ray analysis (SEM-EDX) applied to granular sludge used for biological treatment of high sludge blanket (UASB) reactors and two aerobic granular sequenced batch reactors (GSBR) were evaluated

  15. The viscoelastic behaviour of raw and anaerobic digested sludge: strong similarities with soft-glassy materials

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 The viscoelastic behaviour of raw and anaerobic digested sludge: strong similarities with soft confronted with a dramatically increasing flow of sewage sludge. To improve treatment efficiency, process reliable flow properties to simulate the process, this work is an attempt to approach sludge rheological

  16. Selective hydrolysis of wastewater sludge Part 1, December 2008

    E-Print Network [OSTI]

    the production of biogas based power and heat besides reduce the power consumption from handling and treatment selective hydrolysis of sludge as if established at the existing sludge digester system . The Esbjerg digester technology .l'he plant treats combined household and industrial wastewater with a considerable

  17. Residuals, Sludge, and Composting (Maine)

    Broader source: Energy.gov [DOE]

    The Maine Department of Environmental Protection's Residuals, Sludge, and Composting program regulates the land application and post-processing of organic wastes, including sewage sludge, septage,...

  18. Operational Performance of Sedimentation Basins

    E-Print Network [OSTI]

    Bleything, Matthew D.

    2012-12-14T23:59:59.000Z

    and sludge pumps and clog pipes. (Lee, 2007) Composition of grit varies widely, with moisture content ranging from 13 to 63 percent, and volatile content ranging from 1 to 56 percent. The specific gravity of clean grit particles may be as high as 2... for unobstructed flow of the inlet water into the basin when the basin was almost full to capacity with sediment. The outlet of the sediment basin is an oil/water separator. This is for oil leaks and spills from the plant island. The design called...

  19. Metagenomic analysis of phosphorus removing sludge communities

    E-Print Network [OSTI]

    2008-01-01T23:59:59.000Z

    kinase from activated sludge performing enhanced biologicalbetween flocculation of activated sludge and composition oforganisms from activated sludge systems. Wat Res 31,

  20. activated sludge samples: Topics by E-print Network

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

    on website http:www.wrc.org.za Plant-soil interactions of sludge-borne heavy metals and the Biology and Medicine Websites Summary: of the wastewater treatment works in...

  1. Solidification of low-volume power plant sludges. Final report

    SciTech Connect (OSTI)

    Bell, N.E.; Halverson, M.A.; Mercer, B.M.

    1981-12-01T23:59:59.000Z

    A literature review was conducted to obtain information on the status of hazardous waste solidification technology and application of this technology to low-volume power plant waste sludges. Because of scarcity of sludge composition data, anticipated major components were identified primarily by chemical reactions that are known to occur during treatment of specific wastewaters. Chemical and physical properties of these sludges were critically analyzed for compatibility with several types of commercially available solidification processes. The study pointed out the need for additional information on the nature of these sludges, especially leaching characteristics and the presence of substances that will interfere with solidification processes. Laboratory studies were recommended for evaluation of solidification process which have the greatest potential for converting hazardous low-volume sludges to non-hazardous waste forms.

  2. Coalbed methane produced water management guide treatment and discharge to surface waters: Black Warrior Basin, Alabama. Final report, April 1991-May 1993

    SciTech Connect (OSTI)

    Davis, H.A.

    1993-05-01T23:59:59.000Z

    To assist coalbed methane in their efforts to manage produced waters in an environmentally acceptable manner, GRI, in cooperation with the member companies of the Coalbed Methane Association of Alabama, developed a guidance manual that presents the state-of-the-art methodology for managing Black Warrior Basin produced water through the use of treatment ponds and National Pollutant Discharge Elimination System (NPDES) permits. Six treatment pond systems were studied to develop information for the manual. Topics included in the manual are produced water characteristics, NPDES permit requirements, sample collection and testing, pond based treatment methods, treatment pond management, and process troubleshooting.

  3. Biofiltration vs. conventional activated sludge plants: what about priority and emerging1 pollutants removal?2

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    performances of two complete wastewater treatment plants (WWTP) for all priority19 substances listed solids elimination and possible coagulant impact on soluble compounds. For biological27 treatments; biofiltration; conventional activated sludge; physico-chemical lamellar settling;42 wastewater treatment plant

  4. Composting Manure and Sludge 

    E-Print Network [OSTI]

    Sweeten, John M.

    2008-07-08T23:59:59.000Z

    Composted manure and sludge can be a valuable fertilizer, but special equipment is required. Composting can be done with windrow operations, aerated windrow operations or aerated bins. Factors that affect composting rates are included....

  5. Resources recovery of oil sludge by pyrolysis: Kinetics study

    SciTech Connect (OSTI)

    Shie, J.L.; Chang, C.Y.; Lin, J.P.; Wu, C.H.; Lee, D.J.

    1999-07-01T23:59:59.000Z

    Oil sludge, if unused, is one of the major industrial wastes needed to be treated for the petroleum refinery plant or petrochemical industry. It contains a large amount of combustibles with high heating values. The treatment of waste oil sludge by burning has certain benefit; however, it cannot provide the useful resource efficiently. On the other hand, the conversion of oil sludge to lower molecule weight organic compounds by pyrolysis not only solves the disposal problem but also matches the appeal of resource utilization. The major sources of oil sludge include the oil storage tank sludge, the biological sludge, the dissolve air flotation (DAF) scum, the American Petroleum Institute (API) separator sludge and the chemical sludge. In this study, the oil sludge from the oil storage tank of a typical petroleum refinery plant located in the northern Taiwan is used as the raw material of pyrolysis. Its heating value of dry basis and low heating value of wet basis are about 10,681 k cal/kg and 5,870 k cal/kg, respectively. The removal of the moisture of oil sludge significantly increases its heating value. The pyrolysis of oil sludge is conducted by the use of nitrogen as the carrier gas in the temperature range of 380 {approximately} 1,073 K and at various constant heating rates of 5.2, 12.8 and 21.8 K/min. The pyrolytic reaction is significant in 450 {approximately} 800 K and complex. For the sake of simplicity and engineering use, a one-reaction kinetic model is proposed for the pyrolysis of oil sludge, and is found to satisfactorily fit the experimental data. The activation energy, reaction order and frequency factor of the corresponding pyrolysis reaction in nitrogen for oil sludge are 78.22 kJ/mol, 2.92 and 9.48 105 l/min, respectively. These results are very useful for the proper design of the pyrolysis system of the oil sludge under investigation.

  6. Viscous sludge sample collector

    DOE Patents [OSTI]

    Beitel, George A [Richland, WA

    1983-01-01T23:59:59.000Z

    A vertical core sample collection system for viscous sludge. A sample tube's upper end has a flange and is attached to a piston. The tube and piston are located in the upper end of a bore in a housing. The bore's lower end leads outside the housing and has an inwardly extending rim. Compressed gas, from a storage cylinder, is quickly introduced into the bore's upper end to rapidly accelerate the piston and tube down the bore. The lower end of the tube has a high sludge entering velocity to obtain a full-length sludge sample without disturbing strata detail. The tube's downward motion is stopped when its upper end flange impacts against the bore's lower end inwardly extending rim.

  7. Sludge application and monitoring program on the Oak Ridge Reservation, 1986 through 1993

    SciTech Connect (OSTI)

    Gunderson, C.A.; Boston, H.L.; Van Miegroet, H., Morris, J.L.; Larsen, I.L.; Walzer, A.E.; Adler, T.C.; Bradburn, D.M.; Huq, M.

    1995-08-01T23:59:59.000Z

    Municipal sewage sludge has been applied to forests and pastures on the DOE (U.S. Department of Energy) Oak Ridge Reservation (ORR) since 1983 as a method of both disposal and beneficial reuse. Application was carried out under State of Tennessee permits issued to the City of Oak Ridge for land disposal of. sewage sludge. In conjunction with these applications, information has been collected concerning sludge quantity and characteristics, soil parameters, soil water constituents, groundwater quality, surface runoff water quality, and various chemical constituents in vegetation on application sites. This information provides (1) a record of sludge application on the DOE ORR, and (2) documentation of changes in soil parameters following sludge application. The information also provides a basis for evaluating the implications of the land application of municipal sewage sludge for soil and water quality and for evaluating the fate of sludge constituents when sludge is either sprayed onto or injected into pasture sites or applied to the surface of forested sites. This report covers in detail sludge applications conducted from 1986 through 1993, with some data from the period between 1983 and 1986. Land application has been recommended by the U.S. Environmental Protection Agency as a desirable alternative for disposal of ORR waste. Municipal sewage sludge is in many ways similar to dilute animal manure fertilizer, but it also contains metals, organic chemicals, human pathogens, and other constituents reflective of inputs into the municipal sewage treatment plant. When applied to land, nutrients in the sludge improve soil fertility, and minerals and organic matter in the sludge improve soil structure. Under optimal conditions, metals are immobilized, and organic chemicals and pathogens are immobilized or destroyed. If the sludge is not managed effectively, however, sludge constituents have the potential to affect human health and the environment.

  8. Pretreatment of neutralized cladding removal waste sludge: Results of the second design basis experiment

    SciTech Connect (OSTI)

    Lumetta, G.J.

    1994-05-01T23:59:59.000Z

    For several years, the Pacific Northwest Laboratory (PNL) has been investigating methods to pretreat Hanford neutralized cladding removal waste (NCRW) sludge. In the past, Zircaloy-clad metallic U fuel was chemically decladded using the Zirflex process; NCRW sludge was formed when the decladding solution was neutralized for storage in carbon-steel tanks. This sludge, which is currently stored in Tanks 103-AW and 105-AW on the Hanford Site, primarily consists of insoluble Zr hydroxides and/or oxides and NaF. Significant quantities of Al, La, U, as well as other insoluble minor constituents are present in the sludge, along with sodium and potassium nitrates, nitrites, and hydroxides in the interstitial liquid. The sludge contains about 2,000 nCi of transuranic (TRU) material per gram of dry sludge, and mixed fission products. Therefore, the sludge must be handled as high-level waste (HLW). The NCRW sludge must be pretreated before treatment (e.g., vitrification) and disposal, so that the overall cost of disposal can be minimized. The NCRW pretreatment flowsheet was designed to achieve the following objectives: (a) to separate Am and Pu from the major sludge constituents (Na, Zr). (b) to separate Am and Pu from U. (c) to concentrate Am and Pu in a small volume for immobilization in borosilicate glass, based on Hanford Waste Vitrification Plant (HWVP). The flowsheet involves: (1) sludge washing, (2) sludge dissolution, (3) extraction of U with tributyl phosphate (TBP), and (4) extraction of TRUs with octyl(phenyl)-N,N-diisobutlycarbamoylmethyl-phosphine oxide (CMPO). As presented in the flowsheet, the NCRW sludge is first washed with 0.I M NaOH to remove interstitial liquid and soluble salts from the sludge including sodium and potassium fluorides, carbonates, hydroxides, nitrates, and nitrites. The washed sludge is then subjected to two dissolution steps to achieve near complete dissolution of Zr.

  9. Sociological adaptation among bacterial populations in an activated sludge ecosystem

    E-Print Network [OSTI]

    Forrest, Robert George

    1970-01-01T23:59:59.000Z

    Bacillus Corynebacterium, and Micrococcus being much less abundant. Unz and Dondero (70) isolated two-hundred and three strains from fifty-one trickling filters and activated sludge zoogloeas, with one-hundred and forty-seven of the strains forming... in the aeration basin or secondary sedimentation biomass; instead, members of the Flavobacterium C'~oh~as group, the genus Achromobacter, and a Pseudomonas-l&e group were most numerous. METHODS AND MATERIALS Batch fermentation s stem. The bench scale batch...

  10. Water Clarity Simulant for K East Basin Filtration Testing

    SciTech Connect (OSTI)

    Schmidt, Andrew J.

    2006-01-20T23:59:59.000Z

    This document provides a simulant formulation intended to mimic the behavior of the suspended solids in the K East (KE) Basin fuel storage pool. The simulant will be used to evaluate alternative filtration apparatus to improve Basin water clarity and to possibly replace the existing sandfilter. The simulant was formulated based on the simulant objectives, the key identified parameters important to filtration, the composition and character of the KE Basin suspended sludge particles, and consideration of properties of surrogate materials.

  11. WASTEWATER TREATMENT IN THE OIL SHALE INDUSTRY

    E-Print Network [OSTI]

    Fox, J.P.

    2010-01-01T23:59:59.000Z

    and sludges produced by retort water treatment should bewaters woulp not require treatment since they are producedtreatment technology. Mine waters, by contrast, are produced

  12. Modelling and Control of Activated Sludge Processes

    E-Print Network [OSTI]

    Skogestad, Sigurd

    Modelling and Control of Activated Sludge Processes Michela Mulas Dottorato di Ricerca of Activated Sludge Processes Michela Mulas Supervisors: Prof. Roberto Baratti Ing. Stefania Tronci Dottorato . . . . . . . . . . . . . . . . . . . . . . . . . 5 2 ASP Models and Simulations 7 2.1 The Activated Sludge Process

  13. Short Communication Electricity generation from fermented primary sludge using single-chamber

    E-Print Network [OSTI]

    , Nanjing 210009, China b Department of Civil and Environmental Engineering, 212 Sackett Building, Penn effluent. Ó 2012 Elsevier Ltd. All rights reserved. 1. Introduction The costs for sludge management% of total operation costs (Xiao et al., 2011). There- fore, reducing sludge treatment costs can

  14. Effect of initial physical characteristics on sludge compost performance Anne Trmier1,2,*

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    and Conseil, 2006). In this context, biological treatments such as composting are promoted to transform of wastewater sludge, the bulking agent (BA) plays a major role in establishing the recipe structure, exposed to wastewater sludge dry mass ratio of 1/ 6, the ten (10) recipes were repeated using two BA, residues recycled

  15. K-Basins design guidelines

    SciTech Connect (OSTI)

    Roe, N.R.; Mills, W.C.

    1995-06-01T23:59:59.000Z

    The purpose of the design guidelines is to enable SNF and K Basin personnel to complete fuel and sludge removal, and basin water mitigation by providing engineering guidance for equipment design for the fuel basin, facility modifications (upgrades), remote tools, and new processes. It is not intended to be a purchase order reference for vendors. The document identifies materials, methods, and components that work at K Basins; it also Provides design input and a technical review process to facilitate project interfaces with operations in K Basins. This document is intended to compliment other engineering documentation used at K Basins and throughout the Spent Nuclear Fuel Project. Significant provisions, which are incorporated, include portions of the following: General Design Criteria (DOE 1989), Standard Engineering Practices (WHC-CM-6-1), Engineering Practices Guidelines (WHC 1994b), Hanford Plant Standards (DOE-RL 1989), Safety Analysis Manual (WHC-CM-4-46), and Radiological Design Guide (WHC 1994f). Documents (requirements) essential to the engineering design projects at K Basins are referenced in the guidelines.

  16. RESULTS OF IONSIV® IE-95 STUDIES FOR THE REMOVAL OF RADIOACTIVE CESIUM FROM K-EAST BASIN SPENT NUCLEAR FUEL POOL DURING DECOMMISSIONING ACTIVITIES

    SciTech Connect (OSTI)

    DUNCAN JB; BURKE SP

    2008-07-07T23:59:59.000Z

    This report delineates the results obtained from laboratory testing of IONISIV{reg_sign} IE-95 to determine the efficacy of the zeolite for the removal of radioactive cesium from the KE Basin water prior to transport to the Effluent Treatment Facility, as described in RPP-PLAN-36158, IONSIV{reg_sign} IE-95 Studies for the removal of Radioactive Cesium from KE Basin Spent Nuclear Fuel Pool during Decommissioning Activities. The spent nuclear fuel was removed from KE Basin and the remaining sludge was layered with a grout mixture consisting of 26% Lehigh Type I/II portland cement and 74% Boral Mohave type F fly ash with a water-to-cement ratio of 0.43. The first grout pour was added to the basin floor to a depth of approximately 14 in. covering an area of 12,000 square feet. A grout layer was also added to the sludge containers located in the attached Weasel and Technical View pits.

  17. Long-term investigation of microbial fuel cells treating primary sludge or digested sludge

    E-Print Network [OSTI]

    : Microbial fuel cell Primary sludge Digested sludge Energy Biogas a b s t r a c t The long-term performance. Digested sludge can be further composted for agriculture uses, and biogas can be con- vertedLong-term investigation of microbial fuel cells treating primary sludge or digested sludge Zheng Ge

  18. INTEC SBW Solid Sludge Surrogate Recipe and Validation

    SciTech Connect (OSTI)

    Maio, Vince; Janikowski, Stuart; Johnson, Jim; Maio, Vince; Pao, Jenn-Hai

    2004-06-01T23:59:59.000Z

    A nonhazardous INTEC tank farm sludge surrogate that incorporated metathesis reactions to generate solids from solutions of known elements present in the radioactive INTEC tank farm sodium-bearing waste sludges was formulated. Elemental analyses, physical property analyses, and filtration testing were performed on waste surrogate and tank farm waste samples, and the results were compared. For testing physical systems associated with moving the tank farm solids, the surrogate described in this report is the best currently available choice. No other available surrogate exhibits the noted similarities in behavior to the sludges. The chemical morphology, particle size distribution, and settling and flow characteristics of the surrogate were similar to those exhibited by the waste sludges. Nonetheless, there is a difference in chemical makeup of the surrogate and the tank farm waste. If a chemical treatment process were to be evaluated for final treatment and disposition of the waste sludges, the surrogate synthesis process would likely require modification to yield a surrogate with a closer matching chemical composition.

  19. Grout and glass performance in support of stabilization/solidification of ORNL tank sludges

    SciTech Connect (OSTI)

    Spence, R.D.; Mattus, C.H.; Mattus, A.J.

    1998-09-01T23:59:59.000Z

    Wastewater at Oak Ridge National Laboratory (ORNL) is collected, evaporated, and stored in the Melton Valley Storage Tanks (MVST) and Bethel Valley Evaporator Storage Tanks (BVEST) pending treatment for disposal. In addition, some sludges and supernatants also requiring treatment remain in two inactive tank systems: the gunite and associated tanks (GAAT) and the old hydrofracture (OHF) tank. The waste consists of two phases: sludge and supernatant. The sludges contain a high amount of radioactivity, and some are classified as TRU sludges. Some Resource Conservation and Recovery Act (RCRA) metal concentrations are high enough to be defined as RCRA hazardous; therefore, these sludges are presumed to be mixed TRU waste. Grouting and vitrification are currently two likely stabilization/solidification alternatives for mixed wastes. Grouting has been used to stabilize/solidify hazardous and low-level radioactive waste for decades. Vitrification has been developed as a high-level radioactive alternative for decades and has been under development recently as an alternative disposal technology for mixed waste. The objective of this project is to define an envelope, or operating window, for grout and glass formulations for ORNL tank sludges. Formulations will be defined for the average composition of each of the major tank farms (BVEST/MVST, GAAT, and OHF) and for an overall average composition of all tank farms. This objective is to be accomplished using surrogates of the tank sludges with hot testing of actual tank sludges to check the efficacy of the surrogates.

  20. ORIGINAL PAPER Bioremediation of oily sludge-contaminated soil

    E-Print Network [OSTI]

    Ma, Lena

    ORIGINAL PAPER Bioremediation of oily sludge-contaminated soil by stimulating indigenous microbes contaminants. On the other hand, biological treatment (bioremediation) appears to be among the most promising in the complete destruction of hazardous compounds into innocuous products (Bal- ba et al. 1998). For this reason

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

    SciTech Connect (OSTI)

    Gilliam, T.M.; Spence, R.D.

    1998-11-01T23:59:59.000Z

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

  2. Oxygen-enriched multiple-hearth sewage sludge incineration demonstration. Final report

    SciTech Connect (OSTI)

    NONE

    1998-07-01T23:59:59.000Z

    Oxygen-enhanced multiple-hearth sludge incineration was the focus of a five-month joint study by Praxair and the New York State Energy Research and Development Authority. Testing and demonstration were conducted in Rochester NY, at Monroe County`s Frank E. Van Lare Sewage Treatment Plant. A simple retrofit of high-momentum oxygen lances created a convection hearth in which convective heat and mass transfer with the drying sludge were greatly enhanced, while hearth temperatures were moderated by the wet sludge to prevent overheating. Based on the results of short- and long-term controlled tests discussed in this report, oxygen enhancement of multiple-hearth sludge incinerators can be economically viable, with a savings between $30 and $60 per hour at Van Lare based upon increased sludge throughput and reduced fuel consumption.

  3. A GEOCHEMICAL MODULE FOR "AMDTreat" TO COMPUTE CAUSTIC QUANTITY, EFFLUENT QUALITY, AND SLUDGE VOLUME1

    E-Print Network [OSTI]

    of sludge produced by the treatment, a titration simulation is being developed using the geochemical program The AMDTreat computer program ( . Treatment with caustic chemicals typically is used to increase pH (6 to 8), whereas active manganese removal requires treatment to alkaline pH (~10). The treatment

  4. Pretreatment of high solid microbial sludges

    DOE Patents [OSTI]

    Rivard, Christopher J. (Lakewood, CO); Nagle, Nicholas J. (Broomfield, CO)

    1998-01-01T23:59:59.000Z

    A process and apparatus for pretreating microbial sludges in order to enhance secondary anaerobic digestion. The pretreatment process involves disrupting the cellular integrity of municipal sewage sludge through a combination of thermal, explosive decompression and shear forces. The sludge is pressurized and pumped to a pretreatment reactor where it is mixed with steam to heat and soften the sludge. The pressure of the sludge is suddenly reduced and explosive decompression forces are imparted which partially disrupt the cellular integrity of the sludge. Shear forces are then applied to the sludge to further disrupt the cellular integrity of the sludge. Disrupting cellular integrity releases both soluble and insoluble organic constituents and thereby renders municipal sewage sludge more amenable to secondary anaerobic digestion.

  5. Pretreatment of high solid microbial sludges

    DOE Patents [OSTI]

    Rivard, C.J.; Nagle, N.J.

    1998-07-28T23:59:59.000Z

    A process and apparatus are disclosed for pretreating microbial sludges in order to enhance secondary anaerobic digestion. The pretreatment process involves disrupting the cellular integrity of municipal sewage sludge through a combination of thermal, explosive decompression and shear forces. The sludge is pressurized and pumped to a pretreatment reactor where it is mixed with steam to heat and soften the sludge. The pressure of the sludge is suddenly reduced and explosive decompression forces are imparted which partially disrupt the cellular integrity of the sludge. Shear forces are then applied to the sludge to further disrupt the cellular integrity of the sludge. Disrupting cellular integrity releases both soluble and insoluble organic constituents and thereby renders municipal sewage sludge more amenable to secondary anaerobic digestion. 1 fig.

  6. Comparative assessment of municipal sewage sludge incineration, gasification and pyrolysis for a sustainable sludge-to-energy management in Greece

    SciTech Connect (OSTI)

    Samolada, M.C. [Dept. Secretariat of Environmental and Urban Planning – Decentralized Area Macedonian Thrace, Taki Oikonomidi 1, 54008 Thessaloniki (Greece); Zabaniotou, A.A., E-mail: azampani@auth.gr [Aristotle University of Thessaloniki, Dept. of Chemical Engineering, University Box 455, University Campus, 541 24 Thessaloniki (Greece)

    2014-02-15T23:59:59.000Z

    Highlights: • The high output of MSS highlights the need for alternative routes of valorization. • Evaluation of 3 sludge-to-energy valorisation methods through SWOT analysis. • Pyrolysis is an energy and material recovery process resulting to ‘zero waste’. • Identification of challenges and barriers for MSS pyrolysis in Greece was investigated. • Adopters of pyrolysis systems face the challenge of finding new product markets. - Abstract: For a sustainable municipal sewage sludge management, not only the available technology, but also other parameters, such as policy regulations and socio-economic issues should be taken in account. In this study, the current status of both European and Greek Legislation on waste management, with a special insight in municipal sewage sludge, is presented. A SWOT analysis was further developed for comparison of pyrolysis with incineration and gasification and results are presented. Pyrolysis seems to be the optimal thermochemical treatment option compared to incineration and gasification. Sewage sludge pyrolysis is favorable for energy savings, material recovery and high added materials production, providing a ‘zero waste’ solution. Finally, identification of challenges and barriers for sewage sludge pyrolysis deployment in Greece was investigated.

  7. Structural and mechanical response to a thermo-rheologic history of spinel sludge in high-level waste glass

    SciTech Connect (OSTI)

    Jiricka, Milos (ASSOC WESTERN UNIVERSITY); Hrma, Pavel R. (BATTELLE (PACIFIC NW LAB))

    2002-01-01T23:59:59.000Z

    The composition and structure of a sludge sample from a high-level waste glass melter were studied using optical and scanning electron microscopy, and x-ray diffraction. At isothermal heat treatments between 1050 C and 1350 C, spinel crystals partly dissolved to form on cooling tiny ({approx}10 um) star-like crystals or dendrites. The shear stress in sludge was measured at a constant shear rate (from 0.005 s{sup -1} to 1.0 s{sup -1}) and temperature (from 1050 C to 1350?C) during repeated deformation and after idling. The initial thixotropic character of the loose structure of the settled sludge turned on subsequent deformation (and idling) to rheopectic behavior. As the spinel concentration in the sludge decreased from 28 mass% (sludge as received) to 15 mass% at 1300 C, the sludge turned into a Newtonian suspension.

  8. Radioactive air emissions notice of construction fuel removal for 105-KW Basin

    SciTech Connect (OSTI)

    Hays, C.B.

    1997-05-29T23:59:59.000Z

    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) 61.96, for the modifications, installation of new equipment, and fuel removal and sludge relocation activities at 105-KW Basin. The purpose of the activities described in this NOC is to enable the eventual retrieval and transport of the fuel for processing. The fuel retrieval and transport will require an integrated water treatment system for which performance specifications have been developed. These specifications are currently in the procurement process. Following procurement (and before installation of this system and the handling of fuel) design details will be provided to Washington State Department of Health (WDOH). The 105-K West Reactor (105-KW) and its associated spent nuclear fuel (SNF) storage basin were constructed in the early 1950s and are located on the Hanford Site in the 100-K Area about 1,400 feet from the Columbia River. The 105-KW Basin contains 964 Metric Tons of SNF stored under water in approximately 3,800 closed canisters. This SNF has been stored for varying periods of time ranging from 8 to 17 years. The 105-KW Basin is constructed of concrete with an epoxy coating and contains approximately 1.3 million gallons of water with an asphaltic membrane beneath the pool. Although the 105-KW Basin has not been known to leak, the discharge chute and associated construction joint have been isolated from the rest of the basin by metal isolation barriers. This was a precautionary measure, to mitigate the consequences of a seismic event. The proposed modifications described are scheduled to begin in calendar year 1997.

  9. Radiowave-based process recovers oil from sludge at Texas site

    SciTech Connect (OSTI)

    NONE

    1996-12-02T23:59:59.000Z

    A radio frequency (RF)-based sludge treatment process is proving successful in demonstration tests at a Texas site. The process separates petroleum-based sludges into salable oil, treatment-quality water, and disposable solids. The system, called MST-4000, is effective on most sludges, including: dissolved-air-flotation float, slop oil emulsion solids, heat exchanger cleaning sludge, API separator sludge, and leaded tank bottoms. Major components of the system include: four high-power RF/microwave transmitters; four high-power RF/microwave illuminators, which focus the energy on the sludge in a small, cylindrical reactor; four computer-controlled, automatic RF tuners, which improve the quality of the RF/sludge interface by monitoring and adjusting vector impedance; a wave guide, which channels and controls the RF signals from the transmitters through the tuners and to the illuminators; a specially designed instrumentation and control system; and plumbing and piping systems. The paper describes the process and current tests being performed.

  10. A STUDY OF ACTIVATED SLUDGE DEWATERING IN EXPERIMENTAL REED-PLANTED OR UNPLANTED SLUDGE

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    94/0169 A STUDY OF ACTIVATED SLUDGE DEWATERING IN EXPERIMENTAL REED-PLANTED OR UNPLANTED SLUDGE of the reeds in bed 2 died in spite of the influent sludge dose of 70 g. of SS.m"2.d~l. During the second phase (917 days) the 3 beds were aerated from the bottom and fed with sludge, directly extracted from

  11. Mixing Envelope D Sludge with LAW Intermediate Products with and without Glass Formers

    SciTech Connect (OSTI)

    Hansen, E.K.

    2001-09-21T23:59:59.000Z

    The Department of Energy (DOE) Office of River Protection is in the process of designing a waste treatment system to process the Hanford Reservation High Level Waste (HLW). Envelope D sludge slurries will be blended with the concentrated Cs/Ts eluates, and the Sr/TRU intermediates separated from Envelope A, B, and C feeds. This study produced two washed simulated sludges (representing tanks 241-AZ-101 and 241-AZ-102 sludge), a Sr/TRU washed precipitate produced from tank 241-AN-107 simulant, and a concentrated blended eluate simulant based upon eluates from processing 241-AZ-102 supernate.

  12. Construction materials as a waste management solution for cellulose sludge

    SciTech Connect (OSTI)

    Modolo, R., E-mail: regina.modolo@ua.pt [University of Aveiro, Civil Engineering Department/CICECO, 3810-193 Aveiro (Portugal); Ferreira, V.M. [University of Aveiro, Civil Engineering Department/CICECO, 3810-193 Aveiro (Portugal); Machado, L.M. [RAIZ - Forest and Paper Research Institute, Portucel-Soporcel, Eixo (Portugal); Rodrigues, M.; Coelho, I. [CIMIANTO - Sociedade Tecnica Hidraulica, S.A., Alhandra (Portugal)

    2011-02-15T23:59:59.000Z

    Sustainable waste management system for effluents treatment sludge has been a pressing issue for pulp and paper sector. Recycling is always recommended in terms of environmental sustainability. Following an approach of waste valorisation, this work aims to demonstrate the technical viability of producing fiber-cement roof sheets incorporating cellulose primary sludge generated on paper and pulp mills. From the results obtained with preliminary studies it was possible to verify the possibility of producing fiber-cement sheets by replacing 25% of the conventional used virgin long fiber by primary effluent treatment cellulose sludge. This amount of incorporation was tested on an industrial scale. Environmental parameters related to water and waste, as well as tests for checking the quality of the final product was performed. These control parameters involved total solids in suspension, dissolved salts, chlorides, sulphates, COD, metals content. In the product, parameters like moisture, density and strength were controlled. The results showed that it is possible to replace the virgin long fibers pulp by primary sludge without impacts in final product characteristics and on the environment. This work ensures the elimination of significant waste amounts, which are nowadays sent to landfill, as well as reduces costs associated with the standard raw materials use in the fiber-cement industrial sector.

  13. Laser removal of sludge from steam generators

    DOE Patents [OSTI]

    Nachbar, Henry D. (Ballston Lake, NY)

    1990-01-01T23:59:59.000Z

    A method of removing unwanted chemical deposits known as sludge from the metal surfaces of steam generators with laser energy is provided. Laser energy of a certain power density, of a critical wavelength and frequency, is intermittently focused on the sludge deposits to vaporize them so that the surfaces are cleaned without affecting the metal surface (sludge substrate). Fiberoptic tubes are utilized for laser beam transmission and beam direction. Fiberoptics are also utilized to monitor laser operation and sludge removal.

  14. Adaptive k-tracking control of activated sludge processes PETIA GEORGIEVA{ and ACHIM ILCHMANN{*

    E-Print Network [OSTI]

    Knobloch,Jürgen

    of coarse solid material, primary treatment for separation of decantable material and biological treatment (activated sludge pro- cess and recirculation). The treatment of solid material includes anaerobic digestion in the presence of oxygen. The tank is equipped with a surface aeration turbine which supplies oxygen

  15. Independent Oversight Activity Report, Hanford Sludge Treatment...

    Office of Environmental Management (EM)

    Project Engineered Container Retrieval and Transfer System Preliminary Documented Safety Analysis, Revision 00 - April 2015 Independent Activity Report, Richland Operations...

  16. Design considerations for sludge fired fluidized bed incinerator-cum-boiler

    SciTech Connect (OSTI)

    Bapat, D.W.; Vishwanathan, K. [Thermax Ltd., Pune (India). Research and Development Centre

    1997-12-31T23:59:59.000Z

    Thermal Limited, a major player in the field of Fluidized Bed Boilers in India, has supplied on a turnkey basis, three boilers each of 22.5 tons per hour capacity as a part of Cogeneration system for PT. South Pacific Viscose, Indonesia. The plant generates huge volumes of sludge from its effluent Treatment Plant (ETP). The sludge produced from the ETP has a moisture content of about 98%, which is subsequently reduced to about 78% using a decanter before feeding the sludge into the boiler. The waste sludge has a negative heating value ({minus}150 kcal/kg on NCV basis) and required coal as support fuel for burning. The plant`s requirement was to incinerate the entire sludge generated in the plant, which meant that nearly 50% of the fuel fed to the boiler consisted of the waste sludge. Additional requirements were to burn coal and oil as back-up fuels. This paper deals with the challenges encountered and various design features provided in the configuration of the incinerator-cum-boiler including conveying, feeding and spreading arrangement of the waste sludge for effective incineration in addition to burning coal and oil. Also included in the paper is a brief description of the automatic control logics for combustion control and bed temperature control.

  17. Multi-step process for concentrating magnetic particles in waste sludges

    DOE Patents [OSTI]

    Watson, John L. (Rolla, MO)

    1990-01-01T23:59:59.000Z

    This invention involves a multi-step, multi-force process for dewatering sludges which have high concentrations of magnetic particles, such as waste sludges generated during steelmaking. This series of processing steps involves (1) mixing a chemical flocculating agent with the sludge; (2) allowing the particles to aggregate under non-turbulent conditions; (3) subjecting the mixture to a magnetic field which will pull the magnetic aggregates in a selected direction, causing them to form a compacted sludge; (4) preferably, decanting the clarified liquid from the compacted sludge; and (5) using filtration to convert the compacted sludge into a cake having a very high solids content. Steps 2 and 3 should be performed simultaneously. This reduces the treatment time and increases the extent of flocculation and the effectiveness of the process. As partially formed aggregates with active flocculating groups are pulled through the mixture by the magnetic field, they will contact other particles and form larger aggregates. This process can increase the solids concentration of steelmaking sludges in an efficient and economic manner, thereby accomplishing either of two goals: (a) it can convert hazardous wastes into economic resources for recycling as furnace feed material, or (b) it can dramatically reduce the volume of waste material which must be disposed.

  18. Multi-step process for concentrating magnetic particles in waste sludges

    DOE Patents [OSTI]

    Watson, J.L.

    1990-07-10T23:59:59.000Z

    This invention involves a multi-step, multi-force process for dewatering sludges which have high concentrations of magnetic particles, such as waste sludges generated during steelmaking. This series of processing steps involves (1) mixing a chemical flocculating agent with the sludge; (2) allowing the particles to aggregate under non-turbulent conditions; (3) subjecting the mixture to a magnetic field which will pull the magnetic aggregates in a selected direction, causing them to form a compacted sludge; (4) preferably, decanting the clarified liquid from the compacted sludge; and (5) using filtration to convert the compacted sludge into a cake having a very high solids content. Steps 2 and 3 should be performed simultaneously. This reduces the treatment time and increases the extent of flocculation and the effectiveness of the process. As partially formed aggregates with active flocculating groups are pulled through the mixture by the magnetic field, they will contact other particles and form larger aggregates. This process can increase the solids concentration of steelmaking sludges in an efficient and economic manner, thereby accomplishing either of two goals: (a) it can convert hazardous wastes into economic resources for recycling as furnace feed material, or (b) it can dramatically reduce the volume of waste material which must be disposed. 7 figs.

  19. Rheology of spinel sludge in molten glass

    SciTech Connect (OSTI)

    Mika, M (.); Hrma, Pavel R. (BATTELLE (PACIFIC NW LAB)); Schweiger, M J. (.)

    1999-11-01T23:59:59.000Z

    Spinel sludge, which forms while vitrifying high-level waste, obstructs the flow of molten glass and damages the melter. The effectiveness of removing spinel sludge from a high-level waste glass melter depends on its rheological behavior. We prepared spinel sludge in a laboratory crucible by allowing spinel to settle from molten glass and measured the response of the sludge to shear using a rotating spindle viscometer. The shear stress increased nonlinearly with the velocity gradient (the shear rate) and with time at a constant velocity gradient, as is typical for a pseudoplastic rheopectic liquid. The apparent viscosity of the sludge substantially increased when RuO-2 needles were present.

  20. Characterization, Leaching, and Filtrations Testing of Ferrocyanide Tank sludge (Group 8) Actual Waste Composite

    SciTech Connect (OSTI)

    Fiskum, Sandra K.; Billing, Justin M.; Crum, J. V.; Daniel, Richard C.; Edwards, Matthew K.; Shimskey, Rick W.; Peterson, Reid A.; MacFarlan, Paul J.; Buck, Edgar C.; Draper, Kathryn E.; Kozelisky, Anne E.

    2009-02-28T23:59:59.000Z

    This is the final report in a series of eight reports defining characterization, leach, and filtration testing of a wide variety of Hanford tank waste sludges. The information generated from this series is intended to supplement the Waste Treatment and Immobilization Plant (WTP) project understanding of actual waste behaviors associated with tank waste sludge processing through the pretreatment portion of the WTP. The work described in this report presents information on a high-iron waste form, specifically the ferrocyanide tank waste sludge. Iron hydroxide has been shown to pose technical challenges during filtration processing; the ferrocyanide tank waste sludge represented a good source of the high-iron matrix to test the filtration processing.

  1. CRAD, Emergency Management - Office of River Protection K Basin Sludge

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China U.S. Department ofJune 2,The BigSidingState6Report,COMMENTS ONPRGMof EnergyWaste

  2. Dose reduction improvements in storage basins of spent nuclear fuel

    SciTech Connect (OSTI)

    Huang, Fan-Hsiung F.

    1997-08-13T23:59:59.000Z

    Spent nuclear fuel in storage basins at the Hanford Site has corroded and contaminated basin water, which has leaked into the soil; the fuel also had deposited a layer of radioactive sludge on basin floors. The SNF is to be removed from the basins to protect the nearby Columbia River. Because the radiation level is high, measures have been taken to reduce the background dose rate to as low as reasonably achievable (ALARA) to prevent radiation doses from becoming the limiting factor for removal of the SW in the basins to long-term dry storage. All activities of the SNF Project require application of ALARA principles for the workers. On the basis of these principles dose reduction improvements have been made by first identifying radiological sources. Principal radiological sources in the basin are basin walls, basin water, recirculation piping and equipment. Dose reduction activities focus on cleaning and coating basin walls to permit raising the water level, hydrolasing piping, and placing lead plates. In addition, the transfer bay floor will be refinished to make decontamination easier and reduce worker exposures in the radiation field. The background dose rates in the basin will be estimated before each task commences and after it is completed; these dose reduction data will provide the basis for cost benefit analysis.

  3. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE

    SciTech Connect (OSTI)

    Adams, J. W.; Bowerman, B. S.; Kalb, P. D.

    2002-02-25T23:59:59.000Z

    The Environmental Protection Agency (EPA) is currently evaluating alternative treatment standards for radioactively contaminated high mercury (Hg) subcategory wastes, which do not require the removal of mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needed additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 46 wt% (30 wt% dry) sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide the EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes.

  4. Sewage sludge dewatering using flowing liquid metals

    DOE Patents [OSTI]

    Carlson, Larry W. (Oswego, IL)

    1986-01-01T23:59:59.000Z

    A method and apparatus for reducing the moisture content of a moist sewage sludge having a moisture content of about 50% to 80% and formed of small cellular micro-organism bodies having internally confined water is provided. A hot liquid metal is circulated in a circulation loop and the moist sewage sludge is injected in the circulation loop under conditions of temperature and pressure such that the confined water vaporizes and ruptures the cellular bodies. The vapor produced, the dried sludge, and the liquid metal are then separated. Preferably, the moist sewage sludge is injected into the hot liquid metal adjacent the upstream side of a venturi which serves to thoroughly mix the hot liquid metal and the moist sewage sludge. The venturi and the drying zone after the venturi are preferably vertically oriented. The dried sewage sludge recovered is available as a fuel and is preferably used for heating the hot liquid metal.

  5. Qualification testing and full-scale demonstration of titanium-treated zeolite for sludge wash processing

    SciTech Connect (OSTI)

    Dalton, W.J.

    1997-06-30T23:59:59.000Z

    Titanium-treated zeolite is a new ion-exchange material that is a variation of UOP (formerly Union Carbide) IONSIV IE-96 zeolite (IE-96) that has been treated with an aqueous titanium solution in a proprietary process. IE-96 zeolite, without the titanium treatment, has been used since 1988 in the West Valley Demonstration Project`s (WVDP) Supernatant Treatment System (STS) ion-exchange columns to remove Cs-137 from the liquid supernatant solution. The titanium-treated zeolite (TIE-96) was developed by Battelle-Pacific Northwest Laboratory (PNL). Following successful lab-scale testing of the PNL-prepared TIE-96, UOP was selected as a commercial supplier of the TIE-96 zeolite. Extensive laboratory tests conducted by both the WVDP and PNL indicate that the TIE-96 will successfully remove comparable quantities of Cs-137 from Tank 8D-2 high-level radioactive liquid as was done previously with IE-96. In addition to removing Cs-137, TIE-96 also removes trace quantities of Pu, as well as Sr-90, from the liquid being processed over a wide range of operating conditions: temperature, pH, and dilution. The exact mechanism responsible for the Pu removal is not fully understood. However, the Pu that is removed by the TIE-96 remains on the ion-exchange column under anticipated sludge wash processing conditions. From May 1988 to November 1990, the WVDP processed 560,000 gallons of liquid high-level radioactive supernatant waste stored in Tank 8D-2. Supernatant is an aqueous salt solution comprised primarily of soluble sodium salts. The second stage of the high-level waste treatment process began November 1991 with the initiation of sludge washing. Sludge washing involves the mixing of Tank 8D-2 contents, both sludge and liquid, to dissolve the sulfate salts present in the sludge. Two sludge washes were required to remove sulfates from the sludge.

  6. Conceptual Thermal Treatment Technologies Feasibility Study

    SciTech Connect (OSTI)

    Suer, A.

    1996-02-28T23:59:59.000Z

    This report presents a conceptual Thermal Treatment Technologies Feasibility Study (FS) for the Savannah River Site (SRS) focusing exclusively on thermal treatment technologies for contaminated soil, sediment, or sludge remediation projects.

  7. activated sludge oxygen: Topics by E-print Network

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

    1 Effects of oxygen transport limitation on nitrification in the activated sludge process Environmental Management and Restoration Websites Summary: sludge age (MCRT), pH,...

  8. Washing and caustic leaching of Hanford tank sludge: Results of FY 1997 studies

    SciTech Connect (OSTI)

    Lumetta, G.J.; Burgeson, I.E.; Wagner, M.J.; Liu, J.; Chen, Y.L.

    1997-08-01T23:59:59.000Z

    The current plan for remediating the Hanford tank farms consists of waste retrieval, pretreatment, treatment (immobilization), and disposal. The tank wastes will be partitioned into high-level and low-level fractions. The HLW will be immobilized in a borosilicate glass matrix; the resulting glass canisters will then be disposed of in a geologic repository. Because of the expected high cost of HLW vitrification and geologic disposal, pretreatment processes will be implemented to reduce the volume of immobilized high-level waste (IHLW). Caustic leaching (sometimes referred to as enhanced sludge washing or ESW) represents the baseline method for pretreating Hanford tank sludges. Caustic leaching is expected to remove a large fraction of the Al, which is present in large quantities in Hanford tank sludges. A significant portion of the P is also expected to be removed from the sludge by metathesis of water-insoluble metal phosphates to insoluble hydroxides and soluble Na{sub 3}PO{sub 4}. Similar metathesis reactions can occur for insoluble sulfate salts, allowing the removal of sulfate from the HLW stream. This report describes the sludge washing and caustic leaching tests performed at the Pacific Northwest National Laboratory in FY 1996. The sludges used in this study were taken from Hanford tanks AN-104, BY-108, S-101, and S-111.

  9. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE.

    SciTech Connect (OSTI)

    ADAMA, J.W.; BOWERMAN, B.S.; KALB, P.D.

    2002-10-01T23:59:59.000Z

    The Environmental Protection Agency (EPA) is currently seeking to validate technologies that can directly treat radioactively contaminated high mercury (Hg) subcategory wastes without removing the mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needs additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 30 wt% dry sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes.

  10. EFFICACY OF FILTRATION PROCESSES TO OBTAIN WATER CLARITY AT K EAST SPENT NUCLEAR FUEL (SNF) BASIN

    SciTech Connect (OSTI)

    DUNCAN JB

    2006-09-28T23:59:59.000Z

    The objective is to provide water clarity to the K East Basin via filtration processes. Several activities are planned that will challenge not only the capacity of the existing ion exchange modules to perform as needed but also the current filtration system to maintain water clarity. Among the planned activities are containerization of sludge, removal of debris, and hydrolasing the basin walls to remove contamination.

  11. Fuel Pond Sludge - Lessons Learned from Initial De-sludging of Sellafield's Pile Fuel Storage Pond - 12066

    SciTech Connect (OSTI)

    Carlisle, Derek; Adamson, Kate [Sellafield Ltd, Sellafield, Cumbria (United Kingdom)

    2012-07-01T23:59:59.000Z

    The Pile Fuel Storage Pond (PFSP) at Sellafield was built and commissioned between the late 1940's and early 1950's as a storage and cooling facility for irradiated fuel and isotopes from the two Windscale Pile reactors. The pond was linked via submerged water ducts to each reactor, where fuel and isotopes were discharged into skips for transfer along the duct to the pond. In the pond the fuel was cooled then de-canned underwater prior to export for reprocessing. The plant operated successfully until it was taken out of operation in 1962 when the First Magnox Fuel Storage Pond took over fuel storage and de-canning operations on the site. The pond was then used for storage of miscellaneous Intermediate Level Waste (ILW) and fuel from the UK's Nuclear Programme for which no defined disposal route was available. By the mid 1970's the import of waste ceased and the plant, with its inventory, was placed into a passive care and maintenance regime. By the mid 1990s, driven by the age of the facility and concern over the potential challenge to dispose of the various wastes and fuels being stored, the plant operator initiated a programme of work to remediate the facility. This programme is split into a number of key phases targeted at sustained reduction in the hazard associated with the pond, these include: - Pond Preparation: Before any remediation work could start the condition of the pond had to be transformed from a passive store to a plant capable of complex retrieval operations. This work included plant and equipment upgrades, removal of redundant structures and the provision of a effluent treatment plant for removing particulate and dissolved activity from the pond water. - Canned Fuel Retrieval: Removal of canned fuel, including oxide and carbide fuels, is the highest priority within the programme. Handling and export equipment required to remove the canned fuel from the pond has been provided and treatment routes developed utilising existing site facilities to allow the fuel to be reprocessed or conditioned for long term storage. - Sludge Retrieval: In excess of 300 m{sup 3} of sludge has accumulated in the pond over many years and is made up of debris arising from fuel and metallic corrosion, wind blown debris and bio-organic materials. The Sludge Retrieval Project has provided the equipment necessary to retrieve the sludge, including skip washer and tipper machines for clearing sludge from the pond skips, equipment for clearing sludge from the pond floor and bays, along with an 'in pond' corral for interim storage of retrieved sludge. Two further projects are providing new plant processing routes, which will initially store and eventually passivate the sludge. - Metal Fuel Retrieval: Metal Fuel from early Windscale Pile operations and various other sources is stored within the pond; the fuel varies considerably in both form and condition. A retrieval project is planned which will provide fuel handling, conditioning, sentencing and export equipment required to remove the metal fuel from the pond for export to on site facilities for interim storage and disposal. - Solid Waste Retrieval: A final retrieval project will provide methods for handling, retrieval, packaging and export of the remaining solid Intermediate Level Waste within the pond. This includes residual metal fuel pieces, fuel cladding (Magnox, aluminium and zircaloy), isotope cartridges, reactor furniture, and miscellaneous activated and contaminated items. Each of the waste streams requires conditioning to allow it to be and disposed of via one of the site treatment plants. - Pond Dewatering and Dismantling: Delivery of the above projects will allow operations to progressively remove the radiological inventory, thereby reducing the hazard/risk posed by the plant. This will then allow subsequent dewatering of the pond and dismantling of the structure. (authors)

  12. RESEARCH ARTICLE Algae production on pig sludge

    E-Print Network [OSTI]

    Boyer, Edmond

    RESEARCH ARTICLE Algae production on pig sludge Attila Bai & László Stündl & Péter Bársony & Milán- ied an economical method of algae production on pig sludge that can be operated on animal farms in Hungary with modest levels of investment. We analyzed four algae spe- cies, Chlorella vulgaris

  13. Sewage sludge dewatering using flowing liquid metals

    DOE Patents [OSTI]

    Carlson, L.W.

    1985-08-30T23:59:59.000Z

    This invention relates generally to the dewatering of sludge, and more particularly to the dewatering of a sewage sludge having a moisture content of about 50 to 80% in the form of small cellular micro-organism bodies having internally confined water.

  14. Disposable sludge dewatering container and method

    DOE Patents [OSTI]

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

    1993-01-01T23:59:59.000Z

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

  15. IMPROVEMENTS IN MODELLING DISSOLVED OXYGEN IN ACTIVATED SLUDGE SYSTEMS

    E-Print Network [OSTI]

    Wells, Scott A.

    1 IMPROVEMENTS IN MODELLING DISSOLVED OXYGEN IN ACTIVATED SLUDGE SYSTEMS Jacek Makinia*, Scott A in a full-scale activated sludge reactor. The Activated Sludge Model No. 1 was used to describe for dissolved oxygen. KEYWORDS Activated sludge; dispersion; dissolved oxygen dynamics; mass transfer

  16. Sludge Batch 2 (Macrobatch 3) Rheology Studies with Simulants

    SciTech Connect (OSTI)

    Koopman, D.C.

    2001-05-02T23:59:59.000Z

    Non-radioactive sludge-only process simulations of the DWPF Sludge Receipt and Adjustment Tank (SRAT) and the Slurry Mix Evaporator (SME) cycles were conducted for a 50:50 blend of Tank 8 and Tank 40 washed sludge and Tank 40 washed sludge by itself. Rheological characterization of the sludge, SRAT product, and SME product material was requested as part of the simulant program.

  17. Modeling of the reburning process using sewage sludge-derived syngas

    SciTech Connect (OSTI)

    Werle, Sebastian, E-mail: sebastian.werle@polsl.pl [Institute of Thermal Technology, Silesian University of Technology at Gliwice, 44-100 Gliwice, Konarskiego 22 (Poland)

    2012-04-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer Gasification provides an attractive method for sewage sludges treatment. Black-Right-Pointing-Pointer Gasification generates a fuel gas (syngas) which can be used as a reburning fuel. Black-Right-Pointing-Pointer Reburning potential of sewage sludge gasification gases was defined. Black-Right-Pointing-Pointer Numerical simulation of co-combustion of syngases in coal fired boiler has been done. Black-Right-Pointing-Pointer Calculation shows that analysed syngases can provide higher than 80% reduction of NO{sub x}. - Abstract: Gasification of sewage sludge can provide clean and effective reburning fuel for combustion applications. The motivation of this work was to define the reburning potential of the sewage sludge gasification gas (syngas). A numerical simulation of the co-combustion process of syngas in a hard coal-fired boiler was done. All calculations were performed using the Chemkin programme and a plug-flow reactor model was used. The calculations were modelled using the GRI-Mech 2.11 mechanism. The highest conversions for nitric oxide (NO) were obtained at temperatures of approximately 1000-1200 K. The combustion of hard coal with sewage sludge-derived syngas reduces NO emissions. The highest reduction efficiency (>90%) was achieved when the molar flow ratio of the syngas was 15%. Calculations show that the analysed syngas can provide better results than advanced reburning (connected with ammonia injection), which is more complicated process.

  18. An evaluation of the mixing and oxygen transfer occurring in a deep aeration basin

    E-Print Network [OSTI]

    Andrews, Donald Craig

    1981-01-01T23:59:59.000Z

    -ci~cuiting. JJ 0 0 cl aa 0 al la all M Li 0 0 0 M Y :tl 0 C g IJ Ul 0i 0 aa M aa Ql C Vl Cl 0 0 0 0 0 0 C2 M 18 However, the design of the basin must be considered. In settling basins and some aer ati. on basins, this is the case... aeration of tap water, (b) steady state aeration of tap water, (c) steady state oxidation of sulf ite solution, and (d) steady state aer ation of activated sludge. Today most aerator testing either occurs with non-steady state ae. ation of tap water...

  19. Application for Approval of Modification for the 105-KE Basin Encapsulation Activity

    SciTech Connect (OSTI)

    Not Available

    1993-03-01T23:59:59.000Z

    This application is being submitted to US EPA pursuant to Title 40, Code of Federal Regulations, Part 61.07, amended. The encapsulation activity will consist of the activities necessary to complete encapsulation of the fuel elements and sludge in 105-KE basin, a storage basin for irradiated N Reactor fuel in Hanford 100-K Area; it currently stores 1,150 MTU of N Reactor irradiated fuel elements transferred to the basin from 1975 through 1989. The application presents the chemical and physical processes relating to the encapsulation activity, source term, expected annual emissions, radionuclide control and monitoring equipment, and projected dose to the maximally exposed individual.

  20. UW-Approved Waste Disposal, Recycling and Treatment Sites Hazardous waste disposal at the University of Washington is coordinated by the EH&S Environmental Programs Office

    E-Print Network [OSTI]

    Wilcock, William

    solid waste, use the approved facilities listed below. This document is primarily intended & sludge Seattle, WA Ventilation Power Cleaning Vactor & parking garage waste Seattle, WA King County Treatment Plant Liquids & sludge Seattle, WA La Farge Cement Kiln Liquids & sludge Seattle, WA Cemex Liquids

  1. ACCIDENT ANALYSES & CONTROL OPTIONS IN SUPPORT OF THE SLUDGE WATER SYSTEM SAFETY ANALYSIS

    SciTech Connect (OSTI)

    WILLIAMS, J.C.

    2003-11-15T23:59:59.000Z

    This report documents the accident analyses and nuclear safety control options for use in Revision 7 of HNF-SD-WM-SAR-062, ''K Basins Safety Analysis Report'' and Revision 4 of HNF-SD-SNF-TSR-001, ''Technical Safety Requirements - 100 KE and 100 KW Fuel Storage Basins''. These documents will define the authorization basis for Sludge Water System (SWS) operations. This report follows the guidance of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', for calculating onsite and offsite consequences. The accident analysis summary is shown in Table ES-1 below. While this document describes and discusses potential control options to either mitigate or prevent the accidents discussed herein, it should be made clear that the final control selection for any accident is determined and presented in HNF-SD-WM-SAR-062.

  2. Energy recovery from sewage sludge by means of fluidised bed gasification

    SciTech Connect (OSTI)

    Gross, Bodo [IZES gGmbH, Altenkesseler Strasse 17, D-66115 Saarbruecken (Germany); Eder, Christian [CET, Christian Eder Technology, Eduard-Didion Strasse, D-66539 Neunkirchen (Germany); Grziwa, Peter [BISANZ Anlagenbau GmbH, Scheidter Strasse 2, D-66123 Saarbruecken (Germany); Horst, Juri [IZES gGmbH, Altenkesseler Strasse 17, D-66115 Saarbruecken (Germany)], E-mail: horst@izes.de; Kimmerle, Klaus [IZES gGmbH, Altenkesseler Strasse 17, D-66115 Saarbruecken (Germany)

    2008-07-01T23:59:59.000Z

    Because of its potential harmful impact on the environment, disposal of sewage sludge is becoming a major problem all over the world. Today the available disposal measures are at the crossroads. One alternative would be to continue its usage as fertiliser or to abandon it. Due to the discussions about soil contamination caused by sewage sludge, some countries have already prohibited its application in agriculture. In these countries, thermal treatment is now presenting the most common alternative. This report describes two suitable methods to directly convert sewage sludge into useful energy on-site at the wastewater treatment plant. Both processes consist mainly of four devices: dewatering and drying of the sewage sludge, gasification by means of fluidised bed technology (followed by a gas cleaning step) and production of useful energy via CHP units as the final step. The process described first (ETVS-Process) is using a high pressure technique for the initial dewatering and a fluidised bed technology utilising waste heat from the overall process for drying. In the second process (NTVS-Process) in addition to the waste heat, solar radiation is utilised. The subsequent measures - gasification, gas cleaning and electric and thermal power generation - are identical in both processes. The ETVS-Process and the NTVS-Process are self-sustaining in terms of energy use; actually a surplus of heat and electricity is generated in both processes.

  3. Basin analysis in the Illinois basin

    SciTech Connect (OSTI)

    Leighton, M.W. (Illinois State Geological Survey, Champaign (USA)); Haney, D. (Kentucky Geological Survey, Lexington (USA)); Hester, N. (Indiana Geological Survey, Bloomington (USA))

    1990-05-01T23:59:59.000Z

    In April 1989, the Illinois State Geological Survey and the Indiana and Kentucky Geological surveys formed the Illinois Basin Consortium (IBC) for the purpose of advancing the geologic understanding of the Illinois basin and of developing basin-wide studies for the assessment and wise development of the Illinois basin energy, mineral, and water resources. Cooperative efforts include work on the AAPG Interior Cratonic Sag Basin volume, Springfield coal study, Paducah CUSMAP study in cooperation with the US Geological Survey, Illinois Basin Cross Section Project, Geologic Society of America Coal Division field trip and workshop on Lower Pennsylvanian geology, workshops in basin analysis, and the Tri-State Committee on correlations in the Pennsylvanian System of the Illinois Basin. A network of 16 regional surface to basement cross sections portraying the structural and stratigraphic framework of the total sedimentary section of the entire basin is in preparation. Based on more than 140 of the deepest wells with wireline logs, the sections will show formation boundaries and gross lithofacies of the entire stratigraphic column. A set of basin-wide maps shows structure, thickness, and coal quality of the economically important Springfield coal seam. These maps were generated from recently joined computerized databases of the three member surveys of IBC. A unified stratigraphic nomenclature of the Pennsylvanian System is being developed, including seven new members and seven new formation names. The goal is to simplify, standardize, and gradually improve the stratigraphic terminology to be used in the Illinois basin.

  4. COMPARATIVE HEALTH IMPACT ASSESSMENTS ON FECAL SLUDGE MANAGEMENT PRACTICES

    E-Print Network [OSTI]

    Richner, Heinz

    i COMPARATIVE HEALTH IMPACT ASSESSMENTS ON FECAL SLUDGE MANAGEMENT PRACTICES: A CASE STUDY OF KLONG Fecal sludge (FS) is widely acknowledged as a major source of infectious pathogens. However, the proper

  5. Caustic Leaching of Sludges from Selected Hanford Tanks

    SciTech Connect (OSTI)

    Chase, C.W.; Egan, B.Z.; Spencer, B.B.

    1998-08-01T23:59:59.000Z

    The objective of this project was to measure the caustic dissolution behavior of sludge components from selected Hanford waste tank sludge samples under different conditions. The dissolution of aluminum, chromium, and other constituents of actual sludge samples in aqueous sodium hydroxide solution was evaluated using various values of temperature, sodium hydroxide concentration, volume of caustic solution per unit mass of sludge (liquid:solids ratio), and leaching time.

  6. Phase Chemistry of Tank Sludge Residual Components

    SciTech Connect (OSTI)

    J.L. Krumhansl

    2002-04-02T23:59:59.000Z

    The US Department of Energy (DOE) has millions of gallons of high level nuclear waste stored in underground tanks at Hanford, Washington and Savannah River, South Carolina. These tanks will eventually be emptied and decommissioned. This will leave a residue of sludge adhering to the interior tank surfaces that may contaminate nearby groundwaters with radionuclides and RCRA metals. Performance assessment (PA) calculations must be carried out prior to closing the tanks. This requires developing radionuclide release models from the sludges so that the PA calculations can be based on credible source terms. These efforts continued to be hindered by uncertainties regarding the actual nature of the tank contents and the distribution of radionuclides among the various phases. In particular, it is of vital importance to know what radionuclides are associated with solid sludge components. Experimentation on actual tank sludges can be difficult, dangerous and prohibitively expensive. The research funded under this grant for the past three years was intended to provide a cost-effective method for developing the needed radionuclide release models using non-radioactive artificial sludges. Insights gained from this work will also have more immediate applications in understanding the processes responsible for heel development in the tanks and in developing effective technologies for removing wastes from the tanks.

  7. Review article The use of urban sewage sludge on pastures

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Review article The use of urban sewage sludge on pastures: the cysticercosis threat Jacques appears to be one of the major pathological threats when sewage sludge is used to fertilise cattle highly prevalent) and Asia (Taenia saginata-like are prevalent). The processing of sludge and the delay

  8. Temperature Modeling in Activated Sludge Systems: A Case Study

    E-Print Network [OSTI]

    Wells, Scott A.

    Temperature Modeling in Activated Sludge Systems: A Case Study Jacek Makinia, Scott A. Wells, Piotr Zima ABSTRACT: A model of temperature dynamics was developed as part of a general model of activated-sludge biochemical-energy inputs and other activated-sludge, heat-balance terms. All the models were tested under

  9. Sensitivity of Optimal Operation of an Activated Sludge Process Model

    E-Print Network [OSTI]

    Skogestad, Sigurd

    Sensitivity of Optimal Operation of an Activated Sludge Process Model Antonio Araujo, Simone sensitivity analysis of optimal operation conducted on an activated sludge process model based on the test.[7] applied a systematic procedure for control structure design of an activated sludge process

  10. Incineration of biological sludge in a fluidized bed

    SciTech Connect (OSTI)

    Ku, W.C.P.

    1988-01-01T23:59:59.000Z

    Incineration rate, ash properties, and percentage destruction of the combustible material were evaluated under different operating conditions. Experimental measurements were made for temperature, air flow rate, sludge size, ash size and sludge composition. A model based on the heat transfer consideration was derived to describe the drying and devolatilization process during sludge incineration. The model assumes that the drying and devolatilization of a sludge particle is manly caused by the heat flowing into the sludge particle from the bed. Parameters affecting the simulation results included sludge size, inert particle size, sludge heat capacity, sludge heat conductivity, operating flow rate and incinerator temperature. A model developed to simulate a batch type air-sand fluidized bed considered the incineration process as being composed of three consecutive operations, namely, drying, devolatilization, and char combustion. The simulation model predicted the dynamic characteristics of sludge incineration in the bed including its percentage completion and the incinerator temperature. The effects of sludge moisture level, sludge size and incinerator operating conditions on the incinerator behavior were also evaluated. The model developed to simulate the behavior of a fluidized bed incinerator under continuous operation was capable of predicting the time to reach steady state, the stack gas composition, the percentage combustion and the auxiliary heat required under various operating conditions, including sludge feed rate and size, air feed rate, and incinerator temperature.

  11. Characterization Data Package for Containerized Sludge Samples Collected from Engineered Container SCS-CON-210

    SciTech Connect (OSTI)

    Fountain, Matthew S.; Fiskum, Sandra K.; Baldwin, David L.; Daniel, Richard C.; Bos, Stanley J.; Burns, Carolyn A.; Carlson, Clark D.; Coffey, Deborah S.; Delegard, Calvin H.; Edwards, Matthew K.; Greenwood, Lawrence R.; Neiner, Doinita; Oliver, Brian M.; Pool, Karl N.; Schmidt, Andrew J.; Shimskey, Rick W.; Sinkov, Sergey I.; Snow, Lanee A.; Soderquist, Chuck Z.; Thompson, Christopher J.; Trang-Le, Truc LT; Urie, Michael W.

    2013-09-10T23:59:59.000Z

    This data package contains the K Basin sludge characterization results obtained by Pacific Northwest National Laboratory during processing and analysis of four sludge core samples collected from Engineered Container SCS-CON-210 in 2010 as requested by CH2M Hill Plateau Remediation Company. Sample processing requirements, analytes of interest, detection limits, and quality control sample requirements are defined in the KBC-33786, Rev. 2. The core processing scope included reconstitution of a sludge core sample distributed among four to six 4-L polypropylene bottles into a single container. The reconstituted core sample was then mixed and subsampled to support a variety of characterization activities. Additional core sludge subsamples were combined to prepare a container composite. The container composite was fractionated by wet sieving through a 2,000 micron mesh and a 500-micron mesh sieve. Each sieve fraction was sampled to support a suite of analyses. The core composite analysis scope included density determination, radioisotope analysis, and metals analysis, including the Waste Isolation Pilot Plant Hazardous Waste Facility Permit metals (with the exception of mercury). The container composite analysis included most of the core composite analysis scope plus particle size distribution, particle density, rheology, and crystalline phase identification. A summary of the received samples, core sample reconstitution and subsampling activities, container composite preparation and subsampling activities, physical properties, and analytical results are presented. Supporting data and documentation are provided in the appendices. There were no cases of sample or data loss and all of the available samples and data are reported as required by the Quality Assurance Project Plan/Sampling and Analysis Plan.

  12. CHARACTERIZATION OF ACTINIDES IN SIMULATED ALKALINE TANK WASTE SLUDGES AND LEACHATES

    SciTech Connect (OSTI)

    Nash, Kenneth L.

    2008-11-20T23:59:59.000Z

    In this project, both the fundamental chemistry of actinides in alkaline solutions (relevant to those present in Hanford-style waste storage tanks), and their dissolution from sludge simulants (and interactions with supernatants) have been investigated under representative sludge leaching procedures. The leaching protocols were designed to go beyond conventional alkaline sludge leaching limits, including the application of acidic leachants, oxidants and complexing agents. The simulant leaching studies confirm in most cases the basic premise that actinides will remain in the sludge during leaching with 2-3 M NaOH caustic leach solutions. However, they also confirm significant chances for increased mobility of actinides under oxidative leaching conditions. Thermodynamic data generated improves the general level of experiemental information available to predict actinide speciation in leach solutions. Additional information indicates that improved Al removal can be achieved with even dilute acid leaching and that acidic Al(NO3)3 solutions can be decontaminated of co-mobilized actinides using conventional separations methods. Both complexing agents and acidic leaching solutions have significant potential to improve the effectiveness of conventional alkaline leaching protocols. The prime objective of this program was to provide adequate insight into actinide behavior under these conditions to enable prudent decision making as tank waste treatment protocols develop.

  13. Acceptance Test Plan for the Sludge Pickup Adaptor

    SciTech Connect (OSTI)

    PITNER, A.L.

    2000-03-29T23:59:59.000Z

    This test plan documents the acceptance testing of the sludge pickup adapter for potential use during PSI Phases 3 and 4 fuel cleanliness inspection activities. The adaptex is attached to the strainer tip of the vacuum wand and used to suction up residual sludge captured in a sludge collection tray. The material is vacuumed into a chamber of known volume in the sludge pickup adapter. The device serves as an aid in helping to determine whether the observed quantity of sludge is within allowable limits (1.4 cm{sup 3} per fuel assembly). This functionality test involves underwater testing in the 305 Building Cold Test Facility to verify that sludge can be successfully vacuumed from a collection tray. Ancillary activities in this acceptance test include demonstration that the sludge pickup adapter CM be successfully attached to and detached from the vacuum wand underwater.

  14. SLUDGE BATCH 5 SIMULANT FLOWSHEET STUDIES

    SciTech Connect (OSTI)

    Lambert, D; Michael Stone, M; Bradley Pickenheim, B; David Best, D; David Koopman, D

    2008-10-03T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) will transition from Sludge Batch 4 (SB4) processing to Sludge Batch 5 (SB5) processing in early fiscal year 2009. Tests were conducted using non-radioactive simulants of the expected SB5 composition to determine the impact of varying the acid stoichiometry during the Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) processes. The work was conducted to meet the Technical Task Request (TTR) HLW/DWPF/TTR-2007-0007, Rev. 1 and followed the guidelines of a Task Technical and Quality Assurance Plan (TT&QAP). The flowsheet studies are performed to evaluate the potential chemical processing issues, hydrogen generation rates, and process slurry rheological properties as a function of acid stoichiometry. Initial SB5 flowsheet studies were conducted to guide decisions during the sludge batch preparation process. These studies were conducted with the estimated SB5 composition at the time of the study. The composition has changed slightly since these studies were completed due to changes in the washing plan to prepare SB5 and the estimated SB4 heel mass. Nine DWPF process simulations were completed in 4-L laboratory-scale equipment using both a batch simulant (Tank 51 simulant after washing is complete) and a blend simulant (Tank 40 simulant after Tank 51 transfer is complete). Each simulant had a set of four SRAT and SME simulations at varying acid stoichiometry levels (115%, 130%, 145% and 160%). One additional run was made using blend simulant at 130% acid that included additions of the Actinide Removal Process (ARP) waste prior to acid addition and the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU) waste following SRAT dewatering. There are several parameters that are noteworthy concerning SB5 sludge: (1) This is the first batch DWPF will be processing that contains sludge that has had a significant fraction of aluminum removed through aluminum dissolution. (2) The sludge is high in mercury. (3) The sludge is high in noble metals. (4) The sludge is high in U and Pu--components that are not added in sludge simulants. Two SB5 processing issues were noted during testing. First, high hydrogen generation rates were measured during experiments with both the blend and batch simulant at high acid stoichiometry. Also, the reflux time was extended due to the high mercury concentration in both the batch and blend simulant. Adding ARP will extend processing times in DWPF. The ARP caustic boil took approximately six hours. The boiling time during the experiment with added MCU was 14 hours at the maximum DWPF steam flux rate. This is comparable to the DWPF processing time for dewatering plus reflux without MCU at a 5000 lbs/hr boil-up rate, but would require significantly more time at boiling at 2000-2500 lbs/hr boil-up rate. The addition of ARP and MCU did not cause any other processing issues, since foaming, rheology and hydrogen generation were less of an issue while processing with ARP/MCU.

  15. Water Basins Civil Engineering

    E-Print Network [OSTI]

    Provancher, William

    Water Basins Civil Engineering Objective · Connect the study of water, water cycle, and ecosystems with engineering · Discuss how human impacts can effect our water basins, and how engineers lessen these impacts: · The basic concepts of water basins are why they are important · To use a topographic map · To delineate

  16. Technology study of Gunite tank sludge mobilization at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    DeVore, J.R.; Herrick, T.J.; Lott, K.E.

    1994-12-01T23:59:59.000Z

    The Oak Ridge National Laboratory (ORNL) Gunite Tank Sludge Mobilization Technology Study was initiated to support the Gunite Tank Treatability Study effort. The technology study surveyed the methods and technologies available for tank cleaning and sludge mobilization in a radioactive environment. Technologies were identified and considered for applicability to the Gunite and Associated Tanks (GAAT) problems. These were then either accepted for further study or rejected as not applicable. Technologies deemed applicable to the GAAT sludge removal project were grouped for evaluation according to (1) deployment method, (2) types of remotely operated end effector equipment applicable to removal of sludge, (3) methods for removing wastes from the tanks, and (4) methods for concrete removal. There were three major groups of deployment technologies: ``past practice`` technologies, mechanical arm-based technologies, and vehicle-based technologies. The different technologies were then combined into logical sequences of deployment platform, problem, end effector, conveyance, post-removal treatment required (if any), and disposition of the waste. Many waste removal options are available, but the best technology in one set of circumstances at one site might not be the best type to use at a different site. No single technology is capable of treating the entire spectrum of wastes that will be encountered in GAAT. None of the systems used in other industries appears to be suitable, primarily because of the nature of the sludges in the GAAT Operable Unit (OU), their radiation levels, and tank geometries. Other commercial technologies were investigated but rejected because the authors did not believe them to be applicable.

  17. Permeation of Tank C-103 sludge simulant by organic solvent

    SciTech Connect (OSTI)

    Gerber, M.A.

    1995-03-01T23:59:59.000Z

    The plan for stabilizing underground storage tanks (USTs) calls for draining the supernate from the tanks; however, there is concern that draining the supernate from Tank C-103 will degrade safety in the tank. The sludge in Tank C-103 contains ranges in depth from 1 to 1.5 m and is covered by both an aqueous phase and a separate organic layer. The main concern is that draining the supernate will cause the solvent to permeate the sludge solids and provide a source of fuel for a fire on the surface of the drained sludge. The question of whether the solvent will permeate sludge that is 1 to 1.5 m deep after the tank is dewatered is the purpose of the tests conducted and described in this report. Evaluation of the solvent permeation mechanism required the preparation of solvent, supernate, and sludge simulants based on the known chemistry of Tank C-103. Solvent and aqueous phase supernate simulants are based on the results of fiscal year 1994 sampling of the tank solvent and supernate. Sludge simulant is based on the chemical analyses of tank sludge samples retrieved in 1986. Experiments were conducted with each simulant to evaluate solvent permeation under matric potentials ranging from 0.8 m to 1.8 m of supernate. The amount of solvent recovered for each experiment was recorded as well as the maximum amount of solvent that could be din the sludge based on solvent recovered from resuspended sludge and solvent not recovered. The wt% of water remaining in the sludge was also recorded for each experiment, which was determined by measuring the weight of the sludge after drying it. One observation noted from the test results is that the finer sludge material tended to have a greater amount of solvent loss compared to the coarser sludge material at comparable levels of vacuum. At this time, there is no explanation.

  18. Tank waste treatment science task quarterly report, April 1995--June 1995

    SciTech Connect (OSTI)

    LaFemina, J.P.

    1995-07-01T23:59:59.000Z

    This report describes the work performed by the Pacific Northwest Laboratory (PNL) during the third quarter of FY 1995 under the Tank Waste Treatment Science Task of the Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project. Work was performed in the following areas: (1) analytical methods development, (2) sludge dissolution modeling, (3) sludge characterization studies, (4) sludge component speciation, (5) pretreatment chemistry evaluation, and (6) colloidal studies for solid-liquid separations.

  19. Assessment of the KE Basin Sand Filter Inventory In Support of Hazard Categorization

    SciTech Connect (OSTI)

    Ross, Steven B.; Young, Jonathan

    2005-09-28T23:59:59.000Z

    In 1978, the water cleaning system for the KE Basin was upgraded by adding a sand filter and ion exchange columns. Basin water containing finely divided solids is collected by three surface skimmers and pumped to the sand filter. Filtrate from the sand filter is further treated in the ion exchange modules. The suspended solids accumulate in the sand until the pressure drop across the filter reaches established operating limits, at which time the sand filter is backwashed. The backwash is collected in the NLOP, where the solids are allowed to settle as sludge. Figure 2-1 shows a basic piping and instrumentation diagram depicting the relationship among the basin skimmers, sand filter, and NLOP. During the course of deactivation and decommissioning (D&D) of the K-Basins, the sand filter and its media will need to be dispositioned. The isotopic distribution of the sludge in the sand filter has been estimated in KE Basin Sand Filter Monolith DQO (KBC-24705). This document estimates the sand filter contribution to the KE hazard categorization using the data from the DQO.

  20. Constructed Wetlands and Waste Stabilization Ponds for municipal wastewater treatment in France: comparison of

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    13 Constructed Wetlands and Waste Stabilization Ponds for municipal wastewater treatment in France In France, vertical flow constructed wetlands and waste stabilisation ponds are both extensive treatment Vertical Flow Constructed Wetlands, Waste Stabilization Ponds, operation and maintenance, sludge management

  1. Behavior of Uranium(VI) during HEDPA Leaching for Aluminum Dissolution in Tank Waste Sludges

    E-Print Network [OSTI]

    Powell, Brian A.; Rao, Linfeng; Nash, Kenneth L.; Martin, Leigh

    2006-01-01T23:59:59.000Z

    Dissolution in Tank Waste Sludges Brian A. Powell 1 ,to produce a clay-like sludge layer, a slurry phase, and anto be concentrated in the sludge phase, which is primarily

  2. Examination of Uranium(VI) Leaching During Ligand Promoted Dissolution of Waste Tank Sludge Surrogates

    E-Print Network [OSTI]

    Powell, Brian A.

    2008-01-01T23:59:59.000Z

    in Hanford waste tank sludge simulants. J. Nucl. Sci.from simulated tank waste sludges. Sep. Sci. Tech. 38(2),Dissolution of Waste Tank Sludge Surrogates. In preparation,

  3. Use of nutrients of sewage sludge in the initial development of Copaifera langsdorffii

    E-Print Network [OSTI]

    Sampaio, Thalita Fernanda; Guerrini, Iraê Amaral; Croce, Ciro; de Toledo, Maria Angélica; Morales, Marina

    2009-01-01T23:59:59.000Z

    under the 20 t ha -1 of sludge rate. Figure 1: CopaibaSupl. K) and sewage sludge doses (2.5, 5, 10, 15 e 20 t ha -dm Fe Mn Zn Table 2: Sewage sludge chemical characteristics.

  4. Field-Measured Oxidation Rates of Biologically Reduced Selenium in Sludge

    E-Print Network [OSTI]

    Benson, Sally M.; Daggett, John; Zawislansi, Peter

    1999-01-01T23:59:59.000Z

    Reduced Selenium in Sludge Sally M. Benson, John Daggett andCalifornia 94720 U.S.A. Sludge generated during surface-Finding safe and economical sludge disposal methods requires

  5. Applications of Energy Efficiency Technologies in Wastewater Treatment Facilities 

    E-Print Network [OSTI]

    Chow, S.; Werner, L.; Wu, Y. Y.; Ganji, A. R.

    2009-01-01T23:59:59.000Z

    % of the electrical power in Northern and Central California. Activated sludge is the most common method for wastewater treatment, and at the same time the most energy intensive process. New energy efficient technologies can help reduce energy consumption...

  6. TESTING OF ENHANCED CHEMICAL CLEANING OF SRS ACTUAL WASTE TANK 5F AND TANK 12H SLUDGES

    SciTech Connect (OSTI)

    Martino, C.; King, W.

    2011-08-22T23:59:59.000Z

    Forty three of the High Level Waste (HLW) tanks at the Savannah River Site (SRS) have internal structures that hinder removal of the last approximately five thousand gallons of waste sludge solely by mechanical means. Chemical cleaning can be utilized to dissolve the sludge heel with oxalic acid (OA) and pump the material to a separate waste tank in preparation for final disposition. This dissolved sludge material is pH adjusted downstream of the dissolution process, precipitating the sludge components along with sodium oxalate solids. The large quantities of sodium oxalate and other metal oxalates formed impact downstream processes by requiring additional washing during sludge batch preparation and increase the amount of material that must be processed in the tank farm evaporator systems and the Saltstone Processing Facility. Enhanced Chemical Cleaning (ECC) was identified as a potential method for greatly reducing the impact of oxalate additions to the SRS Tank Farms without adding additional components to the waste that would extend processing or increase waste form volumes. In support of Savannah River Site (SRS) tank closure efforts, the Savannah River National Laboratory (SRNL) conducted Real Waste Testing (RWT) to evaluate an alternative to the baseline 8 wt. % OA chemical cleaning technology for tank sludge heel removal. The baseline OA technology results in the addition of significant volumes of oxalate salts to the SRS tank farm and there is insufficient space to accommodate the neutralized streams resulting from the treatment of the multiple remaining waste tanks requiring closure. ECC is a promising alternative to bulk OA cleaning, which utilizes a more dilute OA (nominally 2 wt. % at a pH of around 2) and an oxalate destruction technology. The technology is being adapted by AREVA from their decontamination technology for Nuclear Power Plant secondary side scale removal. This report contains results from the SRNL small scale testing of the ECC process using SRS sludge tank sample material. A Task Technical and Quality Assurance Plan (TTQAP) details the experimental plan as outlined by the Technical Task Request (TTR). The TTR identifies that the data produced by this testing and results included in this report will support the technical baseline with portions having a safety class functional classification. The primary goals for SRNL RWT are as follows: (1) to confirm ECC performance with real tank sludge samples, (2) to determine the impact of ECC on fate of actinides and the other sludge metals, and (3) to determine changes, if any, in solids flow and settling behavior.

  7. Utilizing Divers in Support of Spent Fuel Basin Closure Subproject

    SciTech Connect (OSTI)

    Allen Nellesen

    2005-01-01T23:59:59.000Z

    A number of nuclear facilities in the world are aging and with this comes the fact that we have to either keep repairing them or decommission them. At the Department of Energy Idaho Site (DOEID) there are a number of facilities that are being decommissioned, but the facilities that pose the highest risk to the large aquifer that flows under the site are given highest priorities. Aging spent nuclear fuel pools at DOE-ID are among the facilities that pose the highest risk, therefore four pools were targeted for decommissioning in Fiscal Year 2004. To accomplish this task the Idaho Completion Project (ICP) of Bechtel BWXT Idaho, LLC, put together an integrated Basin Closure Subproject team. The team was assigned a goal to look beyond traditional practices at the Idaho National Engineering and Environmental Laboratory (INEEL) to find ways to get the basin closure work done safer and more efficiently. The Idaho Completion Project (ICP) was faced with a major challenge – cleaning and preparing aging spent nuclear fuel basins for closure by removing sludge and debris, as necessary, and removing water to eliminate a potential risk to the Snake River Plain Aquifer. The project included cleaning and removing water from four basins. Two of the main challenges to a project like this is the risk of contamination from the basin walls and floors becoming airborne as the water is removed and keeping personnel exposures ALARA. ICP’s baseline plan had workers standing at the edges of the basins and on rafts or bridge cranes and then using long-handled tools to manually scrub the walls of basin surfaces. This plan had significant risk of skin contamination events, workers falling into the water, or workers sustaining injuries from the awkward working position. Analysis of the safety and radiation dose risks presented by this approach drove the team to look for smarter ways to get the work done.

  8. Phase chemistry and radionuclide retention from simulated tank sludges

    SciTech Connect (OSTI)

    KRUMHANSL,JAMES L.; LIU,J.; ARTHUR,SARA E.; HUTCHERSON,SHEILA K.; QIAN,MORRIS; ANDERSON,HOWARD L.

    2000-05-19T23:59:59.000Z

    Decommissioning high level nuclear waste tanks will leave small amounts of residual sludge clinging to the walls and floor of the structures. The permissible amount of material left in the tanks depends on the radionuclide release characteristics of the sludge. At present, no systematic process exists for assessing how much of the remaining inventory will migrate, and which radioisotopes will remain relatively fixed. Working with actual sludges is both dangerous and prohibitively expensive. Consequently, methods were developed for preparing sludge simulants and doping them with nonradioactive surrogates for several radionuclides and RCRA metals of concern in actual sludges. The phase chemistry of these mixes was found to be a reasonable match for the main phases in actual sludges. Preliminary surrogate release characteristics for these sludges were assessed by lowering the ionic strength and pH of the sludges in the manner that would occur if normal groundwater gained access to a decommissioned tank. Most of the Se, Cs and Tc in the sludges will be released into the first pulse of groundwater passing through the sludge. A significant fraction of the other surrogates will be retained indefinitely by the sludges. This prolonged sequestration results from a combination coprecipitated and sorbed into or onto relatively insoluble phases such as apatite, hydrous oxides of Fe, Al, Bi and rare earth oxides and phosphates. The coprecipitated fraction cannot be released until the host phase dissolves or recrystallizes. The sorbed fraction can be released by ion exchange processes as the pore fluid chemistry changes. However, these releases can be predicted based on a knowledge of the fluid composition and the surface chemistry of the solids. In this regard, the behavior of the hydrous iron oxide component of most sludges will probably play a dominant role for many cationic radionuclides while the hydrous aluminum oxides may be more important in governing anion releases.

  9. SAVANNAH RIVER SITE R REACTOR DISASSEMBLY BASIN IN SITU DECOMMISSIONING

    SciTech Connect (OSTI)

    Langton, C.; Blankenship, J.; Griffin, W.; Serrato, M.

    2009-12-03T23:59:59.000Z

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate in tact, structurally sound facilities that are no longer needed for their original purpose of, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate if from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,424 cubic meters or 31,945 cubic yards. Portland cement-based structural fill materials were design and tested for the reactor ISD project and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and work flow considerations, the recommended maximum lift height is 5 feet with 24 hours between lifts. Pertinent data and information related to the SRS 105-R-Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs and testing, and fill placement strategy. This information is applicable to decommissioning both the 105-P and 105-R facilities. The ISD process for the entire 105-P and 105-R reactor facilities will require approximately 250,000 cubic yards (191,140 cubic meters) of grout and 2,400 cubic yards (1,840 cubic meters) of structural concrete which will be placed over a twelve month period to meet the accelerated schedule ISD schedule. The status and lessons learned in the SRS Reactor Facility ISD process will be described.

  10. ELECTROCHEMICAL CORROSION STUDY FOR TANK 241-AY-102 SLUDGE

    SciTech Connect (OSTI)

    DUNCAN JB

    2002-09-24T23:59:59.000Z

    The report describes the analyses performed on core samples from the sludge region of the waste in Tank 241-AY-102 to determine the electrochemical corrosion potential.

  11. activated sludge wastewater: Topics by E-print Network

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

    The wastewater shows 7 Temperature Modeling in Activated Sludge Systems: A Case Study Environmental Management and Restoration Websites Summary: steady-state and dynamic...

  12. Testing fluidized bed incinerators for energy-efficient operation for the Southtowns Sewage Treatment Agency. Final report

    SciTech Connect (OSTI)

    NONE

    1996-01-01T23:59:59.000Z

    Two methods for improving the energy efficiency of fluidized bed sludge incinerators were evaluated. The first method used paper pulp and polymer as conditioning agents for municipal sludge instead of lime and ferric chloride. Automatic control of the incinerator was the second method evaluated for energy savings. To evaluate the use of paper pulp and polymer as conditioning agents, varying quantities of paper pulp were added to the liquid sludge to determine the optimal sludge-to-paper pulp ratio. The effect of the paper pulp and polymer-conditioned sludge on plant operations also was evaluated. When compared to sludge conditioned with lime and ferric chloride, the paper pulp and polymer-conditioned sludge had similar cake release and feed characteristics, higher BTU values for the dry sludge solids, required less auxiliary fuel for incineration, and generated less ash for disposal. The paper pulp and polymer did not have any appreciable negative effects on the operation of the wastewater treatment plant. It was estimated that processing and incinerating the sludge conditioned with paper pulp and polymer resulted in a cost savings of up to $91.73 per dry ton of activated sludge solids. To evaluate the effect of automatic control, all the incinerator operating parameters including air flow rates, fuel oil feed rates, and sludge feed rates, were automatically monitored and controlled to minimize auxiliary fuel oil use and to keep the incinerator running at optimal conditions. Although effective, the estimated cost savings for automatic control of the incinerator were small.

  13. Finding of no significant impact: Changes in the sanitary sludge land application program on the Oak Ridge Reservation, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    NONE

    1996-10-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1042) that evaluates potential impacts of proposed changes in the sanitary sludge land application program on the DOE Oak Ridge Reservation (ORR), Oak Ridge, Tennessee. Changes in lifetime sludge land application limits and radionuclide loading are proposed, and two new sources of sewage sludge from DOE facilities would be transported to the City of Oak Ridge Publicly Owned Treatment Works (COR POTW). Lifetime sludge land application limits would increase from 22 tons/acre to 50 tons/acre, which is the limit approved and permitted by the Tennessee Department of Environment and Conservation (TDEC). With the approval of TDEC, the permissible radiological dose from sludge land application would change from the current limit of 2x background radionuclide concentrations in receiving soils to a risk-based dose limit of 4 millirem (mrem) per year for the maximally exposed individual. Sludge land application sites would not change from those that are currently part of the program. Based on the results of the analysis reported in the EA, DOE has determined that the proposed action is not a major federal action that would significantly affect the quality of the human environment within the context of the National Environmental Policy Act of 1969 (NEPA). Therefore, preparation of an environmental impact statement (EIS) is not necessary, and DOE is issuing this Finding of No Significant Impact (FONSI). 70 refs., 2 figs., 17 tabs.

  14. SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE

    SciTech Connect (OSTI)

    Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

    2011-11-16T23:59:59.000Z

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest projected noble metals content for SB7b. Characterization was performed on the Tank 51 SB7b samples and SRNL performed DWPF simulations using the Tank 40 SB7b material. This report documents: (1) The preparation and characterization of the Tank 51 SB7b and Tank 40 SB7b samples. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the SB7b Tank 40 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a nonradioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the SRAT receipt, SRAT product, and SME product. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7b related data together in a single permanent record and to discuss the overall aspects of SB7b processing.

  15. Ecosystem Diagnosis and Treatment Planning Model as Applied to Supplementation : Model Description, User Guide, and Theoretical Documentation for the Model Introduced in the Summary Report Series on Supplementation in the Columbia Basin.

    SciTech Connect (OSTI)

    Lestelle, Lawrence C.; Lichatowich, James A.; Mobrand, Lars E.; Cullinan, Valerie I.

    1994-03-01T23:59:59.000Z

    This document describes the formulation and operation of a model designed to assist in planning supplementation projects. It also has application in examining a broader array of questions related to natural fish production and stock restoration. The model is referred to as the Ecosystem Diagnosis and Treatment (EDT) Model because of its utility in helping to diagnose and identify possible treatments to be applied to natural production problems for salmonids. It was developed through the Regional Assessment of Supplementation Project (RASP), which was an initiative to help coordinate supplementation planning in the Columbia Basin. The model is operated within the spreadsheet environment of Quattro Pro using a system of customized menus. No experience with spreadsheet macros is required to operate it. As currently configured, the model should only be applied to spring chinook; modifications are required to apply it to fall chinook and other species. The purpose of the model is to enable managers to consider possible outcomes of supplementation under different sets of assumptions about the natural production system and the integration of supplementation fish into that system. It was designed to help assess uncertainty and the relative risks and benefits of alternative supplementation strategies. The model is a tool to facilitate both planning and learning; it is not a predictive model. This document consists of three principal parts. Part I provides a description of the model. Part II is a guide to running the model. Part III provides theoretical documentation. In addition, a sensitivity analysis of many of the model's parameters is provided in the appendix. This analysis was used to test whether the model produces consistent and reasonable results and to assess the relative effects of specific parameter inputs on outcome.

  16. Filtration and Leach Testing for PUREX Cladding Sludge and REDOX Cladding Sludge Actual Waste Sample Composites

    SciTech Connect (OSTI)

    Shimskey, Rick W.; Billing, Justin M.; Buck, Edgar C.; Casella, Amanda J.; Crum, Jarrod V.; Daniel, Richard C.; Draper, Kathryn E.; Edwards, Matthew K.; Hallen, Richard T.; Kozelisky, Anne E.; MacFarlan, Paul J.; Peterson, Reid A.; Swoboda, Robert G.

    2009-03-02T23:59:59.000Z

    A testing program evaluating actual tank waste was developed in response to Task 4 from the M-12 External Flowsheet Review Team (EFRT) issue response plan (Barnes and Voke 2006). The test program was subdivided into logical increments. The bulk water-insoluble solid wastes that are anticipated to be delivered to the Hanford Waste Treatment and Immobilization Plant (WTP) were identified according to type such that the actual waste testing could be targeted to the relevant categories. Under test plan TP RPP WTP 467 (Fiskum et al. 2007), eight broad waste groupings were defined. Samples available from the 222S archive were identified and obtained for testing. Under this test plan, a waste testing program was implemented that included: • Homogenizing the archive samples by group as defined in the test plan. • Characterizing the homogenized sample groups. • Performing parametric leaching testing on each group for compounds of interest. • Performing bench-top filtration/leaching tests in the hot cell for each group to simulate filtration and leaching activities if they occurred in the UFP2 vessel of the WTP Pretreatment Facility. This report focuses on a filtration/leaching test performed using two of the eight waste composite samples. The sample groups examined in this report were the plutonium-uranium extraction (PUREX) cladding waste sludge (Group 3, or CWP) and reduction-oxidation (REDOX) cladding waste sludge (Group 4, or CWR). Both the Group 3 and 4 waste composites were anticipated to be high in gibbsite, thus requiring caustic leaching. WTP RPT 167 (Snow et al. 2008) describes the homogenization, characterization, and parametric leaching activities before benchtop filtration/leaching testing of these two waste groups. Characterization and initial parametric data in that report were used to plan a single filtration/leaching test using a blend of both wastes. The test focused on filtration testing of the waste and caustic leaching for aluminum, in the form of gibbsite, and its impact on filtration. The initial sample was diluted with a liquid simulant to simulate the receiving concentration of retrieved tank waste into the UFP2 vessel (< 10 wt% undissolved solids). Filtration testing was performed on the dilute waste sample and dewatered to a higher solids concentration. Filtration testing was then performed on the concentrated slurry. Afterwards, the slurry was caustic leached to remove aluminum present in the undissolved solid present in the waste. The leach was planned to simulate leaching conditions in the UFP2 vessel. During the leach, slurry supernate samples were collected to measure the dissolution rate of aluminum in the waste. After the slurry cooled down from the elevated leach temperature, the leach liquor was dewatered from the solids. The remaining slurry was rinsed and dewatered with caustic solutions to remove a majority of the dissolved aluminum from the leached slurry. The concentration of sodium hydroxide in the rinse solutions was high enough to maintain the solubility of the aluminum in the dewatered rinse solutions after dilution of the slurry supernate. Filtration tests were performed on the final slurry to compare to filtration performance before and after caustic leaching.

  17. Combined process for 2,4-Dichlorophenoxyacetic acid treatment Coupling of an electrochemical system with a biological treatment.

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    system with a biological treatment. Jean-Marie Fontmorina,b *, Florence Fourcadea,b Florence Genestec-made electrochemical flow cell was used for the pre-treatment and a biological treatment was then carried out using activated sludge supplied by a local wastewater treatment plant. 2,4-D was used as a target compound

  18. Idaho Cleanup Project CPP-603A basin deactivation waste management 2007

    SciTech Connect (OSTI)

    Croson, D.V.; Davis, R.H.; Cooper, W.B. [CH2M-WG Idaho, LLC, Idaho Cleanup Project, Idaho National Laboratory, Idaho Falls, ID (United States)

    2007-07-01T23:59:59.000Z

    The CPP-603A basin facility is located at the Idaho Nuclear Technology and Engineering Center (INTEC) at the U.S. Department of Energy's (DOE) Idaho National Laboratory (INL). CPP-603A operations are part of the Idaho Cleanup Project (ICP) that is managed by CH2M-WG Idaho, LLC (CWI). Once the inventoried fuel was removed from the basins, they were no longer needed for fuel storage. However, they were still filled with water to provide shielding from high activity debris and contamination, and had to either be maintained so the basins did not present a threat to public or worker health and safety, or be isolated from the environment. The CPP-603A basins contained an estimated 50,000 kg (110,200 lbs) of sludge. The sludge was composed of desert sand, dust, precipitated corrosion products, and metal particles from past cutting operations. The sediment also contained hazardous constituents and radioactive contamination, including cadmium, lead, and U-235. An Engineering Evaluation/Cost Analysis (EE/CA), conducted pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), evaluated the risks associated with deactivation of the basins and the alternatives for addressing those risks. The recommended action identified in the Action Memorandum was to perform interim stabilization of the basins. The sludge in the basins was removed and treated in accordance with the Hazardous Waste Management Act/Resource Conservation and Recovery Act (HWMA/RCRA) and disposed at the INL Radioactive Waste Management Complex (RWMC). A Non-Time Critical Removal Action (NTCRA) was conducted under CERCLA to reduce or eliminate other hazards associated with maintaining the facility. The CERCLA NTCRA included removing a small high-activity debris object (SHADO 1); consolidating and mapping the location of debris objects containing Co-60; removing, treating, and disposing of the basin water; and filling the basins with grout/controlled low strength material (CLSM). The NTCRA is an interim action that reduces the risks to human health and the environment by minimizing the potential for release of hazardous substances. The interim action does not prejudice the final end-state alternative. (authors)

  19. River Basin Commissions (Indiana)

    Broader source: Energy.gov [DOE]

    This legislation establishes river basin commissions, for the Kankakee, Maumee, St. Joseph, and Upper Wabash Rivers. The commissions facilitate and foster cooperative planning and coordinated...

  20. Enterprise Assessments, Review of the Hanford Site Sludge Treatment...

    Energy Savers [EERE]

    Project Engineered Container Retrieval and Transfer System Preliminary Documented Safety Analysis, Revision 00 - April 2015 Enterprise Assessments, Review of the Hanford Site...

  1. Operational Awareness Review of the Hanford Sludge Treatment...

    Office of Environmental Management (EM)

    Design, Preliminary Design Safety Basis, Final Design Safety Basis, Documented Safety Analysis Preparation, T-Plant Safety Basis, and Transportation Safety Basis. The...

  2. SLUDGE TREATMENT PROJECT KOP CONCEPTUAL DESIGN CONTROL DECISION REPORT

    SciTech Connect (OSTI)

    CARRO CA

    2010-03-09T23:59:59.000Z

    This control decision addresses the Knock-Out Pot (KOP) Disposition KOP Processing System (KPS) conceptual design. The KPS functions to (1) retrieve KOP material from canisters, (2) remove particles less than 600 {micro}m in size and low density materials from the KOP material, (3) load the KOP material into Multi-Canister Overpack (MCO) baskets, and (4) stage the MCO baskets for subsequent loading into MCOs. Hazard and accident analyses of the KPS conceptual design have been performed to incorporate safety into the design process. The hazard analysis is documented in PRC-STP-00098, Knock-Out Pot Disposition Project Conceptual Design Hazard Analysis. The accident analysis is documented in PRC-STP-CN-N-00167, Knock-Out Pot Disposition Sub-Project Canister Over Lift Accident Analysis. Based on the results of these analyses, and analyses performed in support of MCO transportation and MCO processing and storage activities at the Cold Vacuum Drying Facility (CVDF) and Canister Storage Building (CSB), control decision meetings were held to determine the controls required to protect onsite and offsite receptors and facility workers. At the conceptual design stage, these controls are primarily defined by their safety functions. Safety significant structures, systems, and components (SSCs) that could provide the identified safety functions have been selected for the conceptual design. It is anticipated that some safety SSCs identified herein will be reclassified based on hazard and accident analyses performed in support of preliminary and detailed design.

  3. Enterprise Assessments, Review of the Hanford Site Sludge Treatment Project

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011 Strategic Plan Departmentof EnergyPublic

  4. Independent Oversight Activity Report, Hanford Sludge Treatment Project -

    Energy Savers [EERE]

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov You are being directed off Energy.gov.Energy02.pdf7 OPAM Flash2011-37EnergySubmitRoad |WaterEditionIncreasing

  5. Enterprise Assessments, Review of the Hanford Site Sludge Treatment Project

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels DataDepartment of Energy Your Density Isn't Your Destiny:RevisedAdvisoryStandardGeneration | Department ofDecember 2014 |Reviews -

  6. Independent Activity Report, Hanford Sludge Treatment Project - February

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked Questions for DOEthe RankingReform atSolar Energy Awareness in El- November

  7. APPLICATION OF SEWAGE SLUDGES AND COMPOSTS BPG NOTE 6

    E-Print Network [OSTI]

    APPLICATION OF SEWAGE SLUDGES AND COMPOSTS BPG NOTE 6 Best Practice Guidance for Land Regeneration harmful organisms (plant, animal and human pathogens) in insufficiently composted materials · If C NOTE 6 PAGE 2 Applications of sewage sludges and composts Forestry Tree growth on nutrient

  8. High Level Waste System Impacts from Acid Dissolution of Sludge

    SciTech Connect (OSTI)

    KETUSKY, EDWARD

    2006-04-20T23:59:59.000Z

    This research evaluates the ability of OLI{copyright} equilibrium based software to forecast Savannah River Site High Level Waste system impacts from oxalic acid dissolution of Tank 1-15 sludge heels. Without further laboratory and field testing, only the use of oxalic acid can be considered plausible to support sludge heel dissolution on multiple tanks. Using OLI{copyright} and available test results, a dissolution model is constructed and validated. Material and energy balances, coupled with the model, identify potential safety concerns. Overpressurization and overheating are shown to be unlikely. Corrosion induced hydrogen could, however, overwhelm the tank ventilation. While pH adjustment can restore the minimal hydrogen generation, resultant precipitates will notably increase the sludge volume. OLI{copyright} is used to develop a flowsheet such that additional sludge vitrification canisters and other negative system impacts are minimized. Sensitivity analyses are used to assess the processability impacts from variations in the sludge/quantities of acids.

  9. Sewage sludge drying by energy recovery from OFMSW composting: Preliminary feasibility evaluation

    SciTech Connect (OSTI)

    Rada, Elena Cristina; Ragazzi, Marco; Villotti, Stefano [University of Trento, Department of Civil, Environmental and Mechanical Engineering, via Mesiano 77, I-38123 Trento (Italy); Torretta, Vincenzo, E-mail: vincenzo.torretta@uninsubria.it [Insubria University of Varese, Department of Biotechnologies and Life Sciences, Via G.B. Vico 46, I-21100 Varese (Italy)

    2014-05-01T23:59:59.000Z

    Highlights: • The aim is to support the drying of sewage sludge, using a solar greenhouse. • The system allows the exploitation of heat available from OFMSW aerobic process. • Another aim is to face the problem of OFMSW treatment, in particular food waste. • Energy and mass balances are presented for a case study. - Abstract: In this paper an original energy recovery method from composting is analyzed. The integrated system exploits the heat available from the aerobic biochemical process in order to support the drying of sewage sludge, using a specific solar greenhouse. The aim is to tackle the problem of organic waste treatment, with specific regard to food waste. This is done by optimizing the energy consumption of the aerobic process of composting, using the heat produced to solve a second important waste management problem such as the sewage waste treatment. Energy and mass balances are presented in a preliminary feasibility study. Referring to a composting plant with a capacity of 15,000 t/y of food waste, the estimation of the power from recovered heat for the entire plant resulted about 42 kW. The results demonstrated that the energy recoverable can cover part of the heat necessary for the treatment of sludge generated by the population served by the composting plant (in terms of food waste and green waste collection). The addition of a renewable source such as solar energy could cover the residual energy demand. The approach is presented in detail in order for it to be replicated in other case studies or at full scale applications.

  10. SLUDGE BATCH 7B GLASS VARIABILITY STUDY

    SciTech Connect (OSTI)

    Johnson, F.; Edwards, T.

    2011-10-25T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) is preparing to initiate processing Sludge Batch 7b (SB7b). In support of the upcoming processing, the Savannah River National Laboratory (SRNL) provided a recommendation to utilize Frits 418 with a 6% Na{sub 2}O addition (26 wt% Na{sub 2}O in sludge) and 702 with a 4% Na{sub 2}O addition (24 wt% Na{sub 2}O in sludge) to process SB7b. This recommendation was based on assessments of the compositional projections for SB7b available at the time from the Savannah River Remediation (SRR). To support qualification of SB7b, SRNL executed a variability study to assess the applicability of the current durability models for SB7b. The durability models were assessed over the expected composition range of SB7b, including potential caustic additions, combined with Frits 702 and 418 over a 32-40% waste loading (WL) range. Thirty four glasses were selected based on Frits 418 and 702 coupled with the sludge projections with an additional 4-6% Na{sub 2}O to reflect the potential caustic addition. Six of these glasses, based on average nominal sludge compositions including the appropriate caustic addition, were developed for both Frit 418 and Frit 702 at 32, 36 and 40% WL to provide coverage in the center of the anticipated SB7b glass region. All glasses were fabricated and characterized using chemical composition analysis, X-ray diffraction (XRD) and the Product Consistency Test (PCT). To comply with the DWPF Glass Product Control Program, a total of thirty four glasses were fabricated to assess the applicability of the current DWPF PCCS durability models. Based on the measured PCT response, all of the glasses were acceptable with respect to the Environmental Assessment (EA) benchmark glass regardless of thermal history. The NL[B] values of the SB7b variability study glasses were less than 1.99 g/L as compared to 16.695 g/L for EA. A small number of the D-optimally selected 'outer layer' extreme vertices (EV) glasses were not predictable using the current Product Composition Control System (PCCS) models for durability, but were acceptable compared to the EA glass when tested. These glasses fell outside of the lower 95% confidence band, which demonstrates conservatism in the model. A few of the glasses fell outside of the upper 95% confidence band; however, these particular glasses have normalized release values that were much lower than the values of EA and should be of no practical concern. Per the requirements of the DWPF Glass Product Control Program, the PCCS durability models have been shown to be applicable to the SB7b sludge system with a range of Na{sub 2}O concentrations blended with Frits 418 or 702. PCT results from the glasses fabricated as part of the variability study were shown to be predictable by the current DWPF PCCS models and/or acceptable with respect to the EA benchmark glass regardless of thermal history or compositional view.

  11. Biodegradation of triclosan and formation of methyl-triclosan in activated sludge under aerobic conditions

    E-Print Network [OSTI]

    Kolaei, Alireza Rezania

    Biodegradation of triclosan and formation of methyl-triclosan in activated sludge under aerobic in activated sludge from a standard activated sludge WWTP equipped with enhanced biological phosphorus removal) and anaerobic conditions rather low removal rates were determined. In a laboratory-scale activated sludge

  12. Tank 42 sludge-only process development for the Defense Waste Processing Facility (DWPF)

    SciTech Connect (OSTI)

    Lambert, D.P.

    2000-03-22T23:59:59.000Z

    Defense Waste Processing Facility (DWPF) requested the development of a sludge-only process for Tank 42 sludge since at the current processing rate, the Tank 51 sludge has been projected to be depleted as early as August 1998. Testing was completed using a non-radioactive Tank 42 sludge simulant. The testing was completed under a range of operating conditions, including worst case conditions, to develop the processing conditions for radioactive Tank 42 sludge. The existing Tank 51 sludge-only process is adequate with the exception that 10 percent additional acid is recommended during sludge receipt and adjustment tank (SRAT) processing to ensure adequate destruction of nitrite during the SRAT cycle.

  13. International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry

    E-Print Network [OSTI]

    Hasanbeigi, Ali

    2013-01-01T23:59:59.000Z

    no date) Use of biogas from anaerobic sludge digestion for2010). The biogas produced by sludge anaerobic digestion canThickener Sludge pretreatment Biogas Digester Residual

  14. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 5 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J; Cj Bannochie, C; Damon Click, D; Dan Lambert, D; Michael Stone, M; Bradley Pickenheim, B; Amanda Billings, A; Ned Bibler, N

    2008-11-10T23:59:59.000Z

    Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that underwent aluminum dissolution in late 2007 to reduce the total mass of sludge solids and aluminum being fed to the Defense Waste Processing Facility (DWPF) and Purex sludge transferred from Tank 7. Following aluminum dissolution, the addition of Tank 7 sludge and excess Pu to Tank 51, Liquid Waste Operations (LWO) provided the Savannah River National Laboratory (SRNL) a 3-L sample of Tank 51 sludge for SB5 qualification. SB5 qualification included washing the sample per LWO plans/projections (including the addition of a Pu/Be stream from H Canyon), DWPF Chemical Process Cell (CPC) simulations, waste glass fabrication (vitrification), and waste glass chemical durability evaluation. This report documents: (1) The washing (addition of water to dilute the sludge supernatant) and concentration (decanting of supernatant) of the Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF CPC simulation using the washed Tank 51 sample. This includes a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid is added to the sludge to destroy nitrite and remove mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit is added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters for the CPC processing were based on work with a non radioactive simulant. (3) Vitrification of a portion of the SME product and Product Consistency Test (PCT) evaluation of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This work is controlled by a Task Technical and Quality Assurance Plan (TTQAP) , and analyses are guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF.

  15. SLUDGE BATCH 4: MODEL BASED ASSESSMENTS OF THE FEBRUARY 2007 SLUDGE PROJECTION

    SciTech Connect (OSTI)

    Peeler, D; Tommy Edwards, T; Kevin Fox, K

    2007-03-22T23:59:59.000Z

    The Savannah River National Laboratory (SRNL) has developed, and continues to enhance, its integrated capability to evaluate the impact of proposed sludge preparation plans on the Defense Waste Processing Facility's (DWPF's) operation. One of the components of this integrated capability focuses on frit development which identifies a viable frit or frits for each sludge option being contemplated for DWPF processing. A frit is considered viable if its composition allows for economic fabrication and if, when it is combined with the sludge option under consideration, the DWPF property/composition models (the models of DWPF's Product Composition Control System (PCCS)) indicate that the combination has the potential for an operating window (a waste loading (WL) interval over which the sludge/frit glass system satisfies processability and durability constraints) that would allow DWPF to meet its goals for waste loading and canister production. This report documents the results of SRNL's efforts to identify candidate frit compositions and corresponding predicted operating windows (defined in terms of WL intervals) for the February 2007 compositional projection of Sludge Batch 4 (SB4) developed by the Liquid Waste Organization (LWO). The nominal compositional projection was used to assess projected operating windows (in terms of a waste loading interval over which all predicted properties were classified as acceptable) for various frits, evaluate the applicability of the 0.6 wt% SO{sub 4}{sup =} PCCS limit to the glass systems of interest, and determine the impact (or lack thereof) to the previous SB4 variability studies. It should be mentioned that the information from this report will be coupled with assessments of melt rate to recommend a frit for SB4 processing. The results of this paper study suggest that candidate frits are available to process the nominal SB4 composition over attractive waste loadings of interest to DWPF. Specifically, two primary candidate frits for SB4 processing, Frit 510 and Frit 418, have projected operating windows that should allow for successful processing at DWPF. While Frit 418 has been utilized at DWPF, Frit 510 is a higher B{sub 2}O{sub 3} based frit which could lead to improvements in melt rate. These frits provide relatively large operating windows and demonstrate robustness to possible sludge compositional variation while avoiding potential nepheline formation issues. In addition, assessments of SO{sub 4}{sup =} solubility indicate that the 0.6 wt% SO{sub 4}{sup =} limit in PCCS is applicable for the Frit 418 and the Frit 510 based SB4 glass systems.

  16. A new method of petroleum sludge disposal and utilization

    SciTech Connect (OSTI)

    Kanakamedala, R.D.; Islam, M.R. [South Dakota School of Mines and Technology, Rapid City, SD (United States)

    1995-12-31T23:59:59.000Z

    Disposal of the oil sludge is one of the fundamental problems of petroleum production. Increasingly stringent environmental control regulations, lack of final disposal sites, and high costs involved in disposal have resulted in limitations off oil sludge disposal options. In this study, two options for disposing the oil sludge are investigated. One option is the use of solid-liquid centrifugal separation. The second option is the use of the oil sludge as a cementing material. It is shown that the two options can be used in tandem for total remediation of the petroleum sludge. If the initial oil concentration in the sludge is high, high temperature centrifugation with biodegradable surfactant is recommended to lower the concentration to a reasonable value. The resulting solid extract was mixed with cement and silica fume and examined for cementing properties. Evaluation of compressive strengths of the mortar cubes indicates that it is possible to produce cement from the oil sludge which will satisfy the strength requirements in the ASTM standard for masonry cement.

  17. ADAPTIVE MODEL BASED CONTROL FOR WASTEWATER TREATMENT PLANTS

    E-Print Network [OSTI]

    Boucherie, Richard J.

    .j.boucherie@utwente.nl Abstract In biological wastewater treatment, nitrogen and phosphorous are removed by activated sludge in the Netherlands. An important step in the commonly applied biological wastewater treatment processADAPTIVE MODEL BASED CONTROL FOR WASTEWATER TREATMENT PLANTS Arie de Niet1 , Maartje van de Vrugt2

  18. Growth of chrysanthemums in sewage sludge amended media

    E-Print Network [OSTI]

    Schlutt, Edward Frederick

    1979-01-01T23:59:59.000Z

    1979 ABSTRACT Growth of Chrysanthemums in Sewage Sludge Amended Media. (December 1979) Edwaz d Fnedez ick Schlutt, Jr . B. S. , Texas AFN University Chairman of Advisory Committee: Dr. Everett R. Emino Chr santhemum morifolium cv. 'Bz ight Golden... porosity, total postharvest porosity, non-capillazy pore space, pre- harvest pH and postharvest pH in sewage sludge amended peat-perlite media. 40 TABLE 14. Average heavy metal content in 100% sewage sludge (ug/gm) . 42 TABLE 16. Zinc content (ug/gm...

  19. 241-Z-361 Sludge Characterization Sampling and Analysis Plan

    SciTech Connect (OSTI)

    BANNING, D.L.

    1999-08-05T23:59:59.000Z

    This sampling and analysis plan (SAP) identifies the type, quantity, and quality of data needed to support characterization of the sludge that remains in Tank 241-2-361. The procedures described in this SAP are based on the results of the 241-2-361 Sludge Characterization Data Quality Objectives (DQO) (BWHC 1999) process for the tank. The primary objectives of this project are to evaluate the contents of Tank 241-2-361 in order to resolve safety and safeguards issues and to assess alternatives for sludge removal and disposal.

  20. 241-Z-361 Sludge Characterization Sampling and Analysis Plan

    SciTech Connect (OSTI)

    BANNING, D.L.

    1999-07-29T23:59:59.000Z

    This sampling and analysis plan (SAP) identifies the type, quantity, and quality of data needed to support characterization of the sludge that remains in Tank 241-2-361. The procedures described in this SAP are based on the results of the 241-2-361 Sludge Characterization Data Quality Objectives (DQO) (BWHC 1999) process for the tank. The primary objectives of this project are to evaluate the contents of Tank 241-2-361 in order to resolve safety and safeguards issues and to assess alternatives for sludge removal and disposal.

  1. K Basin Hazard Analysis

    SciTech Connect (OSTI)

    PECH, S.H.

    2000-08-23T23:59:59.000Z

    This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Final Safety Analysis Report. This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

  2. K Basins Hazard Analysis

    SciTech Connect (OSTI)

    WEBB, R.H.

    1999-12-29T23:59:59.000Z

    This report describes the methodology used in conducting the K Basins Hazard Analysis, which provides the foundation for the K Basins Safety Analysis Report (HNF-SD-WM-SAR-062, Rev.4). This hazard analysis was performed in accordance with guidance provided by DOE-STD-3009-94, Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports and implements the requirements of DOE Order 5480.23, Nuclear Safety Analysis Report.

  3. 183-H Basin Mixed Waste Analysis and Testing Report

    SciTech Connect (OSTI)

    NONE

    1995-04-01T23:59:59.000Z

    The purpose of this sampling and analysis report is to provide data necessary to support treatment and disposal options for the low-level mixed waste from the 183-H solar evaporation ponds. In 1973, four of the 16 flocculation and sedimentation basins were designated for use as solar evaporation basins to provide waste reduction by natural evaporation of liquid chemical wastes from the 300 Area fuel fabrication facilities. The primary purpose of this effort is to gather chemical and bulk property data for the waste in the drums/boxes of sediment removed from the basin at Central Waste Complex.

  4. An integrated system to remote monitor and control anaerobic wastewater treatment plants through the internet

    E-Print Network [OSTI]

    Bernard, Olivier

    controllers that stabilise the treatment plant, meet the depollution requirements and provide a biogas quality to degrade slowly degradable substrates at high #12;concentrations, very low sludge production, low energy

  5. OVERVIEW OF TESTING TO SUPPORT PROCESSING OF SLUDGE BATCH 4 IN THE DEFENSE WASTE PROCESSING FACILITY

    SciTech Connect (OSTI)

    Herman, C

    2006-09-20T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site began processing of its third sludge batch in March 2004. To avoid a feed outage in the facility, the next sludge batch will have to be prepared and ready for transfer to the DWPF by the end of 2006. The next sludge batch, Sludge Batch 4 (SB4), will consist of a significant volume of HM-type sludge. HM-type sludge is very high in aluminum compared to the mostly Purex-type sludges that have been processed to date. The Savannah River National Laboratory (SRNL) has been working with Liquid Waste Operations to define the sludge preparation plans and to perform testing to support qualification and processing of SB4. Significant challenges have arisen during SB4 preparation and testing to include poor sludge settling behavior and lower than desired projected melt rates. An overview of the testing activities is provided.

  6. anaerobic sewage sludge: Topics by E-print Network

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

    and staff available for flue gas scrubbing test with dry lime sludge. The Ames Power Plant provided fly ash for the construction of the test embankment. iii Disclaimer "The...

  7. aerobic activated sludge: Topics by E-print Network

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

    and staff available for flue gas scrubbing test with dry lime sludge. The Ames Power Plant provided fly ash for the construction of the test embankment. iii Disclaimer "The...

  8. Proper Lagoon Management to Reduce Odor and Excessive Sludge Accumulation

    E-Print Network [OSTI]

    Mukhtar, Saqib

    1999-10-19T23:59:59.000Z

    Proper management techniques to reduce odor and excessive sludge accumulation include maintaining pH and salt levels, pumping regularly, maintaining adequate bacteria levels, and designing for efficiency. Definitions of key words are boxed for easy...

  9. Rules and Regulations for Sewage Sludge Management (Rhode Island)

    Broader source: Energy.gov [DOE]

    The purpose of these rules and regulations is to ensure that sewage sludge that is treated, land applied, disposed, distributed, stockpiled or transported in the State of Rhode Island is done so in...

  10. acid tar sludges: Topics by E-print Network

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

    to my peers Jaewoo Chung, Drew Harry, Andrea Colaco, Dori Lin, and Matt 10 Composting Manure and Sludge Texas A&M University - TxSpace Summary: composting,thefinalproductgener-...

  11. Proper Lagoon Management to Reduce Odor and Excessive Sludge Accumulation 

    E-Print Network [OSTI]

    Mukhtar, Saqib

    1999-10-19T23:59:59.000Z

    Proper management techniques to reduce odor and excessive sludge accumulation include maintaining pH and salt levels, pumping regularly, maintaining adequate bacteria levels, and designing for efficiency. Definitions of key words are boxed for easy...

  12. SLUDGE HEEL REMOVAL BY ALUMINUM DISSOLUTION AT SAVANNAH RIVER SITE 12390

    SciTech Connect (OSTI)

    Keefer, M.

    2012-01-12T23:59:59.000Z

    High Level Waste (HLW) at the Savannah River Site (SRS) is currently stored in aging underground storage tanks. This waste is a complex mixture of insoluble solids, referred to as sludge, and soluble salts. Continued long-term storage of these radioactive wastes poses an environmental risk. Operations are underway to remove and disposition the waste, clean the tanks and fill with grout for permanent closure. Heel removal is the intermediate phase of the waste retrieval and tank cleaning process at SRS, which is intended to reduce the volume of waste prior to treatment with oxalic acid. The goal of heel removal is to reduce the residual amount of radioactive sludge wastes to less than 37,900 liters (10,000 gallons) of wet solids. Reducing the quantity of residual waste solids in the tank prior to acid cleaning reduces the amount of acid required and reduces the amount of excess acid that could impact ongoing waste management processes. Mechanical heel removal campaigns in Tank 12 have relied solely on the use of mixing pumps that have not been effective at reducing the volume of remaining solids. The remaining waste in Tank 12 is known to have a high aluminum concentration. Aluminum dissolution by caustic leaching was identified as a treatment step to reduce the volume of remaining solids and prepare the tank for acid cleaning. Dissolution was performed in Tank 12 over a two month period in July and August, 2011. Sample results indicated that 16,440 kg of aluminum oxide (boehmite) had been dissolved representing 60% of the starting inventory. The evolution resulted in reducing the sludge solids volume by 22,300 liters (5900 gallons), preparing the tank for chemical cleaning with oxalic acid.

  13. Temperature effects on seawater batch activated sludge systems

    E-Print Network [OSTI]

    Wigley, Henry Albert

    1972-01-01T23:59:59.000Z

    TEMPERATURE EFFECTS ON SEAMATER BATCH ACTIVATED SLUDGE SYSTEMS A Thesis by HENRY ALBERT WIGLEY, JR. Submitted to the Graduate Colleqe of Texas A&M University in partial fulfillment of the requirement for the deqree of MASTER OF SCIENCE May... 1972 Major Subject: Civil Engineerinq TEMPERATURE EFFECTS ON SEAWATER BATCH ACTIVATED SLUDGE SYSTEMS A Thesis by HENRY ALBERT WIGLEY, JR. Approved as to style and content by: C ai rman o ommi ttee Head of D partmen Member Member May 1972...

  14. Ahmet H. Aydilek, 1 Tuncer B. Edil, 1 Patrick J. Fox2 Consolidation Characteristics of Wastewater Sludge

    E-Print Network [OSTI]

    Aydilek, Ahmet

    Sludge ________________________________________________________________________ Reference: Aydilek, A. H., Edil, T. B., and Fox, P. J., "Consolidation Characteristics of Wastewater Sludge", Geotechnics of High contaminated sludge. The Madison Metropolitan Sewerage District evaluated different remediation alternatives

  15. Evolution of Extensional Basins and Basin and Range Topography...

    Open Energy Info (EERE)

    Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article: Evolution of Extensional Basins and Basin and Range Topography West of Death Valley California...

  16. Geology, exploration status of Uruguay's sedimentary basins

    SciTech Connect (OSTI)

    Goso, C.; Santa Ana, H. de (Administracion Nacional de Combustibles, Alcohol y Portland (Uruguay))

    1994-02-07T23:59:59.000Z

    This article attempts to present the geological characteristics and tectonic and sedimentary evolution of Uruguayan basins and the extent to which they have been explored. Uruguay is on the Atlantic coast of South America. The country covers about 318,000 sq km, including offshore and onshore territories corresponding to more than 65% of the various sedimentary basins. Four basins underlie the country: the Norte basin, the Santa Lucia basin, the offshore Punta del Este basin, and the offshore-onshore Pelotas-Merin basin. The Norte basin is a Paleozoic basin while the others are Mesozoic basins. Each basin has been explored to a different extent, as this paper explains.

  17. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 7A QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Billings, A.; Click, D.

    2011-07-08T23:59:59.000Z

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry (Sludge Batch 7a*) be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). Sludge Batch 7a (SB7a) is composed of portions of Tanks 4, 7, and 12; the Sludge Batch 6 heel in Tank 51; and a plutonium stream from H Canyon. SRNL received the Tank 51 qualification sample (sample ID HTF-51-10-125) following sludge additions to Tank 51. This report documents: (1) The washing (addition of water to dilute the sludge supernate) and concentration (decanting of supernate) of the SB7a - Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the washed Tank 51 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a non-radioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7a related data together in a single permanent record and to discuss the overall aspects of SB7a processing.

  18. Enclosure 2 Additional Information on K-Basins Knock-Out Pot Sludge

    E-Print Network [OSTI]

    of strainers and collection containers called Knock-Out Pots (KOP) and Settler Tanks. After cleaning canister overpacks and managed as spent nuclear fuel scrap/debris. The Knock-Out Pot strainers limited the strainer then settled out in the Knock-Out Pots. Velocity of the water limited the material collected

  19. CRAD, Engineering - Office of River Protection K Basin Sludge Waste System

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742Energy China U.S. Department ofJune 2,The BigSidingState6Report,COMMENTS ONPRGMofRev. 0) ||

  20. CRAD, Training - Office of River Protection K Basin Sludge Waste System |

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33 1112011AT&T, Inc.'sEnergy Bush HydrogenEmissions andDepartmentDepartment of Energy

  1. EFFECTIVE ENVIRONMENTAL COMPLIANCE STRATEGY FOR THE CLEANUP OF K BASINS AT HANFORD SITE WASHINGTON

    SciTech Connect (OSTI)

    AMBALAM, T.

    2004-12-01T23:59:59.000Z

    K Basins, consisting of two water-filled storage basins (KW and KE) for spent nuclear fuel (SNF), are part of the 100-K Area of the Hanford Site, along the shoreline of the Columbia River, situated approximately 40 km (25 miles) northwest of the City of Richland, Washington. The KW contained 964 metric tons of SNF in sealed canisters and the KE contained 1152 metric tons of SNF under water in open canisters. The cladding on much of the fuel was damaged allowing the fuel to corrode and degrade during storage underwater. An estimated 1,700 cubic feet of sludge, containing radionuclides and sediments, have accumulated in the KE basin. Various alternatives for removing and processing the SNF, sludge, debris and water were originally evaluated, by USDOE (DOE), in the Environmental Impact Statement (EIS) with a preferred alternative identified in the Record of Decision. The SNF, sludge, debris and water are ''hazardous substances'' under the Comprehensive, Environmental, Response, Compensation and Liability Act of 1980 (CERCLA). Leakage of radiologically contaminated water from one of the basins and subsequent detection of increased contamination in a down-gradient monitoring well helped to form the regulatory bases for cleanup action under CERCLA. The realization that actual or threatened release of hazardous substances from the waste sites and K Basins, if not addressed in a timely manner, may present an imminent and substantial endangerment to public health, welfare and environment led to action under CERCLA, with EPA as the lead regulatory agency. Clean-up of the K Basins as a CERCLA site required SNF retrieval, processing, packaging, vacuum drying and transport to a vaulted storage facility for storage, in conformance with a quality assurance program approved by the Office of Civilian Radioactive Waste Management (OCRWM). Excluding the facilities built for SNF drying and vaulted storage, the scope of CERCLA interim remedial action was limited to the removal of fuel, sludge, debris and water. At present, almost all of the spent fuel has been removed from the basins and other activities to remove sludge, debris and water are scheduled to be completed in 2007. Developing environmental documentation and obtaining regulatory approvals for a project which was initiated outside CERCLA and came under CERCLA during execution, was a significant priority to the successful completion of the SNF retrieval, transfer, drying, transport and storage of fuel, within the purview of strong conduct-of-operations culture associated with nuclear facilities. Environmental requirements promulgated in the state regulations by Washington Department of Public Health for radiation were recognized as ''applicable or relevant and appropriate.'' Effective implementation of the environmental compliance strategy in a project that transitioned to CERCLA became a significant challenge involving multiple contractors. This paper provides an overview of the development and implementation of an environmental permitting and surveillance strategy that enabled us to achieve full compliance in a challenging environment, with milestones and cost constraints, while meeting the high safety standards. The details of the strategy as to how continuous rapport with the regulators, facility operators and surveillance groups helped to avoid impacts on the clean-up schedule are discussed. Highlighted are the role of engineered controls, surveillance protocols and triggers for monitoring and reporting, and active administrative controls that were established for the control of emissions, water loss and transport of waste shipments, during the different phases of the project.

  2. Systematic Multimodeling Methodology Applied to an Activated Sludge Reactor Anca Maria Nagy,*,

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Systematic Multimodeling Methodology Applied to an Activated Sludge Reactor Model Anca Maria Nagy for analysis or control purpose. This method is applied to an activated sludge reactor model. Introduction

  3. Removal of polycyclic aromatic hydrocarbons (PAHs) from sewage sludge by anaerobic degradation

    E-Print Network [OSTI]

    Removal of polycyclic aromatic hydrocarbons (PAHs) from sewage sludge by anaerobic degradation N nature of the polyaromatic hydrocarbons (PAHs) they are mostly bound to the sludge and escape aerobic

  4. SLUDGE BATCH 4 SIMULANT FLOWSHEET STUDIES: PHASE II RESULTS

    SciTech Connect (OSTI)

    Stone, M; David Best, D

    2006-09-12T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) will transition from Sludge Batch 3 (SB3) processing to Sludge Batch 4 (SB4) processing in early fiscal year 2007. Tests were conducted using non-radioactive simulants of the expected SB4 composition to determine the impact of varying the acid stoichiometry during the Sludge Receipt and Adjustment Tank (SRAT) process. The work was conducted to meet the Technical Task Request (TTR) HLW/DWPF/TTR-2004-0031 and followed the guidelines of a Task Technical and Quality Assurance Plan (TT&QAP). The flowsheet studies are performed to evaluate the potential chemical processing issues, hydrogen generation rates, and process slurry rheological properties as a function of acid stoichiometry. Initial SB4 flowsheet studies were conducted to guide decisions during the sludge batch preparation process. These studies were conducted with the estimated SB4 composition at the time of the study. The composition has changed slightly since these studies were completed due to changes in the sludges blended to prepare SB4 and the estimated SB3 heel mass. The following TTR requirements were addressed in this testing: (1) Hydrogen and nitrous oxide generation rates as a function of acid stoichiometry; (2) Acid quantities and processing times required for mercury removal; (3) Acid quantities and processing times required for nitrite destruction; and (4) Impact of SB4 composition (in particular, oxalate, manganese, nickel, mercury, and aluminum) on DWPF processing (i.e. acid addition strategy, foaming, hydrogen generation, REDOX control, rheology, etc.).

  5. Sensitivity Analysis of Optimal Operation of an Activated Sludge Process Model for Economic Controlled Variable Selection

    E-Print Network [OSTI]

    Skogestad, Sigurd

    Sensitivity Analysis of Optimal Operation of an Activated Sludge Process Model for Economic operation conducted on an activated sludge process model based on the test-bed benchmark simulation model no. 1 (BSM1) and the activated sludge model no. 1 (ASM1). The objective is to search for a control

  6. Improving rheological sludge characterization with electrical measurements1 Dieud-Fauvel E.1

    E-Print Network [OSTI]

    1 Improving rheological sludge characterization with electrical measurements1 2 Dieudé-Fauvel E.1 to obtain information on the rheological behaviour of sewage11 sludge by performing electrical resistivity suitable for implementation in the field. The viscosity and resistivity of sludges containing17 between 4

  7. Effects of oxygen transport limitation on nitrification in the activated sludge process

    E-Print Network [OSTI]

    Stenstrom, Michael K.

    Effects of oxygen transport limitation on nitrification in the activated sludge process ABSTRACT: Apseudohomogeneous model ofthe nitrifying activated sludge process was developed to investigate the effects ofmass and autotrophic ammonia oxidation within activated sludge flocs were described by an interactive-type, multiple

  8. Total nitrogen removal in a hybrid, membrane-aerated activated sludge process

    E-Print Network [OSTI]

    Nerenberg, Robert

    Total nitrogen removal in a hybrid, membrane-aerated activated sludge process Leon S. Downing wastewater. Air-filled hollow-fiber membranes are incorporated into an activated sludge tank removal in activated sludge. ª 2008 Elsevier Ltd. All rights reserved. 1. Introduction The removal

  9. Study of two sampling procedures for the valorization of metal hydroxide sludge as pollutant trapper

    E-Print Network [OSTI]

    Boyer, Edmond

    1 Study of two sampling procedures for the valorization of metal hydroxide sludge as pollutant@emse.fr Abstract: For the valorisation of metal hydroxide sludge as adsorbent of pollutant, it is necessary to make sure that the adsorption matrix (sludge) has characteristics allowing a reproducibility

  10. Using water activity measurements to evaluate rheological consistency and structure strength of sludge

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    of sludge G. Agoda-Tandjawa, E. Dieudé-Fauvel*, R. Girault. and J.-C. Baudez Irstea, UR TSCF, Domaine des/solid matter interactions in sewage sludge has been developed, based on both rheological characteristics parameters (G' and G'') of both raw and flocculated sewage sludge at optimal dose of polymer increase

  11. Effect of Processing Mode on Trace Elements in Dewatered Sludge Products Brian K. Richards1

    E-Print Network [OSTI]

    Walter, M.Todd

    Effect of Processing Mode on Trace Elements in Dewatered Sludge Products Brian K. Richards1 *, John considering the land application of wastewater sludges. The effects of pelletization/drying, composting compared. A single day's production of dewatered anaerobically-digested sludge (Syracuse, NY) was used

  12. Impact of sludge mechanical behaviour on spatial distribution parameters obtained with centrifugal spreader

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Impact of sludge mechanical behaviour on spatial distribution parameters obtained to analyse organic spreading and opens the way to more developments. Keywords: sludge rheological behaviour a large amount of residues which are spread on agricultural fields. This process of sludge reuse is mainly

  13. A modified Activated Sludge Model No. 3 (ASM3) with two-step nitrificationedenitrification

    E-Print Network [OSTI]

    A modified Activated Sludge Model No. 3 (ASM3) with two-step nitrificationedenitrification Ilenia of the Activated Sludge Models (ASM) [Henze, M., Gujer, W., Mino, T., van Loosdrecht, M.C.M., 2000. Ac- tivated Sludge Models ASM1, ASM2, ASM2d, and ASM3. IWA Scientific and Technical Report No. 9. IWA Publishing

  14. Assessing nitrogen losses after sewage sludge spreading: A method based on simulation models and spreader

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Assessing nitrogen losses after sewage sludge spreading: A method based on simulation models performances. We define 45 sewage sludge spreading scenarios covering a wide range of situations in France. Several models are used to (i) assess nitrogen losses due to sewage sludge spreading and (ii) calculate

  15. Water Research 36 (2002) 11811192 Accuracy analysis of a respirometer for activated sludge

    E-Print Network [OSTI]

    2002-01-01T23:59:59.000Z

    Water Research 36 (2002) 1181­1192 Accuracy analysis of a respirometer for activated sludge dynamic transfer, pH, and the influence of sludge condition on ``start-up'' behaviour. It is shown to what extent Elsevier Science Ltd. All rights reserved. Keywords: Respirometry; Oxygen uptake rate; Activated sludge

  16. Enhanced integrated nonthermal treatment system study

    SciTech Connect (OSTI)

    Biagi, C.; Schwinkendorf, B.; Teheranian, B.

    1997-02-01T23:59:59.000Z

    The purpose of the Enhanced Nonthermal Treatment Systems (ENTS) study is to evaluate alternative configurations of one of the five systems evaluated in the Integrated Nonthermal Treatment Systems (INTS) study. Five alternative configurations are evaluated. Each is designed to enhance the final waste form performance by replacing grout with improved stabilization technologies, or to improve system performance by improving the destruction efficiency for organic contaminants. AU enhanced systems are alternative configurations of System NT-5, which has the following characteristics: Nonthermal System NT-5: (1) catalytic wet oxidation (CWO) to treat organic material including organic liquids, sludges, and soft (or combustible) debris, (2) thermal desorption of inorganic sludge and process residue, (3) washing of soil and inorganic debris with treatment by CWO of removed organic material, (4) metal decontamination by abrasive blasting, (5) stabilization of treated sludge, soil, debris, and untreated debris with entrained contamination in grout, and (6) stabilization of inorganic sludge, salts and secondary waste in polymer. System NT-5 was chosen because it was designed to treat combustible debris thereby minimizing the final waste form volume, and because it uses grout for primary stabilization. The enhanced nonthermal systems were studied to determine the cost and performance impact of replacing grout (a commonly used stabilization agent in the DOE complex) with improved waste stabilization methods such as vitrification and polymer.

  17. Cenozoic basin development in Hispaniola

    SciTech Connect (OSTI)

    Mann, P.; Burke, K.

    1984-04-01T23:59:59.000Z

    Four distinct generations of Cenozoic basins have developed in Hispaniola (Haiti and Dominican Republic) as a result of collisional or strike-slip interactions between the North America and Caribbean plates. First generation basins formed when the north-facing Hispaniola arc collided with the Bahama platform in the middle Eocene; because of large post-Eocene vertical movements, these basins are preserved locally in widely separated areas but contain several kilometers of arc and ophiolite-derived clastic marine sediments, probably deposited in thrust-loaded, flexure-type basins. Second generation basins, of which only one is exposed at the surface, formed during west-northwesterly strike-slip displacement of southern Cuba and northern Hispaniola relative to central Hispaniola during the middle to late Oligocene; deposition occurred along a 5-km (3-mi) wide fault-angle depression and consisted of about 2 km (1 mi) of submarine fan deposits. Third generation basins developed during post-Oligocene convergent strike-slip displacement across a restraining bend formed in central Hispaniola; the southern 2 basins are fairly symmetrical, thrust-bounded ramp valleys, and the third is an asymmetrical fault-angle basin. Fourth generation basins are pull-aparts formed during post-Miocene divergent strike-slip motion along a fault zone across southern Hispaniola. As in other Caribbean areas, good source rocks are present in all generations of basins, but suitable reservoir rocks are scarce. Proven reservoirs are late Neogene shallow marine and fluvial sandstones in third generation basins.

  18. Sludge Washing And Demonstration Of The DWPF Flowsheet In The SRNL Shielded Cells For Sludge Batch 8 Qualification

    SciTech Connect (OSTI)

    Pareizs, J. M.; Crawford, C. L.

    2013-04-26T23:59:59.000Z

    The current Waste Solidification Engineering (WSE) practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks to Tank 51. Tank 51 sludge is washed and transferred to Tank 40, the current Defense Waste Processing Facility (DWPF) feed tank. Prior to transfer of Tank 51 to Tank 40, the Savannah River National Laboratory (SRNL) typically simulates the Tank Farm and DWPF processes using a Tank 51 sample (referred to as the qualification sample). WSE requested the SRNL to perform characterization on a Sludge Batch 8 (SB8) sample and demonstrate the DWPF flowsheet in the SRNL shielded cells for SB8 as the final qualification process required prior to SB8 transfer from Tank 51 to Tank 40. A 3-L sample from Tank 51 (the SB8 qualification sample; Tank Farm sample HTF-51-12-80) was received by SRNL on September 20, 2012. The as-received sample was characterized prior to being washed. The washed material was further characterized and used as the material for the DWPF process simulation including a Sludge Receipt and Adjustment Tank (SRAT) cycle, a Slurry Mix Evaporator (SME) cycle, and glass fabrication and chemical durability measurements.

  19. SAVANNAH RIVER SITE R-REACTOR DISASSEMBLY BASIN IN-SITU DECOMMISSIONING -10499

    SciTech Connect (OSTI)

    Langton, C.; Serrato, M.; Blankenship, J.; Griffin, W.

    2010-01-04T23:59:59.000Z

    The US DOE concept for facility in-situ decommissioning (ISD) is to physically stabilize and isolate intact, structurally sound facilities that are no longer needed for their original purpose, i.e., generating (reactor facilities), processing(isotope separation facilities) or storing radioactive materials. The 105-R Disassembly Basin is the first SRS reactor facility to undergo the in-situ decommissioning (ISD) process. This ISD process complies with the 105-R Disassembly Basin project strategy as outlined in the Engineering Evaluation/Cost Analysis for the Grouting of the R-Reactor Disassembly Basin at the Savannah River Site and includes: (1) Managing residual water by solidification in-place or evaporation at another facility; (2) Filling the below grade portion of the basin with cementitious materials to physically stabilize the basin and prevent collapse of the final cap - Sludge and debris in the bottom few feet of the basin will be encapsulated between the basin floor and overlying fill material to isolate it from the environment; (3) Demolishing the above grade portion of the structure and relocating the resulting debris to another location or disposing of the debris in-place; and (4) Capping the basin area with a concrete slab which is part of an engineered cap to prevent inadvertent intrusion. The estimated total grout volume to fill the 105-R Reactor Disassembly Basin is 24,384 cubic meters or 31,894 cubic yards. Portland cement-based structural fill materials were designed and tested for the reactor ISD project, and a placement strategy for stabilizing the basin was developed. Based on structural engineering analyses and material flow considerations, maximum lift heights and differential height requirements were determined. Pertinent data and information related to the SRS 105-R Reactor Disassembly Basin in-situ decommissioning include: regulatory documentation, residual water management, area preparation activities, technology needs, fill material designs and testing, and fill placement strategy. This information is applicable to decommissioning both the 105-P and 105-R facilities. The ISD process for the entire 105-P and 105-R reactor facilities will require approximately 250,000 cubic yards (191,140 cubic meters) of grout and approximately 3,900 cubic yards (2,989 cubic meters) of structural concrete which will be placed over about an eighteen month period to meet the accelerated schedule ISD schedule. The status and lessons learned in the SRS Reactor Facility ISD process will be described.

  20. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 6 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Pickenheim, B.; Bannochie, C.; Billings, A.; Bibler, N.; Click, D.

    2010-10-01T23:59:59.000Z

    Prior to initiating a new sludge batch in the Defense Waste Processing Facility (DWPF), Savannah River National Laboratory (SRNL) is required to simulate this processing, including Chemical Process Cell (CPC) simulation, waste glass fabrication, and chemical durability testing. This report documents this simulation for the next sludge batch, Sludge Batch 6 (SB6). SB6 consists of Tank 12 material that has been transferred to Tank 51 and subjected to Low Temperature Aluminum Dissolution (LTAD), Tank 4 sludge, and H-Canyon Pu solutions. Following LTAD and the Tank 4 addition, Liquid Waste Operations (LWO) provided SRNL a 3 L sample of Tank 51 sludge for SB6 qualification. Pu solution from H Canyon was also received. SB6 qualification included washing the sample per LWO plans/projections (including the addition of Pu from H Canyon), DWPF CPC simulations, waste glass fabrication (vitrification), and waste glass characterization and chemical durability evaluation. The following are significant observations from this demonstration. Sludge settling improved slightly as the sludge was washed. SRNL recommended (and the Tank Farm implemented) one less wash based on evaluations of Tank 40 heel projections and projections of the glass composition following transfer of Tank 51 to Tank 40. Thorium was detected in significant quantities (>0.1 wt % of total solids) in the sludge. In past sludge batches, thorium has been determined by Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS), seen in small quantities, and reported with the radionuclides. As a result of the high thorium, SRNL-AD has added thorium to their suite of Inductively Coupled Plasma-Atomic Emission Spectroscopy (ICP-AES) elements. The acid stoichiometry for the DWPF Sludge Receipt and Adjustment Tank (SRAT) processing of 115%, or 1.3 mol acid per liter of SRAT receipt slurry, was adequate to accomplish some of the goals of SRAT processing: nitrite was destroyed to below 1,000 mg/kg and mercury was removed to below the DWPF target with 750 g of steam per g of mercury. However, rheological properties did not improve and were above the design basis. Hydrogen generation rates did not exceed DWPF limits during the SRAT and Slurry Mix Evaporator (SME) cycles. However, hydrogen generation during the SRAT cycle approached the DWPF limit. The glass fabricated with the Tank 51 SB6 SME product and Frit 418 was acceptable with respect to chemical durability as measured by the Product Consistency Test (PCT). The PCT response was also predictable by the current durability models of the DWPF Product Composition Control System (PCCS). It should be noted, however, that in the first attempt to make glass from the SME product, the contents of the fabrication crucible foamed over. This may be a result of the SME product's REDOX (Reduction/Oxidation - Fe{sup 2+}/{Sigma}Fe) of 0.08 (calculated from SME product analytical results). The following are recommendations drawn from this demonstration. In this demonstration, at the request of DWPF, SRNL caustic boiled the SRAT contents prior to acid addition to remove water (to increase solids concentration). During the nearly five hours of caustic boiling, 700 ppm of antifoam was required to control foaming. SRNL recommends that DWPF not caustic boil/concentrate SRAT receipt prior to acid addition until further studies can be performed to provide a better foaming control strategy or a new antifoam is developed for caustic boiling. Based on this set of runs and a recently completed demonstration with the SB6 Waste Acceptance Product Specifications (WAPS) sample, it is recommended that DWPF not add formic acid at the design addition rate of two gallons per minute for this sludge batch. A longer acid addition time appears to be helpful in allowing slower reaction of formic acid with the sludge and possibly decreases the chance of a foam over during acid addition.

  1. PILOT-SCALE TESTING OF THE SUSPENSION OF MST, CST, AND SIMULATED SLUDGE SLURRIES IN A SLUDGE TANK

    SciTech Connect (OSTI)

    Poirier, M.; Qureshi, Z.; Restivo, M.; Steeper, T.; Williams, M.; Herman, D.

    2011-08-02T23:59:59.000Z

    The Small Column Ion Exchange (SCIX) process is being developed to remove cesium, strontium, and actinides from Savannah River Site (SRS) Liquid Waste using an existing waste tank (i.e., Tank 41H) to house the process. Following strontium, actinide, and cesium removal, the concentrated solids will be transported to a sludge tank (i.e., monosodium titanate (MST)/sludge solids to Tank 42H or Tank 51H and crystalline silicotitanate (CST) to Tank 40H) for eventual transfer to the Defense Waste Processing Facility (DWPF). Savannah River National Laboratory (SRNL) is conducting pilot-scale mixing tests to determine the pump requirements for mixing MST, CST, and simulated sludge. The purpose of this pilot scale testing is to determine the pump requirements for mixing MST and CST with sludge in a sludge tank and to determine whether segregation of particles occurs during settling. Tank 40H and Tank 51H have four Quad Volute pumps; Tank 42H has four standard pumps. The pilot-scale tank is a 1/10.85 linear scaled model of Tank 40H. The tank diameter, tank liquid level, pump nozzle diameter, pump elevation, and cooling coil diameter are all 1/10.85 of their dimensions in Tank 40H. The pump locations correspond to the current locations in Tank 40H (Risers B2, H, B6, and G). The pumps are pilot-scale Quad Volute pumps. Additional settling tests were conducted in a 30 foot tall, 4 inch inner diameter clear column to investigate segregation of MST, CST, and simulated sludge particles during settling.

  2. GLYCOLIC-FORMIC ACID FLOWSHEET SLUDGE MATRIX STUDY

    SciTech Connect (OSTI)

    Lambert, D.; Koopman, D.

    2011-06-30T23:59:59.000Z

    Testing was completed to demonstrate the viability of the newly developed glycolic acid/formic acid flowsheet on processing in the Defense Waste Processing Facility's (DWPF) Chemical Process Cell (CPC). The Savannah River National Laboratory (SRNL) initiated a sludge matrix study to evaluate the impact of changing insoluble solid composition on the processing characteristics of slurries in DWPF. Four sludge simulants were prepared to cover two compositional ranges in the waste. The first was high iron/low aluminum versus low iron/high aluminum (referred to as HiFe or LoFe in this report). The second was high calcium-manganese/low nickel, chromium, and magnesium versus low calcium-manganese/high nickel, chromium, and magnesium (referred to as HiMn or LoMn in this report). These two options can be combined to form four distinct sludge compositions. The sludge matrix study called for testing each of these four simulants near the minimum acid required for nitrite destruction (100% acid stoichiometry) and at a second acid level that produced significant hydrogen by noble metal catalyzed decomposition of formic acid (150% acid stoichiometry). Four simulants were prepared based on the four possible combinations of the Al/Fe and Mn-Ca/Mg-Ni-Cr options. Preliminary simulant preparation work has already been documented. The four simulants were used for high and low acid testing. Eight planned experiments (GF26 to GF33) were completed to demonstrate the viability of the glycolic-formic flowsheet. Composition and physical property measurements were made on the SRAT product. Composition measurements were made on the condensate from the Mercury Water Wash Tank (MWWT), Formic Acid Vent Condenser (FAVC), ammonia scrubber and on SRAT samples pulled throughout the SRAT cycle. Updated values for formate loss and nitrite-tonitrate conversion were found that can be used in the acid calculations for future sludge matrix process simulations with the glycolic acid/formic acid flowsheet. Preliminary results of the initial testing indicate: (1) Hydrogen generation rate was very low throughout all SRAT cycles. (2) The mercury concentration of the SRAT product was below the 0.8 wt% limit in all runs. (3) Nitrite in the SRAT product was <100 mg/kg for all runs. (4) Foaminess was not an issue using the nominal antifoam addition strategy in these tests. (5) The high aluminum sludges (LoFe, HM type sludges) were much more viscous than the Hi Fe sludges. At 100% acid stoichiometry, the SRAT products from the high aluminum sludges were very viscous but at 150% acid stoichiometry, the SRAT products from the high aluminum sludges were very thin. This makes the glycolic acid/formic acid flowsheet an improvement for processing more viscous sludges. (6) The pH of the SRAT products was from 2.7-3.1 for the 150% acid stoichiometry runs and 5.1-6.1 for the 100% acid stoichiometry runs, significantly lower than is typical of the baseline nitric acid/formic acid flowsheet.

  3. Rappahannock River Basin Commission (Virginia)

    Broader source: Energy.gov [DOE]

    The Rappahannock River Basin Commission is an independent local entity tasked with providing guidance for the stewardship and enhancement of the water quality and natural resources of the...

  4. Susquehanna River Basin Compact (Maryland)

    Broader source: Energy.gov [DOE]

    This legislation enables the state's entrance into the Susquehanna River Basin Compact, which provides for the conservation, development, and administration of the water resources of the...

  5. Novel Nanoscale Materials Reduce Electricity Needed for Sludge

    E-Print Network [OSTI]

    This project researches the use of nanoscale materials (a broadly defined set of substances that haveNovel Nanoscale Materials Reduce Electricity Needed for Sludge Dewatering Industrial process, requiring up to 6000 kilowatt hours/year per million gallons per day. Project Description

  6. Example of latest techniques for bottom-sludge dredging

    SciTech Connect (OSTI)

    Hamasuna, J.

    1992-03-01T23:59:59.000Z

    Recently in Japan, the biggest problems of the bottom sludge dredging are lack of enough room for dumping areas and preventing water contamination during dredging in terms of environmental aspects. The new dredging system introduced at this time has been developed for the above purposes.

  7. SLUDGE BATCH 7 PREPARATION TANK 4 AND 12 CHARACTERIZATION

    SciTech Connect (OSTI)

    Bannochie, C.; Click, D.; Pareizs, J.

    2010-05-21T23:59:59.000Z

    Samples of PUREX sludge from Tank 4 and HM sludge from Tank 12 were characterized in preparation for Sludge Batch 7 (SB7) formulation in Tank 51. SRNL analyses on Tank 4 and Tank 12 were requested in separate Technical Assistance Requests (TAR). The Tank 4 samples were pulled on January 19, 2010 following slurry operations by F-Tank Farm. The Tank 12 samples were pulled on February 9, 2010 following slurry operations by H-Tank Farm. At the Savannah River National Laboratory (SRNL), two 200 mL dip samples of Tank 4 and two 200 mL dip samples of Tank 12 were received in the SRNL Shielded Cells. Each tank's samples were composited into clean 500 mL polyethylene storage bottles and weighed. The composited Tank 4 sample was 428.27 g and the composited Tank 12 sample was 502.15 g. As expected there are distinct compositional differences between Tank 4 and Tank 12 sludges. The Tank 12 slurry is much higher in Al, Hg, Mn, and Th, and much lower in Fe, Ni, S, and U than the Tank 4 slurry. The Tank 4 sludge definitely makes the more significant contribution of S to any sludge batch blend. This S, like that observed during SB6 washing, is best monitored by looking at the total S measured by digesting the sample and analyzing by inductively coupled plasma - atomic emission spectroscopy (ICPAES). Alternatively, one can measure the soluble S by ICP-AES and adjust the value upward by approximately 15% to have a pretty good estimate of the total S in the slurry. Soluble sulfate measurements by ion chromatography (IC) will be biased considerably lower than the actual total S, the difference being due to the non-sulfate soluble S and the undissolved S. Tank 12 sludge is enriched in U-235, and hence samples transferred into SRNL from the Tank Farm will need to be placed on the reportable special nuclear material inventory and tracked for total U per SRNL procedure requirements.

  8. FLOWSHEET FOR ALUMINUM REMOVAL FROM SLUDGE BATCH 6

    SciTech Connect (OSTI)

    Pike, J; Jeffrey Gillam, J

    2008-12-17T23:59:59.000Z

    Samples of Tank 12 sludge slurry show a substantially larger fraction of aluminum than originally identified in sludge batch planning. The Liquid Waste Organization (LWO) plans to formulate Sludge Batch 6 (SB6) with about one half of the sludge slurry in Tank 12 and one half of the sludge slurry in Tank 4. LWO identified aluminum dissolution as a method to mitigate the effect of having about 50% more solids in High Level Waste (HLW) sludge than previously planned. Previous aluminum dissolution performed in a HLW tank in 1982 was performed at approximately 85 C for 5 days and dissolved nearly 80% of the aluminum in the sludge slurry. In 2008, LWO successfully dissolved 64% of the aluminum at approximately 60 C in 46 days with minimal tank modifications and using only slurry pumps as a heat source. This report establishes the technical basis and flowsheet for performing an aluminum removal process in Tank 51 for SB6 that incorporates the lessons learned from previous aluminum dissolution evolutions. For SB6, aluminum dissolution process temperature will be held at a minimum of 65 C for at least 24 days, but as long as practical or until as much as 80% of the aluminum is dissolved. As planned, an aluminum removal process can reduce the aluminum in SB6 from about 84,500 kg to as little as 17,900 kg with a corresponding reduction of total insoluble solids in the batch from 246,000 kg to 131,000 kg. The extent of the reduction may be limited by the time available to maintain Tank 51 at dissolution temperature. The range of dissolution in four weeks based on the known variability in dissolution kinetics can range from 44 to more than 80%. At 44% of the aluminum dissolved, the mass reduction is approximately 1/2 of the mass noted above, i.e., 33,300 kg of aluminum instead of 66,600 kg. Planning to reach 80% of the aluminum dissolved should allow a maximum of 81 days for dissolution and reduce the allowance if test data shows faster kinetics. 47,800 kg of the dissolved aluminum will be stored in Tank 8 and 21,000 kg will be stored in saltcake via evaporation. Up to 77% of the total aluminum planned for SB6 may be removed via aluminum dissolution. Storage of the aluminum-laden supernate in Tank 8 will require routine evaluation of the free hydroxide concentration in order to maintain aluminum in solution. Periodic evaluation will be established on concurrent frequency with corrosion program samples as previously established for aluminum-laden supernate from SB5 that is stored in Tank 11.

  9. HIGH LEVEL WASTE SLUDGE BATCH 4 VARIABILITY STUDY

    SciTech Connect (OSTI)

    Fox, K; Tommy Edwards, T; David Peeler, D; David Best, D; Irene Reamer, I; Phyllis Workman, P

    2006-10-02T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) is preparing for vitrification of High Level Waste (HLW) Sludge Batch 4 (SB4) in early FY2007. To support this process, the Savannah River National Laboratory (SRNL) has provided a recommendation to utilize Frit 503 for vitrifying this sludge batch, based on the composition projection provided by the Liquid Waste Organization on June 22, 2006. Frit 418 was also recommended for possible use during the transition from SB3 to SB4. A critical step in the SB4 qualification process is to demonstrate the applicability of the durability models, which are used as part of the DWPF's process control strategy, to the glass system of interest via a variability study. A variability study is an experimentally-driven assessment of the predictability and acceptability of the quality of the vitrified waste product that is anticipated from the processing of a sludge batch. At the DWPF, the durability of the vitrified waste product is not directly measured. Instead, the durability is predicted using a set of models that relate the Product Consistency Test (PCT) response of a glass to the chemical composition of that glass. In addition, a glass sample is taken during the processing of that sludge batch, the sample is transmitted to SRNL, and the durability is measured to confirm acceptance. The objective of a variability study is to demonstrate that these models are applicable to the glass composition region anticipated during the processing of the sludge batch - in this case the Frit 503 - SB4 compositional region. The success of this demonstration allows the DWPF to confidently rely on the predictions of the durability/composition models as they are used in the control of the DWPF process.

  10. USE OF AN EQUILIBRIUM MODEL TO FORECAST DISSOLUTION EFFECTIVENESS, SAFETY IMPACTS, AND DOWNSTREAM PROCESSABILITY FROM OXALIC ACID AIDED SLUDGE REMOVAL IN SAVANNAH RIVER SITE HIGH LEVEL WASTE TANKS 1-15

    SciTech Connect (OSTI)

    KETUSKY, EDWARD

    2005-10-31T23:59:59.000Z

    This thesis details a graduate research effort written to fulfill the Magister of Technologiae in Chemical Engineering requirements at the University of South Africa. The research evaluates the ability of equilibrium based software to forecast dissolution, evaluate safety impacts, and determine downstream processability changes associated with using oxalic acid solutions to dissolve sludge heels in Savannah River Site High Level Waste (HLW) Tanks 1-15. First, a dissolution model is constructed and validated. Coupled with a model, a material balance determines the fate of hypothetical worst-case sludge in the treatment and neutralization tanks during each chemical adjustment. Although sludge is dissolved, after neutralization more is created within HLW. An energy balance determines overpressurization and overheating to be unlikely. Corrosion induced hydrogen may overwhelm the purge ventilation. Limiting the heel volume treated/acid added and processing the solids through vitrification is preferred and should not significantly increase the number of glass canisters.

  11. Advanced Chemistry Basins Model

    SciTech Connect (OSTI)

    Blanco, Mario; Cathles, Lawrence; Manhardt, Paul; Meulbroek, Peter; Tang, Yongchun

    2003-02-13T23:59:59.000Z

    The objective of this project is to: (1) Develop a database of additional and better maturity indicators for paleo-heat flow calibration; (2) Develop maturation models capable of predicting the chemical composition of hydrocarbons produced by a specific kerogen as a function of maturity, heating rate, etc.; assemble a compositional kinetic database of representative kerogens; (3) Develop a 4 phase equation of state-flash model that can define the physical properties (viscosity, density, etc.) of the products of kerogen maturation, and phase transitions that occur along secondary migration pathways; (4) Build a conventional basin model and incorporate new maturity indicators and data bases in a user-friendly way; (5) Develop an algorithm which combines the volume change and viscosities of the compositional maturation model to predict the chemistry of the hydrocarbons that will be expelled from the kerogen to the secondary migration pathways; (6) Develop an algorithm that predicts the flow of hydrocarbons along secondary migration pathways, accounts for mixing of miscible hydrocarbon components along the pathway, and calculates the phase fractionation that will occur as the hydrocarbons move upward down the geothermal and fluid pressure gradients in the basin; and (7) Integrate the above components into a functional model implemented on a PC or low cost workstation.

  12. Effect of Cd-Enriched Sewage Sludge on Plant Growth, Nutrients and Heavy Metals Concentrations in the Soil–Plant System

    E-Print Network [OSTI]

    Rusan, Munir Mohammad; Athamneh, Bayan Mahmoud

    2009-01-01T23:59:59.000Z

    from waste-activated sludge, Soil Sci. Soc. Am. J, 60:505-utilization of sewage sludge. A twenty-year study atCd-enriched sewage sludge (SS) and diammonium phosphate (

  13. RESERVES IN WESTERN BASINS PART IV: WIND RIVER BASIN

    SciTech Connect (OSTI)

    Robert Caldwell

    1998-04-01T23:59:59.000Z

    Vast quantities of natural gas are entrapped within various tight formations in the Rocky Mountain area. This report seeks to quantify what proportion of that resource can be considered recoverable under today's technological and economic conditions and discusses factors controlling recovery. The ultimate goal of this project is to encourage development of tight gas reserves by industry through reducing the technical and economic risks of locating, drilling and completing commercial tight gas wells. This report is the fourth in a series and focuses on the Wind River Basin located in west central Wyoming. The first three reports presented analyses of the tight gas reserves and resources in the Greater Green River Basin (Scotia, 1993), Piceance Basin (Scotia, 1995) and the Uinta Basin (Scotia, 1995). Since each report is a stand-alone document, duplication of language will exist where common aspects are discussed. This study, and the previous three, describe basin-centered gas deposits (Masters, 1979) which contain vast quantities of natural gas entrapped in low permeability (tight), overpressured sandstones occupying a central basin location. Such deposits are generally continuous and are not conventionally trapped by a structural or stratigraphic seal. Rather, the tight character of the reservoirs prevents rapid migration of the gas, and where rates of gas generation exceed rates of escape, an overpressured basin-centered gas deposit results (Spencer, 1987). Since the temperature is a primary controlling factor for the onset and rate of gas generation, these deposits exist in the deeper, central parts of a basin where temperatures generally exceed 200 F and drill depths exceed 8,000 feet. The abbreviation OPT (overpressured tight) is used when referring to sandstone reservoirs that comprise the basin-centered gas deposit. Because the gas resources trapped in this setting are so large, they represent an important source of future gas supply, prompting studies to understand and quantify the resource itself and to develop technologies that will permit commercial exploitation. This study is a contribution to that process.

  14. Waste Acceptance Radionuclides To Be Reported In Tank 51 Sludge Only Glass

    SciTech Connect (OSTI)

    Hyder, M. Lee

    1995-12-12T23:59:59.000Z

    The first high level waste glass to be generated at SRS will incorporate sludge from Tank 51. This sludge has been characterized by Bibler et al., who measured and estimated the radioisotope composition of the glass that might be derived from this sludge. In this report this characterization is used to determine which isotopes must be quantified to meet the legal criteria for repository placement.

  15. Reactance simulation for the defects in steam generator tube with outside ferrite sludge

    SciTech Connect (OSTI)

    Ryu, Kwon-sang; Kima, Yong-il [Division of Metrology for Quality Life, KRISS, Daejeon, 305-600 (Korea, Republic of); Son, Derac [Department of Physics, Hannam University, Daejeon, 336-840 (Korea, Republic of); Park, Duck-gun [Nuclear Material Technique Development Team, KAERI, Daejeon, 305-353 (Korea, Republic of); Jung, Jae-kap [Division of Physical Metrology, KRISS, Daejeon, 305-600 (Korea, Republic of)

    2009-04-01T23:59:59.000Z

    A magnetic sludge is partly produced around the tube sheet outside a steam generator due to stress and heat. The sludge with magnetite is one of the important factors affecting eddy current signals. It causes trouble for the safety of the steam generator tubes and is difficult to detect by conventional eddy current methods. A new type of probe is needed to detect the signals for the magnetic sludge. We designed a new U-type yoke which has two kinds of coils--a magnetizing coil and the other a detecting coil--and we simulated the signal induced by the ferromagnetic sludge in the Inconel 600 tube.

  16. A study of acid sludge obtained in the refining of petroleum

    E-Print Network [OSTI]

    Johnson, Albert Sidney

    1923-01-01T23:59:59.000Z

    fo. petroleum Refin- eries {S l yellow colo of petroleum after ref in&ng m:y be due to impurities in the sulphurio &icid used ~ Since it is known that nitro. ?en trioxide, nitro en pentoxide, and selenium dioxide will cayuse discolor ~tion... of the sludge with ocustio soda o soda ash, &nd the "mixing" of the neutrul- ised sludge eith fuel oil. Much i&ttentlon h s been:i eu t:& the recover" of tho sludge acid, i. nd but little cr no uttention to thc study of the orgunic c&ntent of the caid sludge...

  17. Examination of the Potential for Formation of Energetic Compounds in Dry Sludge

    SciTech Connect (OSTI)

    Barnes, M.J.

    1998-12-17T23:59:59.000Z

    This report details initial results from an investigation of the potential formation and fate of energetic compounds in Savannah River Site sludge.

  18. acidic oily sludge-contaminated: Topics by E-print Network

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

    Last Page Topic Index 1 ORIGINAL PAPER Bioremediation of oily sludge-contaminated soil Environmental Management and Restoration Websites Summary: accidents, and storage tank...

  19. Removal of fluoride from aqueous solution by using alum sludge

    SciTech Connect (OSTI)

    Sujana, M.G.; Thakur, R.S.; Rao, S.B. [CSIR, Bhubaneswar (India). Regional Research Lab.] [CSIR, Bhubaneswar (India). Regional Research Lab.

    1998-10-01T23:59:59.000Z

    The ability of treated alum sludge to remove fluoride from aqueous solution has been investigated. The studies were carried out as functions of contact time, concentration of adsorbent and adsorbate, temperature, pH, and effect of concentrations of other anions. The data indicate that treated alum sludge surface sites are heterogeneous in nature and that fits into a heterogeneous site binding model. The optimum pH for complete removal of fluoride from aqueous solution was found to be 6. The rate of adsorption was rapid during the initial 5 minutes, and equilibrium was attained within 240 minutes. The adsorption followed first-order rate kinetics. The present system followed the Langmuir adsorption isotherm model. The loading factor (i.e., the milligram of fluoride adsorbed per gram of alum sludge) increased with initial fluoride concentration, whereas a negative trend was observed with increasing temperature. The influence of addition of anions on fluoride removal depends on the relative affinity of the anions for the surface and the relative concentrations of the anions.

  20. Essays on Environmental and Resource Economics

    E-Print Network [OSTI]

    Toledo, Chantal Nathalie

    2013-01-01T23:59:59.000Z

    of variable “activated sludge treatment” in 2006: 0.003.income (soles) activated sludge treatment Table 2.10: Wateractivated septic septic sludge sludge sludge tank tank

  1. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect (OSTI)

    PACKER, M.J.

    1999-11-04T23:59:59.000Z

    Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  2. 488-D Ash Basin Vegetative Cover Treatibility Study

    SciTech Connect (OSTI)

    Barton, Christopher; Marx, Don; Blake, John; Adriano, Domy; Koo, Bon-Jun; Czapka, Stephen

    2003-01-01T23:59:59.000Z

    The 488-D Ash Basin is an unlined containment basin that received ash and coal reject material from the operation of a powerhouse at the USDOE's Savannah River Site, SC. They pyretic nature of the coal rejects has resulted in the formation of acidic drainage (AD), which has contributed to groundwater deterioration and threatens biota in down gradient wetlands. Establishment of a vegetative cover was examined as a remedial alternative for reducing AD generation within this system by enhanced utilization of rainwater and subsequent non-point source water pollution control. The low nutrient content, high acidity, and high salinity of the basin material, however, was deleterious to plant survivability. As such, studies to identify suitable plant species and potential adaptations, and pretreatment techniques in the form of amendments, tilling, and/or chemical stabilization were needed. A randomized block design consisting of three subsurface treatments (blocks) and five duplicated surface amendments (treatments) was developed. One hundred inoculated pine trees were planted on each plot. Herbaceous species were also planted on half of the plots in duplicated 1-m2 beds. After two growing seasons, deep ripping, subsurface amendments and surface covers were shown to be essential for the successful establishment of vegetation on the basin. This is the final report of the study.

  3. Rivanna River Basin Commission (Virginia)

    Broader source: Energy.gov [DOE]

    The Rivanna River Basin Commission is an independent local entity tasked with providing guidance for the stewardship and enhancement of the water quality and natural resources of the Rivanna River...

  4. TANK 12 SLUDGE CHARACTERIZATION AND ALUMINUM DISSOLUTION DEMONSTRATION

    SciTech Connect (OSTI)

    Reboul, S; Michael Hay, M; Kristine Zeigler, K; Michael Stone, M

    2009-03-25T23:59:59.000Z

    A 3-L sludge slurry sample from Tank 12 was characterized and then processed through an aluminum dissolution demonstration. The dominant constituent of the sludge was found to be aluminum in the form of boehmite. The iron content was minor, about one-tenth that of the aluminum. The salt content of the supernatant was relatively high, with a sodium concentration of {approx}7 M. Due to these characteristics, the yield stress and plastic viscosity of the unprocessed slurry were relatively high (19 Pa and 27 cP), and the settling rate of the sludge was relatively low ({approx}20% settling over a two and a half week period). Prior to performing aluminum dissolution, plutonium and gadolinium were added to the slurry to simulate receipt of plutonium waste from H-Canyon. Aluminum dissolution was performed over a 26 day period at a temperature of 65 C. Approximately 60% of the insoluble aluminum dissolved during the demonstration, with the rate of dissolution slowing significantly by the end of the demonstration period. In contrast, approximately 20% of the plutonium and less than 1% of the gadolinium partitioned to the liquid phase. However, about a third of the liquid phase plutonium became solubilized prior to the dissolution period, when the H-Canyon plutonium/gadolinium simulant was added to the Tank 12 slurry. Quantification of iron dissolution was less clear, but appeared to be on the order of 1% based on the majority of data (a minor portion of the data suggested iron dissolution could be as high as 10%). The yield stress of the post-dissolution slurry (2.5 Pa) was an order of magnitude lower than the initial slurry, due most likely to the reduced insoluble solids content caused by aluminum dissolution. In contrast, the plastic viscosity remained unchanged (27 cP). The settling rate of the post-dissolution slurry was higher than the initial slurry, but still relatively low compared to settling of typical high iron content/low salt content sludges. Approximately 40% of the post-dissolution sludge settled over a three week period. The corresponding volume of supernatant that was decanted from the waste was approximately 35% of the total waste volume. The decanted supernatant contained approximately one-third of the dissolved aluminum and exhibited a mild greenish-grey hue.

  5. Tank 12 Sludge Characterization and Aluminum Dissolution Demonstration

    SciTech Connect (OSTI)

    Reboul, S.; Hay, M.; Zeigler, K; Stone, M.

    2010-05-05T23:59:59.000Z

    A 3-L sludge slurry sample from Tank 12 was characterized and then processed through an aluminum dissolution demonstration. The dominant constituent of the sludge was found to be aluminum in the form of boehmite. The iron content was minor, about one-tenth that of the aluminum. The salt content of the supernatant was relatively high, with a sodium concentration of {approx}7 M. Due to these characteristics, the yield stress and plastic viscosity of the unprocessed slurry were relatively high (19 Pa and 27 cP), and the settling rate of the sludge was relatively low ({approx}20% settling over a two and a half week period). Prior to performing aluminum dissolution, plutonium and gadolinium were added to the slurry to simulate receipt of plutonium waste from H-Canyon. Aluminum dissolution was performed over a 26 day period at a temperature of 65 C. Approximately 60% of the insoluble aluminum dissolved during the demonstration, with the rate of dissolution slowing significantly by the end of the demonstration period. In contrast, approximately 20% of the plutonium and less than 1% of the gadolinium partitioned to the liquid phase. However, about a third of the liquid phase plutonium became solubilized prior to the dissolution period, when the H-Canyon plutonium/gadolinium simulant was added to the Tank 12 slurry. Quantification of iron dissolution was less clear, but appeared to be on the order of 1% based on the majority of data (a minor portion of the data suggested iron dissolution could be as high as 10%). The yield stress of the post-dissolution slurry (2.5 Pa) was an order of magnitude lower than the initial slurry, due most likely to the reduced insoluble solids content caused by aluminum dissolution. In contrast, the plastic viscosity remained unchanged (27 cP). The settling rate of the post-dissolution slurry was higher than the initial slurry, but still relatively low compared to settling of typical high iron content/low salt content sludges. Approximately 40% of the post-dissolution sludge settled over a three week period. The corresponding volume of supernatant that was decanted from the waste was approximately 35% of the total waste volume. The decanted supernatant contained approximately one-third of the dissolved aluminum and exhibited a mild greenish-grey hue.

  6. Acceptance testing report of Eductor System to be installed in the 105 K Basins

    SciTech Connect (OSTI)

    Packer, M.J.

    1996-04-25T23:59:59.000Z

    The Spent Nuclear Fuel (SNF) Project Engineering Support group cold-tested the Eductor System a 15 horsepower multi-stage centrifugal pump manufactured by the Grunfos Corporation with the housing manufactured and sold with the pump by the Tri-Nuclear Corporation and a 3-inch diameter water jet eductor manufactured by the Fox Valve Corporation. The Eductor System was tested to gather and document information to optimize sludge retrieval operations for use in the 105 K Basins. The cold-testing took place during February 12 through February 29, 1996 in the 305 Cold Test Facility basin located in the 300 area. The pump, utilized in conjunction with the eductor, makes up the core of the Eductor System. The pumping unit consists of a 15 hp stainless steel multi-stage centrifugal Grunfos pump which is seated in a stainless steel fabricated housing. Two baskets or filter elements make up part of the housing on the suction side of the pump. The pump can be used independent of the housing but the housing has two identified purposes. The first use is to stabilize the centrifugal pump and give the pneumatic valves and pump discharge piping a solid platform so the Eductor System can be more easily mobilized within the basin as one unit. The second use for the housing presents the option to utilize the suction-side filters for capturing larger fuel pieces after the smaller fines have been removed.

  7. Integrated nonthermal treatment system study

    SciTech Connect (OSTI)

    Biagi, C.; Bahar, D.; Teheranian, B.; Vetromile, J. [Morrison Knudsen Corp. (United States); Quapp, W.J. [Nuclear Metals (United States); Bechtold, T.; Brown, B.; Schwinkendorf, W. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States); Swartz, G. [Swartz and Associates (United States)

    1997-01-01T23:59:59.000Z

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

  8. Localised mobilisation of metals, as measured by diffusive gradients in thin-films, in soil historically treated with sewage sludge

    E-Print Network [OSTI]

    Ma, Lena

    historically treated with sewage sludge Jun Luo a,c , Hao Zhang a, , William Davison a , Ronald G. McLaren b online 11 September 2012 Keywords: Trace metals Soil Sewage sludge Mn oxide Diffusive gradients in thin was investigated in a sandy loam soil historically treated with sewage sludge. After deployment of two DGT

  9. Impact on sludge inventory and control strategies using the Benchmark Simulation Model No. 1 with the Brger-Diehl

    E-Print Network [OSTI]

    Bürger, Raimund

    Impact on sludge inventory and control strategies using the Benchmark Simulation Model No. 1 concentration predictions, plant sludge inventory and mixed liquor suspended solids based control actions-Diehl model allows for more realistic predictions of the underflow sludge concentration which is essential

  10. Biohydrogen production from oil palm frond juice and sewage sludge by a metabolically engineered

    E-Print Network [OSTI]

    Wood, Thomas K.

    Biohydrogen production from oil palm frond juice and sewage sludge by a metabolically engineered from oil palm frond (OPF) juice and sewage sludge as substrates. Substrate improvement was accomplished Accepted 16 June 2013 Available online 13 July 2013 Keywords: Biohydrogen Escherichia coli Oil palm frond

  11. Fate of Radionuclides in Wastewater Treatment Plants

    E-Print Network [OSTI]

    Shabani Samgh Abadi, Farzaneh

    2013-01-01T23:59:59.000Z

    Used Radionuclides in Sewage Sludge. Water, Air, and Soilin Ground Level Air and Sewage Sludge. Water, Air, and SoilMeans of Measurements on Sewage Sludge. Water, Air, and Soil

  12. Resuspension and Settling of Monosodium Titanate and Sludge in Supernate Simulate for the Savannah River Site

    SciTech Connect (OSTI)

    Taylor, P.A.; Mattus, C.H.

    1999-10-01T23:59:59.000Z

    The Savannah River Site (SRS) is testing several methods for their effectiveness in removing the major radionuclides from the supernate solutions that are stored in the high-level waste tanks at the site. One option is to mix the tank contents (sludge and supernate), in situ, with monosodium titanate (MST) powder to remove 90Sr and transuranics. The sludge and MST would be allowed to settle, and thet reated supernate would then be decanted. The sludge and MST would need to be resuspended later so that the solids could be pumped to the Defense Waste Processing Facility for vitrification. Small-scale tests evaluated the effect of various storage conditions on the rheological properties of the sludge/MST slurry. Laboratory-scale and pilot-scale tests were conducted to determine the mixing requirements for resuspending slurries of sludge simulant and MST, following settleing periods of various lengths.`

  13. REPORTABLE RADIONUCLIDES IN DWPF SLUDGE BATCH 7A (MACROBATCH 8)

    SciTech Connect (OSTI)

    Reboul, S.; Diprete, D.; Click, D.; Bannochie, C.

    2011-12-20T23:59:59.000Z

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that the waste producer 'shall report the curie inventory of radionuclides that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115.' As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type all radionuclides that have half-lives longer than 10 years and contribute greater than 0.01 percent of the total curie inventory from the time of production through the 1100 year period from 2015 through 3115. The initial list of radionuclides to be reported is based on the design-basis glass identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report. However, it is required that the list be expanded if other radionuclides with half-lives greater than 10 years are identified that meet the 'greater than 0.01% of the curie inventory' criterion. Specification 1.6 of the WAPS, International Atomic Energy Agency Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, and U-238; and Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete list of reportable radionuclides must also include these sets of U and Pu isotopes - and the U and Pu isotopic mass distributions must be identified. The DWPF receives HLW sludge slurry from Savannah River Site (SRS) Tank 40. For Sludge Batch 7a (SB7a), the waste in Tank 40 contained a blend of the heel from Sludge Batch 6 (SB6) and the Sludge Batch 7 (SB7) material transferred to Tank 40 from Tank 51. This sludge blend is also referred to as Macrobatch 8. Laboratory analyses of a Tank 40 sludge sample were performed to quantify the concentrations of pertinent radionuclides in the SB7a waste. Subsequently, radiological decay and in-growth were calculated over the time period from 2015 to 3115. This provided a basis for characterizing the radionuclide content of SB7a over time and for identifying the 'reportable radionuclides.' Details of the characterization methodology and the analytical results are the focus of this report. This work was performed at the request of the Waste Solidification Engineering Department of Savannah River Remediation, initiated via Technical Task Request (TTR) HLW-DWPF-TTR-2010-0031. A minor revision in the reporting requirements was requested via a subsequent email communication. The work was conducted in accordance with the protocols identified in Task Technical and Quality Assurance Plan SRNL-RP-2010-01218 and Analytical Study Plan SRNL-RP-2010-01219. All of the raw data related to this scope have been recorded in laboratory notebook SRNL-NB-2011-00061. The overall goal of this task was to characterize the radionuclide content of the SB7a waste sufficiently to meet the WAPS and DWPF reporting requirements. The specific objectives were: (1) Quantify the current concentrations of all radionuclides impacting (or potentially-impacting) the total curie content between calendar years 2011 and 3115. Also quantify the current concentrations of other radionuclides specifically requested in the TTR or required by the WAPS. (2) Calculate future concentrations of decayed and in-grown radionuclides impacting the total curie content between calendar years 2015 and 3115; (3) Identify as 'reportable' all radionuclides contributing {ge} 0.01% of the total curie content from 2015 to 3115 and having half-lives {ge} 10 years.

  14. Water washes and caustic leaches of sludge from Hanford Tank S-101 and water washes of sludge from Hanford Tank C-103

    SciTech Connect (OSTI)

    Hunt, R.D.; Collins, J.L.; Chase, C.W.

    1998-07-01T23:59:59.000Z

    In 1993, the Department of Energy (DOE) selected the enhanced sludge washing (ESW) process as the baseline for pretreatment of Hanford tank sludges. The ESW process uses a series of water washes and caustic leaches to separate nonradioactive components such as aluminum, chromium, and phosphate from the high-level waste sludges. If the ESW process is successful, the volume of immobilized high-level waste will be significantly reduced. The tests on the sludge from Hanford Tank S-101 focused on the effects of process variables such as sodium hydroxide concentration (1 and 3 M), temperature (70 and 95 C), and leaching time (5, 24, 72, and 168 h) on the efficacy of the ESW process with realistic liquid-to-solid ratios. Another goal of this study was to evaluate the effectiveness of water washes on a sludge sample from hanford Tank C-103. The final objective of this study was to test potential process control monitors during the water washes and caustic leaches with actual sludge. Both {sup 137}Cs activity and conductance were measured for each of the water washes and caustic leaches. Experimental procedures, a discussion of results, conclusions and recommendations are included in this report.

  15. Fuel storage basin seismic analysis

    SciTech Connect (OSTI)

    Kanjilal, S.K.; Winkel, B.V.

    1991-08-01T23:59:59.000Z

    The 105-KE and 105-KW Fuel Storage Basins were constructed more than 35 years ago as repositories for irradiated fuel from the K East and K West Reactors. Currently, the basins contain irradiated fuel from the N Reactor. To continue to use the basins as desired, seismic adequacy in accordance with current US Department of Energy facility requirements must be demonstrated. The 105-KE and 105-KW Basins are reinforced concrete, belowground reservoirs with a 16-ft water depth. The entire water retention boundary, which currently includes a portion of the adjacent reactor buildings, must be qualified for the Hanford Site design basis earthquake. The reactor building interface joints are sealed against leakage with rubber water stops. Demonstration of the seismic adequacy of these interface joints was initially identified as a key issue in the seismic qualification effort. The issue of water leakage through seismicly induced cracks was also investigated. This issue, coupled with the relatively complex geometry of the basins, dictated a need for three-dimensional modeling. A three-dimensional soil/structure interaction model was developed with the SASSI computer code. The development of three-dimensional models of the interfacing structures using the ANSYS code was also found to be necessary. 8 refs., 7 figs., 1 tab.

  16. REAL WASTE TESTING OF SLUDGE BATCH 5 MELTER FEED RHEOLOGY

    SciTech Connect (OSTI)

    Reboul, S.; Stone, M.

    2010-03-17T23:59:59.000Z

    Clogging of the melter feed loop at the Defense Waste Processing Facility (DWPF) has reduced the throughput of Sludge Batch 5 (SB5) processing. After completing a data review, DWPF attributed the clogging to the rheological properties of the Slurry Mix Evaporator (SME) project. The yield stress of the SB5 melter feed material was expected to be high, based on the relatively high pH of the SME product and the rheological results of a previous Chemical Process Cell (CPC) demonstration performed at the Savannah River National Laboratory (SRNL).

  17. Completion optimization in the Black Warrior basin

    SciTech Connect (OSTI)

    NONE

    1997-09-01T23:59:59.000Z

    The Black Warrior basin continues to be an active area for development of coalbed methane. The majority of the successful wells have been in areas with relatively high permeability. A study was initiated to determine whether stimulation results could be improved by implementing specific optimization procedures for each of the coal groups. The optimization process included extensive prefracture formation evaluation, injection/falloff testing, in-situ-stress testing, fracture modeling with a three-dimensional (3D) simulator, and radioactive tracing of individual fluid and proppant stages with time-lapse monitoring. Several practical innovations were developed during the study that will aid in the design of the optimum treatment for each well.

  18. Delaware River Basin Commission (Multiple States)

    Broader source: Energy.gov [DOE]

    The Delaware River Basin Commission (DRBC) is a federal-interstate compact government agency that was formed by concurrent legislation enacted in 1961 by the United States and the four basin states...

  19. Basin width control of faulting in the Naryn Basin, south central Kyrgyzstan

    E-Print Network [OSTI]

    Bookhagen, Bodo

    Basin width control of faulting in the Naryn Basin, south central Kyrgyzstan Joseph K. Goode,1 the controls on this intramontane basin deformation, we study the Naryn Basin of south central Kyrgyzstan central Kyrgyzstan, Tectonics, 30, TC6009, doi:10.1029/2011TC002910. 1. Introduction [2] Deformation

  20. The Climate of the South Platte Basin

    E-Print Network [OSTI]

    The Climate of the South Platte Basin Colorado Climate Center http://climate.atmos.colostate.edu #12;Key Features of the Climate of the South Platte Basin #12;Temperature Cold winters Hot summers #12;Precipitation Monthly Average Precipitation for Selected Sites in the South Platte Basin 0.00 0

  1. Geological Modeling of Dahomey and Liberian Basins

    E-Print Network [OSTI]

    Gbadamosi, Hakeem B.

    2010-01-16T23:59:59.000Z

    The objective of this thesis is to study two Basins of the Gulf of Guinea (GoG), namely the Dahomey and the Liberian Basins. These Basins are located in the northern part of the GoG, where oil and gas exploration has significantly increased...

  2. Aluminum Leaching of ''Archived'' Sludge from Tanks 8F, 11H, and 12H

    SciTech Connect (OSTI)

    FONDEUR, FERNANDOF.

    2004-03-12T23:59:59.000Z

    Aluminum can promote formation or dissolution of networks in hydroxide solid solutions. When present in large amounts it will act as a network former increasing both the viscosity and the surface tension of melts. This translates into poor free flow properties that affect pour rate of glass production in the Defense Waste Processing Facility (DWPF). To mitigate this situation, DWPF operations limit the amount of aluminum contained in sludge. This study investigated the leaching of aluminum compounds from archived sludge samples. The conclusions found boehmite present as the predominant aluminum compound in sludge from two tanks. We did not identify an aluminum compound in sludge from the third tank. We did not detect any amorphous aluminum hydroxide in the samples. The amount of goethite measured 4.2 percentage weight while hematite measured 3.7 percentage weight in Tank 11H sludge. The recommended recipe for removing gibbsite in sludge proved inefficient for digesting boehmite, removing less than 50 per cent of the compound within 48 hours. The recipe did remove boehmite when the test ran for 10 days (i.e., 7 more days than the recommended baseline leaching period). Additions of fluoride and phosphate to Tank 12H archived sludge did not improve the aluminum leaching efficiency of the baseline recipe.

  3. Engineering Work Plan for Development of Sludge Pickup Adapter for Fuel Cleanliness Inspections

    SciTech Connect (OSTI)

    PITNER, A.L.

    2000-01-06T23:59:59.000Z

    The plan for developing an adapter to suction up sludge into a calibrated tube for fuel cleanliness inspection activities is described. A primary assessment of fuel cleanliness to be performed after processing through the Primary Cleaning Machine is whether the volume of any remaining canister sludge in or on a fuel assembly exceeds the allowable 14 cm{sup 3} limit. It is anticipated that a general visual inspection of the sludge inventory after fuel assembly separation will usually suffice in making this assessment, but occasions may arise where there is some question as to whether or not the observed quantity of sludge exceeds this limit. Therefore a quantitative method of collecting and measuring the sludge volume is needed for these borderline situations. It is proposed to develop an adapter that fits on the end of the secondary cleaning station vacuum wand that will suction the material from the sludge collection tray into a chamber marked with the limiting volume to permit a direct go/no-go assessment of the sludge quantity.

  4. Wastewater treatment by aerobic granular biofilmWastewater treatment by aerobic granular biofilmaste ate t eat e t by ae ob c g a u a b o Aeration pulses to improve N eliminationAeration pulses to improve N-eliminationAeration pulses to improve N eliminat

    E-Print Network [OSTI]

    Wastewater treatment by aerobic granular biofilmWastewater treatment by aerobic granular wastewater treatment p p denitrification Nitrification is the oxidation from ammonium (NH +) first activated sludge for biological N-elimination is a two step process: aerobic nitrification and anoxicp g g g

  5. Successful Deployment of System for the Storage and Retrieval of Spent/Used Nuclear Fuel from Hanford K-West Fuel Storage Basin-13051

    SciTech Connect (OSTI)

    Quintero, Roger; Smith, Sahid [U.S. Department of Energy, Richland Operations Office, Richland, Washington 99352 (United States)] [U.S. Department of Energy, Richland Operations Office, Richland, Washington 99352 (United States); Blackford, Leonard Ty; Johnson, Mike W.; Raymond, Richard; Sullivan, Neal; Sloughter, Jim [CH2M HILL Plateau Remediation Company, Richland, Washington 99352 (United States)] [CH2M HILL Plateau Remediation Company, Richland, Washington 99352 (United States)

    2013-07-01T23:59:59.000Z

    In 2012, a system was deployed to remove, transport, and interim store chemically reactive and highly radioactive sludge material from the Hanford Site's 105-K West Fuel Storage Basin that will be managed as spent/used nuclear fuel. The Knockout Pot (KOP) sludge in the 105-K West Basin was a legacy issue resulting from the spent nuclear fuel (SNF) washing process applied to 2200 metric tons of highly degraded fuel elements following long-term underwater storage. The washing process removed uranium metal and other non-uranium constituents that could pass through a screen with 0.25-inch openings; larger pieces are, by definition, SNF or fuel scrap. When originally retrieved, KOP sludge contained pieces of degraded uranium fuel ranging from 600 microns (?m) to 6350 ?m mixed with inert material such as aluminum hydroxide, aluminum wire, and graphite in the same size range. In 2011, a system was developed, tested, successfully deployed and operated to pre-treat KOP sludge as part of 105-K West Basin cleanup. The pretreatment process successfully removed the vast majority of inert material from the KOP sludge stream and reduced the remaining volume of material by approximately 65 percent, down to approximately 50 liters of material requiring management as used fuel. The removal of inert material resulted in significant waste minimization and project cost savings because of the reduced number of transportation/storage containers and improvement in worker safety. The improvement in worker safety is a result of shorter operating times and reduced number of remote handled shipments to the site fuel storage facility. Additionally in 2011, technology development, final design, and cold testing was completed on the system to be used in processing and packaging the remaining KOP material for removal from the basin in much the same manner spent fuel was removed. This system was deployed and successfully operated from June through September 2012, to remove and package the last of the SNF fragments from the 105-K West Basin, ending the long and complex history of the KOP sludge materials. The planning and execution of this project demonstrated how the graded application of DOE O 413.3B, Program and Project Management for the Acquisition of Capital Assets[1], DOE-STD-1189-2008, Integration of Safety into the Design Process[2], and DOE G 413.3-4, U.S. Department of Energy Technology Readiness Assessment Guide[3], can positively affect the outcome of project implementation in the DOE Complex. Provided herein are relevant information, ideas, and tools for use by other projects facing similar issues in managing high risk waste streams in a complex regulatory environment. Positive aspects are also provided of appropriate time spent in detailed planning, design, and testing in non-hazardous environments to reduce project risks in both cost and safety performance, as well as improving confidence in meeting project goals through predictable and reliable performance. (authors)

  6. Genetic classification of petroleum basins

    SciTech Connect (OSTI)

    Demaison, G.; Huizinga, B.J.

    1989-03-01T23:59:59.000Z

    Rather than relying on a descriptive geologic approach, this genetic classification is based on the universal laws that control processes of petroleum formation, migration, and entrapment. Petroleum basins or systems are defined as dynamic petroleum-generating and concentrating physico-chemical systems functioning on a geologic space and time scale. A petroleum system results from the combination of a generative subsystem (or hydrocarbon kitchen), essentially controlled by chemical processes, and a migration-entrapment subsystem, controlled by physical processes. The generative subsystem provides a certain supply of petroleum to the basin during a given geologic time span. The migration-entrapment subsystem receives petroleum and distributes it in a manner that can lead either to dispersion and loss or to concentration of the regional charge into economic accumulations. The authors classification scheme for petroleum basins rests on a simple working nomenclature consisting of the following qualifiers: (1) charge factor: undercharged, normally charged, or supercharged, (2) migration drainage factor: vertically drained or laterally drained, and (3) entrapment factor: low impedance or high impedance. Examples chosen from an extensive roster of documented petroleum basins are reviewed to explain the proposed classification.

  7. Organic and nitrogen removal from landfill leachate in aerobic granular sludge sequencing batch reactors

    SciTech Connect (OSTI)

    Wei Yanjie [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Key Laboratory of Environmental Protection in Water Transport Engineering Ministry of Communications, Tianjin Research Institute of Water Transport Engineering, Tianjin 300456 (China); Ji Min, E-mail: jmtju@yahoo.cn [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Li Ruying [School of Environmental Science and Engineering, Tianjin University, Tianjin 300072 (China); Qin Feifei [Tianjin Tanggu Sino French Water Supply Co. Ltd., Tianjin 300450 (China)

    2012-03-15T23:59:59.000Z

    Highlights: Black-Right-Pointing-Pointer Aerobic granular sludge SBR was used to treat real landfill leachate. Black-Right-Pointing-Pointer COD removal was analyzed kinetically using a modified model. Black-Right-Pointing-Pointer Characteristics of nitrogen removal at different ammonium inputs were explored. Black-Right-Pointing-Pointer DO variations were consistent with the GSBR performances at low ammonium inputs. - Abstract: Granule sequencing batch reactors (GSBR) were established for landfill leachate treatment, and the COD removal was analyzed kinetically using a modified model. Results showed that COD removal rate decreased as influent ammonium concentration increasing. Characteristics of nitrogen removal at different influent ammonium levels were also studied. When the ammonium concentration in the landfill leachate was 366 mg L{sup -1}, the dominant nitrogen removal process in the GSBR was simultaneous nitrification and denitrification (SND). Under the ammonium concentration of 788 mg L{sup -1}, nitrite accumulation occurred and the accumulated nitrite was reduced to nitrogen gas by the shortcut denitrification process. When the influent ammonium increased to a higher level of 1105 mg L{sup -1}, accumulation of nitrite and nitrate lasted in the whole cycle, and the removal efficiencies of total nitrogen and ammonium decreased to only 35.0% and 39.3%, respectively. Results also showed that DO was a useful process controlling parameter for the organics and nitrogen removal at low ammonium input.

  8. Air emissions assessment and air quality permitting for a municipal waste landfill treating municipal sewage sludge

    SciTech Connect (OSTI)

    Koehler, J. [Woodward-Clyde International -- Americas, Oakland, CA (United States)

    1998-12-31T23:59:59.000Z

    This paper presents a case study into the air quality permitting of a municipal solid waste (MSW) landfill in the San Francisco Bay Area undergoing a proposed expansion in operations to increase the life of the landfill. The operations of this facility include MSW landfilling, the treatment and disposal of municipal sewage sludge, the aeration of petroleum-contaminated soils, the construction of a new on-site plant to manufacture soil amendment products from waste wood and other organic material diverted from the landfill, and the installation of a vaporator to create steam from leachate for injection into the landfill gas flare. The emissions assessment for each project component relied upon interpretation of source tests from similar operations, incorporation of on-site measurements into emissions models and mass balances, and use of AP-42 procedures for emissions sources such as wind-blown dust, material handling and transfer operations, and fugitive landfill gas. Air permitting issues included best available control technology (BACT), emission offset thresholds, new source performance standards (NSPS), potential air toxics health risk impacts, and compliance with federal Title V operating permit requirements. With the increasing difficulties of siting new landfills, increasing pressures to reduce the rate of waste placement into existing landfills, and expanding regulatory requirements on landfill operations, experiences similar to those described in this paper are likely to increase in the future as permitting scenarios become more complex.

  9. Mississippian facies relationships, eastern Anadarko basin, Oklahoma

    SciTech Connect (OSTI)

    Peace, H.W. (Oryx Energy, Inc., Midland, TX (United States)); Forgotson, J.M. (Univ. of Oklahoma, Norman (United States))

    1991-08-01T23:59:59.000Z

    Mississippian strata in the eastern Anadarko basin record a gradual deepening of the basin. Late and post-Mississippian tectonism (Wichita and Arbuckle orogenies) fragmented the single large basin into the series of paired basins and uplifts recognized in the southern half of Oklahoma today. Lower Mississippian isopach and facies trends (Sycamore and Caney Formations) indicate that basinal strike in the study area (southeastern Anadarko basin) was predominantly east-west. Depositional environment interpretations made for Lower Mississippian strata suggest that the basin was partially sediment starved and exhibited a low shelf-to-basin gradient. Upper Mississippian isopach and facies trends suggest that basinal strike within the study area shifted from dominantly east-west to dominantly northwest-southeast due to Late Mississippian and Early Pennsylvanian uplift along the Nemaha ridge. Within the study area, the Chester Formation, composed of gray to dove-gray shales with interbedded limestones deposited on a carbonate shelf, thins depositionally into the basin and is thinnest at its facies boundary with the Springer Group and the upper portion of the Caney Formation. As basin subsidence rates accelerated, the southern edge of the Chester carbonate shelf was progressively drowned, causing a backstepping of the Chester Formation calcareous shale and carbonate facies. Springer Group sands and black shales transgressed northward over the drowned Chester Formation shelf.

  10. DOWNSTREAM IMPACTS OF SLUDGE MASS REDUCTION VIA ALUMINUM DISSOLUTION ON DWPF PROCESSING OF SAVANNAH RIVER SITE HIGH LEVEL WASTE - 9382

    SciTech Connect (OSTI)

    Pareizs, J; Cj Bannochie, C; Michael Hay, M; Daniel McCabe, D

    2009-01-14T23:59:59.000Z

    The SRS sludge that was to become a major fraction of Sludge Batch 5 (SB5) for the Defense Waste Processing Facility (DWPF) contained a large fraction of H-Modified PUREX (HM) sludge, containing a large fraction of aluminum compounds that could adversely impact the processing and increase the vitrified waste volume. It is beneficial to reduce the non-radioactive fraction of the sludge to minimize the number of glass waste canisters that must be sent to a Federal Repository. Removal of aluminum compounds, such as boehmite and gibbsite, from sludge can be performed with the addition of NaOH solution and heating the sludge for several days. Preparation of SB5 involved adding sodium hydroxide directly to the waste tank and heating the contents to a moderate temperature through slurry pump operation to remove a fraction of this aluminum. The Savannah River National Laboratory (SRNL) was tasked with demonstrating this process on actual tank waste sludge in our Shielded Cells Facility. This paper evaluates some of the impacts of aluminum dissolution on sludge washing and DWPF processing by comparing sludge processing with and without aluminum dissolution. It was necessary to demonstrate these steps to ensure that the aluminum removal process would not adversely impact the chemical and physical properties of the sludge which could result in slower processing or process upsets in the DWPF.

  11. F- and H-area Sewage Sludge Application Sites: Groundwater monitoring report. Second quarter 1993

    SciTech Connect (OSTI)

    Not Available

    1993-10-01T23:59:59.000Z

    Samples from the four wells at the F-Area Sewage Sludge Application Site (FSS wells) and the three wells at the H-Area Sewage Sludge Application Site (HSS wells) are analyzed quarterly for constituents as required by South Carolina Department of Health and Environmental Control Construction Permit 12,076 and, as requested, for other constituents as part of the Savannah River Site Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals, also are required by the permit. Currently, no permit-required analytes exceed standards at the F- and H-Area Sewage Sludge Application Sites. Tritium and aluminum have been the primary nonpermit constituents exceeding standards at the F-Area Sewage Sludge Application Site. These constituents were not analyzed second quarter 1993. Other constituents also have exceeded standards at this site, but only sporadically, and none of those were analyzed second quarter 1993.

  12. F- and H-Area Sewage Sludge Application Sites groundwater monitoring report

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    Samples from the four wells at the F-Area Sewage Sludge Application Site (FSS wells) and the three wells at the H-Area Sewage Sludge Application Site (HSS wells) are analyzed quarterly for constituents as required by South Carolina Department of Health and Environmental Control Construction Permit 12,076 and, as requested, for other constituents as part of the Savannah River Site Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals, also are required by the permit. Historically and currently, no permit-required analytes exceed standards at the F- and H-Area Sewage Sludge Application Sites except iron, lead, and manganese, which occur in elevated concentrations frequently in FSS wells and occasionally in HSS wells. Tritium and aluminum are the primary nonpermit constituents that exceed standards at the F-Area Sewage Sludge Application Site. Other constituents also exceed standards at this site but only sporadically.

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

    SciTech Connect (OSTI)

    Hunt, R.D.; Kauschinger, J.L.; Spence, R.D.

    1999-04-01T23:59:59.000Z

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

  14. Decision analysis for mobilizing and retrieving sludge from double-shell tanks

    SciTech Connect (OSTI)

    Brothers, A.J.; Williams, N.C.; Dukelow, J.S.; Hansen, R.I. [and others] [and others

    1997-09-01T23:59:59.000Z

    This decision analysis evaluates alternative technologies for the initial mobilization and retrieval of sludges in double-shell tanks (DSTs). The analysis is from the perspective of the need to move sludges from one DST to another for interim retrieval. It supports the more general decision of which technologies to use to retreive various types of DST waste. The initial analysis is from the perspective of a typical DST with 2 ft of sludge to mobilize. During the course of the analysis, it became clear that it was important to also consider sludge mobilization in support of the high-level waste (HLW) vitrification demonstration plant, and in particular the risks associated with failing to meeting the minimum order requirements for the vendor, as well as the cost of mobilization and retrieval from the HLW vitrification source tanks.

  15. Microbial acidification and pH effects on trace element release from sewage sludge

    E-Print Network [OSTI]

    Walter, M.Todd

    readsorbed by calcareous sand when present. Ó 2004 Elsevier Ltd. All rights reserved. Keywords: Biosolids sludge (sewage biosolids) are potentially phyto- or zoo-toxic if present in sufficient concentration

  16. DEVELOPMENT OF HAZARDOUS SLUDGE SIMULANTS FOR ENHANCED CHEMICAL CLEANING TESTS

    SciTech Connect (OSTI)

    Eibling, R.

    2010-04-12T23:59:59.000Z

    An Enhanced Chemical Cleaning (ECC) process is being developed by Savannah River Remediation (SRR) to aid in Savannah River Site (SRS) High-Level Waste (HLW) tank closure. After bulk waste removal, the ECC process can be used to dissolve and remove much of the remaining sludge from HLW tanks. The ECC process uses dilute oxalic acid (1 wt %) with in-line pH monitoring and control. The resulting oxalate is decomposed through hydroxylation using an Advanced Oxidation Process (AOP). Minimizing the amount of oxalic acid used for dissolution and the subsequent oxidative destruction of oxalic acid will minimize the potential for downstream impacts. Initial efficacy tests by AREVA demonstrated that previous tank heel simulants could be dissolved using dilute oxalic acid. The oxalate could be decomposed by an AOP that utilized ozone and ultraviolet (UV) light, and the resultant metal oxides and hydroxides could be separated out of the process.

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

    SciTech Connect (OSTI)

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

    2011-01-12T23:59:59.000Z

    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.

  18. THE ADVANCED CHEMISTRY BASINS PROJECT

    SciTech Connect (OSTI)

    William Goddard; Peter Meulbroek; Yongchun Tang; Lawrence Cathles III

    2004-04-05T23:59:59.000Z

    In the next decades, oil exploration by majors and independents will increasingly be in remote, inaccessible areas, or in areas where there has been extensive shallow exploration but deeper exploration potential may remain; areas where the collection of data is expensive, difficult, or even impossible, and where the most efficient use of existing data can drive the economics of the target. The ability to read hydrocarbon chemistry in terms of subsurface migration processes by relating it to the evolution of the basin and fluid migration is perhaps the single technological capability that could most improve our ability to explore effectively because it would allow us to use a vast store of existing or easily collected chemical data to determine the major migration pathways in a basin and to determine if there is deep exploration potential. To this end a the DOE funded a joint effort between California Institute of Technology, Cornell University, and GeoGroup Inc. to assemble a representative set of maturity and maturation kinetic models and develop an advanced basin model able to predict the chemistry of hydrocarbons in a basin from this input data. The four year project is now completed and has produced set of public domain maturity indicator and maturation kinetic data set, an oil chemistry and flash calculation tool operable under Excel, and a user friendly, graphically intuitive basin model that uses this data and flash tool, operates on a PC, and simulates hydrocarbon generation and migration and the chemical changes that can occur during migration (such as phase separation and gas washing). The DOE Advanced Chemistry Basin Model includes a number of new methods that represent advances over current technology. The model is built around the concept of handling arbitrarily detailed chemical composition of fluids in a robust finite-element 2-D grid. There are three themes on which the model focuses: chemical kinetic and equilibrium reaction parameters, chemical phase equilibrium, and physical flow through porous media. The chemical kinetic scheme includes thermal indicators including vitrinite, sterane ratios, hopane ratios, and diamonoids; and a user-modifiable reaction network for primary and secondary maturation. Also provided is a database of type-specific kerogen maturation schemes. The phase equilibrium scheme includes modules for primary and secondary migration, multi-phase equilibrium (flash) calculations, and viscosity predictions.

  19. The determination of settling velocities for sewage sludge disposed at 106-Mile Site

    E-Print Network [OSTI]

    Hernandez, Daniel Saul

    1991-01-01T23:59:59.000Z

    THE DBTERMZNATZON OF SETTLING VELOCZTZES FOR SEWAGE SLUDGE DZSPOSED AT 106-MILE SITE A Thesis by DANIEL SAUL HERNANDEZ Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of requirements for the degree... of MASTER OF SCIENCE December 1991 Major Subject: Civil Engineering THB DETERMZNATZON OF SBTTLZNG VELOCZTZES FOR SEWAGE SLUDGE DZSPOSBD AT 106-MZLE SZTB A Thesis by DANIEL SAUL HERNANDEZ Approved as to style and content by: James S. Bonner '(Chair...

  20. Mutagenic potential of plants grown on a soil amended with mutagenic municipal sewage sludge

    E-Print Network [OSTI]

    Fiedler, Daniel Alain

    1988-01-01T23:59:59.000Z

    MUTAGENIC POTENTIAL OF PLANTS GROWN ON A SOIL AMENDED WITH MUTAGENIC MUNICIPAL SEWAGE SLUDGE A Thesis by DANIEL ALAIN FIEDLER Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirements for the degree... of MASTER OF SCIENCE May 1988 Major Subject: Agronomy MUTAGENIC POTENTIAL OF PLANTS GROWN ON A SOIL AMENDED WITH MUTAGENIC MUNICIPAL SEWAGE SLUDGE A Thesis by DANIEL ALAIN FIEDLER Approved as to sty1e and content by; Kirk W. Brown (Chairman...

  1. The effect of sewage sludge on the physical properties of lignite overburden

    E-Print Network [OSTI]

    Cocke, Catherine Lynn

    1985-01-01T23:59:59.000Z

    THE EFFECT OF SEWAGE SLUDGE ON THE PHYSICAL PROPERTIES OF LIGNITE OVERBURDEN A Thesis by CATHERINE LYNN COCKE Submitted to the Graduate College of Texas A&M University in Partial fulfillment of the requirements for the degree of MASTER... OF SCIENCE August 1985 Major Subject: Soil Science THE EFFECT OF SEWAGE SLUDGE ON THE PHYSICAL PROPERTIES OF LIGNITE OVERBURDEN A Thesis by CATHERINE LYNN COCK E Appr as o style and content by: . W. Brown (Chairman of Committee) . Hons (Member...

  2. Treatment options for low-level radiologically contaminated ORNL filtercake

    SciTech Connect (OSTI)

    Lee, Hom-Ti [Oak Ridge Associated Universities, Inc., TN (United States); Bostick, W.D. [Oak Ridge K-25 Site, TN (United States)

    1996-04-01T23:59:59.000Z

    Water softening sludge (>4000 stored low level contaminated drums; 600 drums per year) generated by the ORNL Process Waste Treatment Plant must be treated, stabilized, and placed in safe storage/disposal. The sludge is primarily CaCO{sub 3} and is contaminated by low levels of {sup 90}Sr and {sup 137}Cs. In this study, microwave sintering and calcination were evaluated for treating the sludge. The microwave melting experiments showed promise: volume reductions were significant (3-5X), and the waste form was durable with glass additives (LiOH, fly ash). A commercial vendor using surrogate has demonstrated a melt mineralization process that yields a dense monolithic waste form with a volume reduction factor (VR) of 7.7. Calcination of the sludge at 850-900 C yielded a VR of 2.5. Compaction at 4500 psi increased the VR to 4.2, but the compressed form is not dimensionally stable. Addition of paraffin helped consolidate fines and yielded a VR of 3.5. In conclusion, microwave melting or another form of vitrification is likely to be the best method; however for immediate implementation, the calculation/compaction/waxing process is viable.

  3. Silurian of Illinois basin - a carbonate ramp

    SciTech Connect (OSTI)

    Coburn, G.W.

    1986-05-01T23:59:59.000Z

    The Silurian of the Illinois basin has classically been defined as a shelf-basin sequence. According to the shelf-basin model, the Illinois basin is a deep-water basin in the extreme southern part (southern Illinois-Tennessee), with a slope in the south (Illinois-Indiana) and a shelf extending from central Illinois and Indiana northeast to the Michigan basin. Reef buildups are in a continuous trend along the shelf break. However, the author proposes that the silurian of the Illinois basin represents a carbonate ramp. The down-ramp position is located in southern Illinois and grades into deeper water environments south of Illinois. In this environment, reef buildups would form in the late Alexandrian of early St. Clair, and would begin in the down-ramp position. Therefore, using the new model, reef buildups are expected throughout the basin, rather than being confined to an imaginary shelf break. This model would facilitate exploration in southern Illinois, Indiana, and western Kentucky for reefal hydrocarbon deposits. A ramp model is indicated for the Illinois basin because: (1) the basin lacks a shelf-slope break; (2) the facies sequence is compatible with a ramp environment and incompatible with a shelf-slope environment; (3) discontinuous reef trends are typical of a ramp environment; and (4) facies changes and slope are gradual, extending over hundreds of miles as expected in a ramp environment. Modern carbonate models border on ocean basins. However, the Illinois basin is a cratonic basin, which may have affected the depositional environments. How much that environment differed from present-day models is unknown.

  4. CLEAR LAKE BASIN 2000 PROJECT

    SciTech Connect (OSTI)

    LAKE COUNTY SANITATION DISTRICT

    2003-03-31T23:59:59.000Z

    The following is a final report for the Clear Lake Basin 2000 project. All of the major project construction work was complete and this phase generally included final details and testing. Most of the work was electrical. Erosion control activities were underway to prepare for the rainy season. System testing including pump stations, electrical and computer control systems was conducted. Most of the project focus from November onward was completing punch list items.

  5. HIGH LEVEL WASTE MECHANCIAL SLUDGE REMOVAL AT THE SAVANNAH RIVER SITE F TANK FARM CLOSURE PROJECT

    SciTech Connect (OSTI)

    Jolly, R; Bruce Martin, B

    2008-01-15T23:59:59.000Z

    The Savannah River Site F-Tank Farm Closure project has successfully performed Mechanical Sludge Removal (MSR) using the Waste on Wheels (WOW) system for the first time within one of its storage tanks. The WOW system is designed to be relatively mobile with the ability for many components to be redeployed to multiple waste tanks. It is primarily comprised of Submersible Mixer Pumps (SMPs), Submersible Transfer Pumps (STPs), and a mobile control room with a control panel and variable speed drives. In addition, the project is currently preparing another waste tank for MSR utilizing lessons learned from this previous operational activity. These tanks, designated as Tank 6 and Tank 5 respectively, are Type I waste tanks located in F-Tank Farm (FTF) with a capacity of 2,840 cubic meters (750,000 gallons) each. The construction of these tanks was completed in 1953, and they were placed into waste storage service in 1959. The tank's primary shell is 23 meters (75 feet) in diameter, and 7.5 meters (24.5 feet) in height. Type I tanks have 34 vertically oriented cooling coils and two horizontal cooling coil circuits along the tank floor. Both Tank 5 and Tank 6 received and stored F-PUREX waste during their operating service time before sludge removal was performed. DOE intends to remove from service and operationally close (fill with grout) Tank 5 and Tank 6 and other HLW tanks that do not meet current containment standards. Mechanical Sludge Removal, the first step in the tank closure process, will be followed by chemical cleaning. After obtaining regulatory approval, the tanks will be isolated and filled with grout for long-term stabilization. Mechanical Sludge Removal operations within Tank 6 removed approximately 75% of the original 95,000 liters (25,000 gallons). This sludge material was transferred in batches to an interim storage tank to prepare for vitrification. This operation consisted of eleven (11) Submersible Mixer Pump(s) mixing campaigns and multiple intraarea transfers utilizing STPs from July 2006 to August 2007. This operation and successful removal of sludge material meets requirement of approximately 19,000 to 28,000 liters (5,000 to 7,500 gallons) remaining prior to the Chemical Cleaning process. Removal of the last 35% of sludge was exponentially more difficult, as less and less sludge was available to mobilize and the lighter sludge particles were likely removed during the early mixing campaigns. The removal of the 72,000 liters (19,000 gallons) of sludge was challenging due to a number factors. One primary factor was the complex internal cooling coil array within Tank 6 that obstructed mixer discharge jets and impacted the Effective Cleaning Radius (ECR) of the Submersible Mixer Pumps. Minimal access locations into the tank through tank openings (risers) presented a challenge because the available options for equipment locations were very limited. Mechanical Sludge Removal activities using SMPs caused the sludge to migrate to areas of the tank that were outside of the SMP ECR. Various SMP operational strategies were used to address the challenge of moving sludge from remote areas of the tank to the transfer pump. This paper describes in detail the Mechanical Sludge Removal activities and mitigative solutions to cooling coil obstructions and other challenges. The performance of the WOW system and SMP operational strategies were evaluated and the resulting lessons learned are described for application to future Mechanical Sludge Removal operations.

  6. The mobility of water soluble organic compounds in soils from the land application of petroleum waste sludge

    E-Print Network [OSTI]

    Evans, Gordon Barcus

    1979-01-01T23:59:59.000Z

    of gas oil. Fertilizer effects. The nutrient balance further af- fects deterioration of oil. For instance, petroleum sludges have a high C:N ratio which can serve to limit microbial respiration to well below its potential. Addi- tion of nitrogen... an API oil-water separator sludge. Three soils, Bastrop sandy loam, Nacogdoches clay loam, and Norwood loam, were chosen to be representative of potential disposal sites. A sludge containing 41/ water and 10/ solvent extractable hydrocarbons...

  7. The determination of PCBs in Rocky Flats Type IV waste sludge by gas chromatography/electron capture detection. Part 2

    SciTech Connect (OSTI)

    Parish, K.J.; Applegate, D.V.; Postlethwait, P.D.; Boparai, A.S.; Reedy, G.T.

    1994-12-01T23:59:59.000Z

    Before disposal, radioactive sludge (Type IV) from Rocky Flats Plant (RFP) must be evaluated for polychlorinated biphenyl (PCB) content. The Type IV sludge consists of organic solvents, degreasers, cutting oils, and transuranic (TRU) waste mixed with calcium silicate (MicroCel E{reg_sign} and Oil Dri{reg_sign} to form a grease or paste-like material. For laboratory testing, a nonradioactive simulated Type 17V RFP sludge was prepared at Argonne National Laboratory-East (ANL-E). This sludge has a composition similar to that expected from field samples. In an earlier effort, a simplified method was developed for extraction, cleanup of extract, and determination of PCBs in samples of simulated sludge spiked with Aroclors 1254 and 1260. The simplified method has now been used to determine the presence and quantities of other Aroclors in the simulated sludge, namely, Aroclors 10 1 6, 1221, 1232, 1242, and 1248. The accuracy and precision of the data for these Aroclors were found to be similar to the data for sludges spiked with Aroclors 1254 and 1260. Since actual sludges may vary in composition, the method was also verified by analyzing another source of Type IV simulated sludge, prepared by Argonne National Laboratory-West (ANL-W).

  8. Laboratory Report on Performance Evaluation of Key Constituents during Pre-Treatment of High Level Waste Direct Feed

    SciTech Connect (OSTI)

    Huber, Heinz J.

    2013-06-24T23:59:59.000Z

    The analytical capabilities of the 222-S Laboratory are tested against the requirements for an optional start up scenario of the Waste Treatment and Immobilization Plant on the Hanford Site. In this case, washed and in-tank leached sludge would be sent directly to the High Level Melter, bypassing Pretreatment. The sludge samples would need to be analyzed for certain key constituents in terms identifying melter-related issues and adjustment needs. The analyses on original tank waste as well as on washed and leached material were performed using five sludge samples from tanks 241-AY-102, 241-AZ-102, 241-AN-106, 241-AW-105, and 241-SY-102. Additionally, solid phase characterization was applied to determine the changes in mineralogy throughout the pre-treatment steps.

  9. IMPACT OF IRRADIATION AND THERMAL AGING ON DWPF SIMULATED SLUDGE PROPERTIES

    SciTech Connect (OSTI)

    Eibling, R; Michael Stone, M

    2006-10-16T23:59:59.000Z

    The research and development programs in support of the Defense Waste Processing Facility (DWPF) and other high-level waste vitrification processes require the use of both nonradioactive waste simulants and actual waste samples. While actual waste samples are the ideal materials to study, acquiring large quantities of actual waste is difficult and expensive. Tests utilizing actual high-level waste require the use of expensive shielded cells facilities to provide sufficient shielding for the researchers. Nonradioactive waste simulants have been used for laboratory testing, pilot-scale testing and full-scale integrated facility testing. These waste simulants were designed to reproduce the chemical and, if possible, the physical properties of the actual high-level waste. This technical report documents a study on the impact of irradiating a Sludge Batch 3 (SB3) simulant and of additional tests on aging a SB3 simulant by additional thermal processing. Prior simulant development studies examined methods of producing sludge and supernate simulants and processes that could be used to alter the physical properties of the simulant to more accurately mimic the properties of actual waste. Development of a precipitated sludge simulant for the River Protection Project (RPP) demonstrated that the application of heat for a period of time could significantly alter the rheology of the sludge simulant. The RPP precipitated simulant used distillation to concentrate the sludge solids and produced a reduction in sludge yield stress of up to 80% compared to the initial sludge properties. Observations at that time suggested that a substantial fraction of the iron hydroxide had converted to the oxide during the distillation. DWPF sludge simulant studies showed a much smaller reduction in yield stress ({approx}10%), demonstrated the impact of shear on particle size, and showed that smaller particle sizes yielded higher yield stress products. The current study documented in this report focuses on the SB3 sludge composition and recipe developed during the previous year as part of the simulant development program. The study examines the impact of a rapid dose of radiation on the physical properties of the SB3 simulant, the effect of temperature and time on the application of heat as a simulant aging mechanism, and the application of crossflow filtration to the production of an all-metals-precipitated SB3 sludge simulant.

  10. Sediment from hydraulic mining detained by Englebright and small dams in the Yuba basin

    E-Print Network [OSTI]

    James, L. Allan

    Sediment from hydraulic mining detained by Englebright and small dams in the Yuba basin L. Allan substantial modifications or removal of Englebright Dam, a large dam (86 million m3 capacity) built by the U organizations, therefore, is examining aspects of various dam-treatment scenarios that range from no action

  11. Reserves in western basins: Part 1, Greater Green River basin

    SciTech Connect (OSTI)

    Not Available

    1993-10-01T23:59:59.000Z

    This study characterizes an extremely large gas resource located in low permeability, overpressured sandstone reservoirs located below 8,000 feet drill depth in the Greater Green River basin, Wyoming. Total in place resource is estimated at 1,968 Tcf. Via application of geologic, engineering and economic criteria, the portion of this resource potentially recoverable as reserves is estimated. Those volumes estimated include probable, possible and potential categories and total 33 Tcf as a mean estimate of recoverable gas for all plays considered in the basin. Five plays (formations) were included in this study and each was separately analyzed in terms of its overpressured, tight gas resource, established productive characteristics and future reserves potential based on a constant $2/Mcf wellhead gas price scenario. A scheme has been developed to break the overall resource estimate down into components that can be considered as differing technical and economic challenges that must be overcome in order to exploit such resources: in other words, to convert those resources to economically recoverable reserves. Total recoverable reserves estimates of 33 Tcf do not include the existing production from overpressured tight reservoirs in the basin. These have estimated ultimate recovery of approximately 1.6 Tcf, or a per well average recovery of 2.3 Bcf. Due to the fact that considerable pay thicknesses can be present, wells can be economic despite limited drainage areas. It is typical for significant bypassed gas to be present at inter-well locations because drainage areas are commonly less than regulatory well spacing requirements.

  12. Characterization, Washing, Leaching, and Filtration of C-104 Sludge

    SciTech Connect (OSTI)

    KP Brooks; PR Bredt; GR Golcar; SA Hartley; LK Jagoda; KG Rappe; MW Urie

    2000-06-09T23:59:59.000Z

    Approximately 1,400 g of wet Hanford Tank C-104 Sludge was evaluated by Battelle for the high-level waste (HLW) pretreatment processes of ultrafiltration, dilute caustic washing, and elevated-temperature caustic leaching. The filterability of diluted C-104 sludge was measured with a 0.1-{micro}m sintered metal Mott filter using a 24-inch-long, single-element, crossflow filtration system (cells unit filter [CUF]). While the filtrate was being recirculated prior to washing and leaching, a 6.9 wt% solids slurry was evaluated with a matrix of seven 1-hour conditions of varying trans-membrane pressure (30 to 70 psid) and axial velocity (9 to 15 ft/s). The filtrate flux and backpulse efficiency were determined for each condition. The slurry was concentrated to 23 wt% solids, a second matrix of six 1-hour conditions was performed, and data analogous to that recorded in the first matrix were obtained. The low-solids-concentration matrix produced filtrate flux rates that ranged from 0.038 to 0.083 gpm/ft{sup 2}. The high-solids-concentration matrix produced filtrate flux rates that ranged from 0.0095 to 0.0172 gpm/ft{sup 2}. In both cases, the optimum filtrate flux was at the highest axial velocity (15 ft/s) and transmembrane pressure had little effect. Nearly all of the measured filtrate fluxes were more than an order of magnitude greater than the required plant flux for C-104 of 0.00126 gpm/ft{sup 2}. In both matrices, the filtrate flux appeared to be proportional to axial velocity, and the permeability appeared to be inversely proportional to the trans-membrane pressure. The first test condition was repeated as the last test condition for each matrix. In both cases, there was a significant decrease in filtrate flux, indicating some filter fouling during the test matrix that could not be removed by backpulsing alone, although the backpulse number and duration were not optimized. Following testing of these two matrices, the material was washed within the CUF by continuously adding approximately 5 L of 0.01-M NaOH and then removing it through the filter as permeate. The purpose of this washing step with 0.01-MNaOH was to remove water-soluble components that might inhibit dissolution of salts during caustic leaching, while avoiding peptization of the solids that occurs at a pH below 12. After washing the sludge with dilute caustic, it was combined with 3-M caustic, and the slurry was leached in a stainless steel vessel at 85 C for 8 hours. This leaching was followed by two 0.01-M caustic washes, each conducted in a stainless steel vessel to dilute remaining analytes from the interstitial liquids. Each rinse was performed at 85 C for 8 hours. Permeate from each of these process steps was removed using the crossflow filter system. Samples of the permeate from each slurry-washing activity and all intermediate process steps were taken and analyzed for chemical and radiochemical constituents. The fraction of each component removed was calculated. Key results are presented in Table S.1.

  13. WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS USING POST ALUMINUM DISSOLUTION TANK 51 SLUDGE SLURRY

    SciTech Connect (OSTI)

    Pareizs, J; Cj Bannochie, C; Damon Click, D; Erich Hansen, E; Dan Lambert, D; Michael Stone, M

    2008-04-28T23:59:59.000Z

    The remaining contents of Tank 51 from Sludge Batch 4 will be blended with Purex sludge from Tank 7 to constitute Sludge Batch 5 (SB5). The Savannah River Site (SRS) Liquid Waste Organization (LWO) has completed caustic addition to Tank 51 to perform low temperature Al dissolution on the H-Modified (HM) sludge material to reduce the total mass of sludge solids and Al being fed to the Defense Waste Processing Facility (DWPF). The Savannah River National Lab (SRNL) has also completed aluminum dissolution tests using a 3-L sample of Tank 51 sludge slurry through funding by DOE EM-21. This report documents assessment of downstream impacts of the aluminum dissolved sludge, which were investigated so technical issues could be identified before the start of SB5 processing. This assessment included washing the aluminum dissolved sludge to a Tank Farm projected sodium concentration and weight percent insoluble solids content and DWPF Chemical Process Cell (CPC) processing using the washed sludge. Based on the limited testing, the impact of aluminum dissolution on sludge settling is not clear. Settling was not predictable for the 3-L sample. Compared to the post aluminum dissolution sample, settling after the first wash was slower, but settling after the second wash was faster. For example, post aluminum dissolution sludge took six days to settle to 60% of the original sludge slurry height, while Wash 1 took nearly eight days, and Wash 2 only took two days. Aluminum dissolution did impact sludge rheology. A comparison between the as-received, post aluminum dissolution and washed samples indicate that the downstream materials were more viscous and the concentration of insoluble solids less than that of the starting material. This increase in viscosity may impact Tank 51 transfers to Tank 40. The impact of aluminum dissolution on DWPF CPC processing cannot be determined because acid addition for the Sludge Receipt and Adjustment Tank (SRAT) cycle was under-calculated and thus under-added. Although the sludge was rheologically thick throughout the SRAT and Slurry Mix Evaporator (SME) cycles, this may have been due to the under addition of acid. Aluminum dissolution did, however, impact analyses of the SRAT receipt material. Two methods for determining total base yielded significantly different results. The high hydroxide content and the relatively high soluble aluminum content of the washed post aluminum dissolution sludge likely contributed to this difference and the ultimate under addition of acid. It should be noted that the simulant used to provide input for the SRAT cycle was an inadequate representation of the waste in terms of acid demand, likely due to the differences in the form of aluminum and hydroxide in the simulant and actual waste. Based on the results of this task, it is recommended that: (1) Sludge settling and rheology during washing of the forthcoming Sludge Batch 5 qualification sample be monitored closely and communicated to the Tank Farm. (2) SRNL receive a sample of Tank 51 after all chemical additions have been made and prior to the final Sludge Batch 5 decant for rheological assessment. Rheology versus wt% insoluble solids will be performed to determine the maximum amount of decant prior to the Tank 51 to Tank 40 transfer. (3) As a result of the problem with measuring total base and subsequently under-calculating acid for the DWPF CPC processing of the post aluminum dissolution sludge; (4) Studies to develop understanding of how the sludge titrates (i.e., why different titration methods yield different results) should be performed. (5) Simulants that better match the properties of post aluminum dissolution sludge should be developed. (6) Work on developing an acid calculation less dependant on the total base measurement should be continued.

  14. Tank 40 Final Sludge Batch 8 Chemical Characterization Results

    SciTech Connect (OSTI)

    Bannochie, Christopher J.

    2013-09-19T23:59:59.000Z

    A sample of Sludge Batch 8 (SB8) was pulled from Tank 40 in order to obtain radionuclide inventory analyses necessary for compliance with the Waste Acceptance Product Specifications (WAPS). The SB8 WAPS sample was also analyzed for chemical composition, including noble metals, and fissile constituents, and these results are reported here. These analyses along with the WAPS radionuclide analyses will help define the composition of the sludge in Tank 40 that is currently being fed to the Defense Waste Processing Facility (DWPF) as SB8. At SRNL, the 3-L Tank 40 SB8 sample was transferred from the shipping container into a 4-L high density polyethylene bottle and solids were allowed to settle. Supernate was then siphoned off and circulated through the shipping container to complete the transfer of the sample. Following thorough mixing of the 3-L sample, a 553 g sub-sample was removed. This sub-sample was then utilized for all subsequent slurry sample preparations. Eight separate aliquots of the slurry were digested, four with HNO{sub 3}/HCl (aqua regia) in sealed Teflon(r) vessels and four with NaOH/Na{sub 2}O{sub 2} (alkali or peroxide fusion) using Zr crucibles. Two Analytical Reference Glass - 1 (ARG-1) standards were digested along with a blank for each preparation. Each aqua regia digestion and blank was diluted to 1:100 mL with deionized water and submitted to Analytical Development (AD) for inductively coupled plasma - atomic emission spectroscopy (ICP-AES) analysis, inductively coupled plasma - mass spectrometry (ICP-MS) analysis, atomic absorption spectroscopy (AA) for As and Se, and cold vapor atomic absorption spectroscopy (CV-AA) for Hg. Equivalent dilutions of the alkali fusion digestions and blank were submitted to AD for ICP-AES analysis. Tank 40 SB8 supernate was collected from a mixed slurry sample in the SRNL Shielded Cells and submitted to AD for ICP-AES, ion chromatography (IC), total base/free OH-/other base, total inorganic carbon/total organic carbon (TIC/TOC) analyses. Weighted dilutions of slurry were submitted for IC, TIC/TOC, and total base/free OH-/other base analyses. Activities for U-233, U-235, and Pu-239 were determined from the ICP-MS data for the aqua regia digestions of the Tank 40 WAPS slurry using the specific activity of each isotope. The Pu-241 value was determined from a Pu-238/-241 method developed by SRNL AD and previously described.

  15. Dump fire leaves toxic air, sludge A fire which burned for four days at a landfill site in Thessaloniki, sending thick black

    E-Print Network [OSTI]

    Columbia University

    Dump fire leaves toxic air, sludge A fire which burned for four days at a landfill site to break. This led to sludge flowing into some nearby houses. Authorities are due to begin the cleanup

  16. Upflow anaerobic sludge blanket reactors for treatment of wastewater from the brewery industry

    E-Print Network [OSTI]

    Scampini, Amanda C

    2010-01-01T23:59:59.000Z

    Anaerobic digestion can be utilized to convert industrial wastewater into clean water and energy. The goal of this project was to set up lab-scale anaerobic digesters to collect data that will be used to develop and validate ...

  17. Operational Awareness Review of the Hanford Sludge Treatment Project, April 2011

    Office of Environmental Management (EM)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative1 First Use of Energy for All Purposes (Fuel and Nonfuel), 2002; Level: National5Sales for4,645 3,625 1,006 492 742 33Frequently Asked QuestionsDepartmentGas and Oil ResearchEnergyOnHSS Independent Activity Report -

  18. Timing and Tectonic implications of basin inversion in the Nam Con Son Basin and adjacent areas, southern South China Sea

    E-Print Network [OSTI]

    Olson, Christopher Charles

    2001-01-01T23:59:59.000Z

    The Nam Con Son (NCS) Basin, located offshore of SE Vietnam, is one of several Tertiary rift basins that formed during initial Eocene(?)-Oligocene rifting. Following cessation of rifting at the end of Oligocene time, these basins were subjected...

  19. area sichuan basin: Topics by E-print Network

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

    area has been extensively unknown authors 59 outside the Pachitea River Basin, Peru CiteSeer Summary: At a superficial look, the Pachitea river basin gives the impression...

  20. area tarim basin: Topics by E-print Network

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

    area has been extensively unknown authors 65 outside the Pachitea River Basin, Peru CiteSeer Summary: At a superficial look, the Pachitea river basin gives the impression...

  1. area groundwater basin: Topics by E-print Network

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

    concerning aspects of petroleum geochemistry in the basin, especially in determining source rock(s) in the western part of this basin. It has been speculated that Ngimbang...

  2. Teleseismic-Seismic Monitoring At Nw Basin & Range Region (Biasi...

    Open Energy Info (EERE)

    Teleseismic-Seismic Monitoring At Nw Basin & Range Region (Biasi, Et Al., 2008) Exploration Activity Details Location Northwest Basin and Range Geothermal Region Exploration...

  3. Teleseismic-Seismic Monitoring At Nw Basin & Range Region (Biasi...

    Open Energy Info (EERE)

    Teleseismic-Seismic Monitoring At Nw Basin & Range Region (Biasi, Et Al., 2009) Exploration Activity Details Location Northwest Basin and Range Geothermal Region Exploration...

  4. Transuranic Waste Processing Center (TWPC) Legacy Tank RH-TRU Sludge Processing and Compliance Strategy - 13255

    SciTech Connect (OSTI)

    Rogers, Ben C.; Heacker, Fred K.; Shannon, Christopher [Wastren Advantage, Inc., Transuranic Waste Processing Center, 100 WIPP Road, Lenoir City, Tennessee 37771 (United States)] [Wastren Advantage, Inc., Transuranic Waste Processing Center, 100 WIPP Road, Lenoir City, Tennessee 37771 (United States); and others

    2013-07-01T23:59:59.000Z

    The U.S. Department of Energy (DOE) needs to safely and efficiently treat its 'legacy' transuranic (TRU) waste and mixed low-level waste (LLW) from past research and defense activities at the Oak Ridge National Laboratory (ORNL) so that the waste is prepared for safe and secure disposal. The TWPC operates an Environmental Management (EM) waste processing facility on the Oak Ridge Reservation (ORR). The TWPC is classified as a Hazard Category 2, non-reactor nuclear facility. This facility receives, treats, and packages low-level waste and TRU waste stored at various facilities on the ORR for eventual off-site disposal at various DOE sites and commercial facilities. The Remote Handled TRU Waste Sludge held in the Melton Valley Storage Tanks (MVSTs) was produced as a result of the collection, treatment, and storage of liquid radioactive waste originating from the ORNL radiochemical processing and radioisotope production programs. The MVSTs contain most of the associated waste from the Gunite and Associated Tanks (GAAT) in the ORNL's Tank Farms in Bethel Valley and the sludge (SL) and associated waste from the Old Hydro-fracture Facility tanks and other Federal Facility Agreement (FFA) tanks. The SL Processing Facility Build-outs (SL-PFB) Project is integral to the EM cleanup mission at ORNL and is being accelerated by DOE to meet updated regulatory commitments in the Site Treatment Plan. To meet these commitments a Baseline (BL) Change Proposal (BCP) is being submitted to provide continued spending authority as the project re-initiation extends across fiscal year 2012 (FY2012) into fiscal year 2013. Future waste from the ORNL Building 3019 U-233 Disposition project, in the form of U-233 dissolved in nitric acid and water, down-blended with depleted uranyl nitrate solution is also expected to be transferred to the 7856 MVST Annex Facility (formally the Capacity Increase Project (CIP) Tanks) for co-processing with the SL. The SL-PFB project will construct and install the necessary integrated systems to process the accumulated MVST Facilities SL inventory at the TWPC thus enabling safe and effective disposal of the waste. This BCP does not include work to support current MVST Facility Surveillance and Maintenance programs or the ORNL Building 3019 U-233 Disposition project, since they are not currently part of the TWPC prime contract. The purpose of the environmental compliance strategy is to identify the environmental permits and other required regulatory documents necessary for the construction and operation of the SL- PFB at the TWPC, Oak Ridge, TN. The permits and other regulatory documents identified are necessary to comply with the environmental laws and regulations of DOE Orders, and other requirements documented in the SL-PFB, Safety Design Strategy (SDS), SL-A-AD-002, R0 draft, and the Systems, Function and Requirements Document (SFRD), SL-X-AD-002, R1 draft. This compliance strategy is considered a 'living strategy' and it is anticipated that it will be revised as design progresses and more detail is known. The design basis on which this environmental permitting and compliance strategy is based is the Wastren Advantage, Inc., (WAI), TWPC, SL-PFB (WAI-BL-B.01.06) baseline. (authors)

  5. Waste Management Effluent Treatment Facility: Phase I. CAC basic data

    SciTech Connect (OSTI)

    Gemar, D.W.; O'Leary, C.D.

    1984-03-23T23:59:59.000Z

    In order to expedite design and construction of the Waste Management Effluent Treatment Facility (WMETF), the project has been divided into two phases. Phase I consists of four storage basins and the associated transfer lines, diversion boxes, and control rooms. The design data pertaining to Phase I of the WMETF project are presented together with general background information and objectives for both phases. The project will provide means to store and decontaminate wastewater streams that are currently discharged to the seepage basins in F Area and H Area. This currently includes both routine process flows sent directly to the seepage basins and diversions of contaminated cooling water or storm water runoff that are stored in the retention basins before being pumped to the seepage basins.

  6. Greater Green River Basin Production Improvement Project

    SciTech Connect (OSTI)

    DeJarnett, B.B.; Lim, F.H.; Calogero, D.

    1997-10-01T23:59:59.000Z

    The Greater Green River Basin (GGRB) of Wyoming has produced abundant oil and gas out of multiple reservoirs for over 60 years, and large quantities of gas remain untapped in tight gas sandstone reservoirs. Even though GGRB production has been established in formations from the Paleozoic to the Tertiary, recent activity has focused on several Cretaceous reservoirs. Two of these formations, the Ahnond and the Frontier Formations, have been classified as tight sands and are prolific producers in the GGRB. The formations typically naturally fractured and have been exploited using conventional well technology. In most cases, hydraulic fracture treatments must be performed when completing these wells to to increase gas production rates to economic levels. The objectives of the GGRB production improvement project were to apply the concept of horizontal and directional drilling to the Second Frontier Formation on the western flank of the Rock Springs Uplift and to compare production improvements by drilling, completing, and testing vertical, horizontal and directionally-drilled wellbores at a common site.

  7. International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry

    E-Print Network [OSTI]

    Hasanbeigi, Ali

    2013-01-01T23:59:59.000Z

    oil Tire chips Solvents Impregnated sawdust and solvents Solvents Sludgeoil ? 13 percent solvents ? 34 percent plastics (sludge

  8. urricane activity in the Atlantic basin increased

    E-Print Network [OSTI]

    with levels in the 1970s and 1980s. For example, the accumulated cyclone energy (ACE) index in the Atlantic of disturbances. Bottom: annual number (Aug­Oct) of North Atlantic basin hurricanes (1980­2005). See figures 2, is a crucial question for the future outlook of hurricane activity in the basin. It is difficult to distinguish

  9. The State of the Columbia River Basin

    E-Print Network [OSTI]

    the Council to serve as a comprehensive planning agency for energy policy and fish and wildlife policy in the Columbia River Basin and to inform the public about energy and fish and wildlife issues and involve Energy, Fish, Wildlife: The State of the Columbia River Basin, 2013

  10. 6, 839877, 2006 Mexico City basin

    E-Print Network [OSTI]

    Boyer, Edmond

    emitters of air pollutants leading to negative health effects and environmental degradation. The rate altitude basin with air pollutant concentrations above the health limits most days of the year. A mesoscale-dimensional wind patterns in25 the basin and found that the sea-breeze transports the polluted air mass up the moun

  11. Oil migration pattern in the Sirte Basin

    SciTech Connect (OSTI)

    Roohi, M.; Aburawi, R.M. [Waha Oil Co., Tripoli (Libyan Arab Jamahiriya)

    1995-08-01T23:59:59.000Z

    Sirte Basin is an asymmetrical cratonic basin, situated in the north-central part of Libya. It covers an area of over 350,000km{sup 2} and is one of the most prolific oil-producing basins in the world. Sirte Basin is divided into large NW-SE trending sub-parallel platforms and troughs bounded by deep seated syndepositional normal faults. A very unique combination of thick sediments with rich source rocks in the troughs vs. thinner sediments with prolific reservoir rocks on the platforms accounts for the productivity of the basin. Analysis of oil migration pattern in the Sirte Basin will certainly help to discover the remaining reserves, and this can only be achieved if the important parameter of structural configuration of the basin at the time of oil migration is known. The present paper is an attempt to analyse the time of oil migration, to define the structural picture of the 4 Basin during the time of migration and to delineate the most probable connecting routes between the hydrocarbon kitchens and the oil fields.

  12. Sedimentary basins of the late Mesozoic extensional

    E-Print Network [OSTI]

    Johnson, Cari

    17 Sedimentary basins of the late Mesozoic extensional domain of China and Mongolia S.A. Graham,* T Mongolia was extended during the Late Jurassic and Early Cretaceous. As noted by various authors (Li et al in southern Mongolia (Lamb and Badarch, 1997), a crushed late Paleozoic flysch basin along the China­Mongolia

  13. Tar-free fuel gas production from high temperature pyrolysis of sewage sludge

    SciTech Connect (OSTI)

    Zhang, Leguan; Xiao, Bo; Hu, Zhiquan; Liu, Shiming, E-mail: Zhangping101@yeah.net; Cheng, Gong; He, Piwen; Sun, Lei

    2014-01-15T23:59:59.000Z

    Highlights: • High temperature pyrolysis of sewage sludge was efficient for producing tar-free fuel gas. • Complete tar removal and volatile matter release were at elevated temperature of 1300 °C. • Sewage sludge was converted to residual solid with high ash content. • 72.60% of energy conversion efficiency for gas production in high temperature pyrolysis. • Investment and costing for tar cleaning were reduced. - Abstract: Pyrolysis of sewage sludge was studied in a free-fall reactor at 1000–1400 °C. The results showed that the volatile matter in the sludge could be completely released to gaseous product at 1300 °C. The high temperature was in favor of H{sub 2} and CO in the produced gas. However, the low heating value (LHV) of the gas decreased from 15.68 MJ/N m{sup 3} to 9.10 MJ/N m{sup 3} with temperature increasing from 1000 °C to 1400 °C. The obtained residual solid was characterized by high ash content. The energy balance indicated that the most heating value in the sludge was in the gaseous product.

  14. Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)

    SciTech Connect (OSTI)

    Crawford, C. L.; Diprete, D. P.

    2012-12-17T23:59:59.000Z

    The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. Twenty-seven radionuclides have been identified as reportable for DWPF SB7b. Each of these radionuclides has a half-life greater than ten years and contributes more than 0.01% of the radioactivity on a Curie basis at some point from production through the 1100 year period between 2015 and 3115. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100- year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. The radionuclide measurements made for SB7b are the most extensive conducted to date. Some method development/refinement occurred during the conduct of these measurements, leading to lower detection limits and more accurate measurement of some isotopes than was previously possible.

  15. ANAEROBIC BIOLOGICAL TREATMENT OF IN-SITU RETORT WATER

    E-Print Network [OSTI]

    Ossio, Edmundo

    2012-01-01T23:59:59.000Z

    29,000 mg/1 nil a Source of sludge: City of Richmond WaterYen assessed the activated sludge process for the treatmentstudies using a digested sludge seed from a municipal

  16. Eect of sludge-processing mode, soil texture and soil pH on metal mobility in undisturbed soil columns under accelerated loading

    E-Print Network [OSTI]

    Walter, M.Todd

    Eect of sludge-processing mode, soil texture and soil pH on metal mobility in undisturbed soil 8 September 1999 Abstract The eect of sludge processing (digested dewatered, pelletized, alkaline (Lamellic Hapludalf), at initial pH levels of 5 and 7. Sludges were applied during four accelerated cropping

  17. Geology of Alabama's Black Warrior Basin

    SciTech Connect (OSTI)

    Mancini, E.A.; Bearden, B.L.; Holmes, J.W.; Shepard, B.K.

    1983-01-17T23:59:59.000Z

    The Black Warrior basin of northwestern Alabama continues to be an exciting area for oil and gas exploration. Several potential pay zones and a variety of petroleum traps in the basin resulted in a large number of successful test wells, helping to make the basin one of the more attractive areas for continued exploration in the US. The Upper Mississippian sandstone reservoirs in the Black Warrior basin are the primary exploration targets, with the Carter and Lewis sandstones being the most prolific producers. These sanstones exhibit considerable lateral and vertical variability and no apparent regional trends for porosity and permeability development. Determining the depositional environments of the Carter and Lewis sandstones should enhance petroleum exploration in the basin by helping to identify reservoir geometry, areal extent, and quality. To date, the Carter sandstones has produced more than 700,000 bbl of oil and 100 billion CR of gas; the Lewis sandstone, over 5000 bbl of oil and 12 billion CF of gas.

  18. Evaluation of Poly--hydroxybutyrate in activated sludge during feast/famine cycle Fadi Zelhof, Mohammad Tajparast, Dominic Frigon

    E-Print Network [OSTI]

    Barthelat, Francois

    Evaluation of Poly--hydroxybutyrate in activated sludge during feast/famine cycle Fadi Zelhof in an activated sludge reactor. Complete the initial set-up of the reactor by reaching steady state conditions fuels Lower heat of combustion Other bulk chemicals Cosmetics Removes facial oils Material industry

  19. VENTURA BASIN LOS ANGELES BASIN CENTRAL COASTAL BASIN W Y T

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page onYou are now leaving Energy.gov You are now leaving Energy.gov YouKizildere IRaghuraji Agro IndustriesTownDells,1Stocks Nov-14TotalTheE. Great Basin Oil and Gas Fields 2004VENTURA

  20. Verification Of The Defense Waste Processing Facility's (DWPF) Process Digestion Methods For The Sludge Batch 8 Qualification Sample

    SciTech Connect (OSTI)

    Click, D. R.; Edwards, T. B.; Wiedenman, B. J.; Brown, L. W.

    2013-03-18T23:59:59.000Z

    This report contains the results and comparison of data generated from inductively coupled plasma – atomic emission spectroscopy (ICP-AES) analysis of Aqua Regia (AR), Sodium Peroxide/Sodium Hydroxide Fusion Dissolution (PF) and Cold Chem (CC) method digestions and Cold Vapor Atomic Absorption analysis of Hg digestions from the DWPF Hg digestion method of Sludge Batch 8 (SB8) Sludge Receipt and Adjustment Tank (SRAT) Receipt and SB8 SRAT Product samples. The SB8 SRAT Receipt and SB8 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB8 Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 7b (SB7b), to form the SB8 Blend composition.

  1. Research on jet mixing of settled sludges in nuclear waste tanks at Hanford and other DOE sites: A historical perspective

    SciTech Connect (OSTI)

    Powell, M.R.; Onishi, Y.; Shekarriz, R.

    1997-09-01T23:59:59.000Z

    Jet mixer pumps will be used in the Hanford Site double-shell tanks to mobilize and mix the settled solids layer (sludge) with the tank supernatant liquid. Predicting the performance of the jet mixer pumps has been the subject of analysis and testing at Hanford and other U.S. Department of Energy (DOE) waste sites. One important aspect of mixer pump performance is sludge mobilization. The research that correlates mixer pump design and operation with the extent of sludge mobilization is the subject of this report. Sludge mobilization tests have been conducted in tanks ranging from 1/25-scale (3 ft-diameter) to full scale have been conducted at Hanford and other DOE sites over the past 20 years. These tests are described in Sections 3.0 and 4.0 of this report. The computational modeling of sludge mobilization and mixing that has been performed at Hanford is discussed in Section 5.0.

  2. F- and H-Area Sewage Sludge Application Sites Groundwater Monitoring Report: Third quarter 1993

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    Samples from the four wells at the F-Area Sewage Sludge Application Site (FSS wells) and the three wells at the H-Area Sewage Sludge Application Site (HSS wells) are analyzed quarterly for constituents as required by South Carolina Department of Health and Environmental Control Construction Permit 12,076 and, as requested, for other constituents as part of the Savannah River Site Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals, also are required by the permit. Currently, iron, lead, and manganese are the only permit-required analytes that exceed standards at the F- and H-Area Sewage Sludge Application Sites. Tritium and aluminum are the nonpermit constituents exceeding standards. Other constituents have exceeded standards at this site previously, but only sporadically.

  3. Phase chemistry and radionuclide retention of high level radioactive waste tank sludges

    SciTech Connect (OSTI)

    KRUMHANSL,JAMES L.; BRADY,PATRICK V.; ZHANG,PENGCHU; ARTHUR,SARA E.; HUTCHERSON,SHEILA K.; LIU,J.; QIAN,M.; ANDERSON,HOWARD L.

    2000-05-19T23:59:59.000Z

    The US Department of Energy (DOE) has millions of gallons of high level nuclear waste stored in underground tanks at Hanford, Washington and Savannah River, South Carolina. These tanks will eventually be emptied and decommissioned. This will leave a residue of sludge adhering to the interior tank surfaces that may contaminate groundwaters with radionuclides and RCRA metals. Experimentation on such sludges is both dangerous and prohibitively expensive so there is a great advantage to developing artificial sludges. The US DOE Environmental Management Science Program (EMSP) has funded a program to investigate the feasibility of developing such materials. The following text reports on the success of this program, and suggests that much of the radioisotope inventory left in a tank will not move out into the surrounding environment. Ultimately, such studies may play a significant role in developing safe and cost effective tank closure strategies.

  4. Analysis of Sludge Batch 3 (Macrobatch4) DWPF Pour Stream Glass Sample for Canister s02312

    SciTech Connect (OSTI)

    Bannochie, C

    2005-09-01T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 3 (SB3), Macrobatch 4 (MB4) in March 2004 as part of Sludge Receipt and Adjustment Tank (SRAT) Batch 272. Sludge Batch 3 is a blend of the contents Tank 40 remaining from Sludge Batch 2 (SB2), the sludge that was transferred to Tank 40 from Tank 51 and Canyon Np solution additions made directly to Tank 40. The sludge transferred from Tank 51 contained sludges from Tanks 7, 18 and 19 along with precipitated solutions of U, Pu/Gd and Am/Cm from the F and H Canyons. The blend of sludge from Tank 51, Tank 40, and the Canyon additions defines SB3 (or MB4). The sludge slurry is received into the DWPF Chemical Processing Cell (CPC) and is processed through the SRAT and Slurry Mix Evaporator (SME) Tank and fed to the melter. During the processing of each sludge batch, the DWPF is required to take at least one glass sample. This glass sample is taken to meet the objectives of the Glass Product Control Program and complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. Two glass samples were obtained while pouring Canisters S02312 and S02315 which were sent to the Savannah River National Laboratory's (SRNL) Shielded Cells Facility. Sample S02312 was designated for analysis, while sample S02315 was designated for archival storage. This report contains the visual observations of the as-received glass sample, results for the density, chemical composition, the Product Consistency Test (PCT) and the calculated and measured radionuclide results needed for the Production Record for Canister S02312. The following conclusions were drawn from the examination of this DWPF pour stream glass sample: (1) The glass sample taken during the filling of DWPF Canister S02312 weighed 41.69 g and was generally dark and reflective. (2) Minor inclusions, on the order of 1 {micro}m in size, of noble metals were seen in the glass via contained scanning electron microscopy and confirmed from their x-ray fluorescence spectra. (3) The results for the composition of glass sample S02312, except for U, are in reasonable agreement (15% or better) with the DWPF SME Batch 319 results, the SME batch being fed to the melter when the sample was collected. (4) The calculated waste dilution factor (WDF) was 2.19. The measured values of the radionuclides and noble metals in the glass sample generally corresponded well with the calculated values determined using sludge slurry results from Reference 9 and the WDF. (5) The noble metal content of the glass indicates that the noble metals are largely swept from the melter with the glass based upon the noble metals analyzed in the glass and those predicted in the sludge from the WDF. (6) Comparison of the noble metal results for the two digestion methods (mixed acid and alkali fusion) indicates that the alkali fusion method is preferred for the determination of noble metals in glass. (7) The PCT results for the glass (normalized release of B: 1.09 g/L, Na: 1.03 g/L, and Li: 0.94 g/L) indicate that it meets the waste acceptance criterion for durability. (8) The normalized release rates for the measured radionuclides were less than those for the major soluble elements in the waste (B, Na, and Li) with the exception of Tc-99 which was released at a rate similar to that the soluble elements in the leachate. (9) The measured density of the glass was 2.58 {+-} 0.11 g/cm{sup 3}.

  5. Low-Temperature, Vacuum-Aided Thermal Desorption Studies on a Simulated Organic Sludge Waste

    SciTech Connect (OSTI)

    R. K. Farnsworth; D. R. Peterman; Gary L. Anderson; T. G. Garn

    2002-12-01T23:59:59.000Z

    This report describes an initial set of small scale lab tests conducted on surrogate waste materials to investigate mass release behavior of volatile organics (VOC’s) from a solidified liquid organic sludge matrix under vacuumaided, low-temperature thermal desorption conditions. Low temperature thermal desorption is being considered as a potential processing technology alternative to incineration, to remove gas generation limitations affecting the transportation of transuranic (TRU) contaminated organic sludge wastes to a designated off-site repository (i.e., the Waste Isolation Pilot Plant). The lab-scale tests provide initial exploratory level information on temperature profiles and rates of volatile organic desorption for a range of initial VOC/oil liquid mixture concentrations in a calcium silicate matrix, under low temperature heating and vacuum boundary conditions that are representative of potentially desirable “in-drum desorption” conditions. The results of these tests indicate that reduced operating pressures have a potential for significantly enhancing the rate of thermal desorption experienced from a liquid organic/oil solidified “sludge” waste. Furthermore, the results indicate that in-drum thermal desorption can be performed on organic sludge wastes, at reduced pressures, while maintaining an operating temperature sufficiently low to prevent destruction of the waste drum packaging materials (confinement) surrounding the waste. The results also indicate that VOC release behavior/rates in the vacuum thermal desorption process cannot be represented by a simple liquid-liquid mass-diffusion model, since overall mass release rates observed are generally two orders of magnitude greater than predicted by simple liquid-liquid mass diffusion. This is partially attributed to the effects of the transient temperature profiles within the sludge during heat up; however, the primary cause is thought to be micro boiling of the volatile organics within the simulated sludge. Micro boiling of VOC’s would be expected to occur in localized volumes within the organic sludge where temperatures exceed the volatile organic saturation temperature sufficiently to form vapor bubbles. Further model based evaluations reflecting the transient temperatures, local boiling, and subsequent vapor in liquid/sludge transport conditions are needed, with supporting controlled testing of the vacuum-aided thermal desorption process at small and full-scale conditions in order to fully develop this process.

  6. Influence of rainfall on the retention of sludge trace metals by the leaves of forage crops

    E-Print Network [OSTI]

    Jones, Stephen Grady

    1977-01-01T23:59:59.000Z

    INFLUENCE OF RAINFALL ON THE RETENTION OF SLUDGE TRACE METALS BY THE LEAVES OF FORAGE CROPS A Thesis STEPHEN GRADY JONES Submitted to the Graduate College of Texas A&M University in partial fulfillment of the requirement for the degree... of MASTER OF SCIENCE December 1977 Major Subject: Soil Science INFLUENCE OF RAINFALL ON THE RETENTION OF SLUDGE TRACE MFTALS BY THE LEAVES OF FORAGE CROPS A Thesis by STEPHEN GRADY JONES Approved a to style and content by: 1 (Chairman of Committee...

  7. Increased CPC batch size study for Tank 42 sludge in the Defense Waste Processing Facility

    SciTech Connect (OSTI)

    Daniel, W.E.

    2000-01-06T23:59:59.000Z

    A series of experiments have been completed at TNX for the sludge-only REDOX adjusted flowsheet using Tank 42 sludge simulant in response to the Technical Task Request HLW/DWPT/TTR-980013 to increase CPC batch sizes. By increasing the initial SRAT batch size, a melter feed batch at greater waste solids concentration can be prepared and thus increase melter output per batch by about one canister. The increased throughput would allow DWPF to dispose of more waste in a given time period thus shortening the overall campaign.

  8. SLUDGE BATCH 6/TANK 40 SIMULANT CHEMICAL PROCESS CELL SIMULATIONS

    SciTech Connect (OSTI)

    Koopman, David

    2010-04-28T23:59:59.000Z

    Phase III simulant flowsheet testing was completed using the latest composition estimates for SB6/Tank 40 feed to DWPF. The goals of the testing were to determine reasonable operating conditions and assumptions for the startup of SB6 processing in the DWPF. Testing covered the region from 102-159% of the current DWPF stoichiometric acid equation. Nitrite ion concentration was reduced to 90 mg/kg in the SRAT product of the lowest acid run. The 159% acid run reached 60% of the DWPF Sludge Receipt and Adjustment Tank (SRAT) limit of 0.65 lb H2/hr, and then sporadically exceeded the DWPF Slurry Mix Evaporator (SME) limit of 0.223 lb H2/hr. Hydrogen generation rates peaked at 112% of the SME limit, but higher than targeted wt% total solids levels may have been partially responsible for rates seen. A stoichiometric factor of 120% met both objectives. A processing window for SB6 exists from 102% to something close to 159% based on the simulant results. An initial recommendation for SB6 processing is at 115-120% of the current DWPF stoichiometric acid equation. The addition of simulated Actinide Removal Process (ARP) and Modular Caustic Side Solvent Extraction Unit (MCU) streams to the SRAT cycle had no apparent impact on the preferred stoichiometric factor. Hydrogen generation occurred continuously after acid addition in three of the four tests. The three runs at 120%, 118.4% with ARP/MCU, and 159% stoichiometry were all still producing around 0.1 lb hydrogen/hr at DWPF scale after 36 hours of boiling in the SRAT. The 120% acid run reached 23% of the SRAT limit and 37% of the SME limit. Conversely, nitrous oxide generation was subdued compared to previous sludge batches, staying below 29 lb/hr in all four tests or about a fourth as much as in comparable SB4 testing. Two processing issues, identified during SB6 Phase II flowsheet testing and qualification simulant testing, were monitored during Phase III. Mercury material balance closure was impacted by acid stoichiometry, and significant mercury was not accounted for in the highest acid run. Coalescence of elemental mercury droplets in the mercury water wash tank (MWWT) appeared to degrade with increasing stoichiometry. Observations were made of mercury scale formation in the SRAT condenser and MWWT. A tacky mercury amalgam with Rh, Pd, and Cu, plus some Ru and Ca formed on the impeller at 159% acid. It contained a significant fraction of the available Pd, Cu, and Rh as well as about 25% of the total mercury charged. Free (elemental) mercury was found in all of the SME products. Ammonia scrubbers were used during the tests to capture off-gas ammonia for material balance purposes. Significant ammonium ion formation was again observed during the SRAT cycle, and ammonia gas entered the off-gas as the pH rose during boiling. Ammonium ion production was lower than in the SB6 Phase II and the qualification simulant testing. Similar ammonium ion formation was seen in the ARP/MCU simulation as in the 120% flowsheet run. A slightly higher pH caused most of the ammonium to vaporize and collect in the ammonia scrubber reflux solution. Two periods of foaminess were noted. Neither required additional antifoam to control the foam growth. A steady foam layer formed during reflux in the 120% acid run. It was about an inch thick, but was 2-3 times more volume of bubbles than is typically seen during reflux. A similar foam layer also was seen during caustic boiling of the simulant during the ARP addition. While frequently seen with the radioactive sludge, foaminess during caustic boiling with simulants has been relatively rare. Two further flowsheet tests were performed and will be documented separately. One test was to evaluate the impact of process conditions that match current DWPF operation (lower rates). The second test was to evaluate the impact of SRAT/SME processing on the rheology of a modified Phase III simulant that had been made five times more viscous using ultrasonication.

  9. Mid-Continent basin: a reappraisal

    SciTech Connect (OSTI)

    Berg, J.R.

    1983-08-01T23:59:59.000Z

    One of the largest unevaluated basins in the Mid-Continent is the Salina basin in Kansas and its extension into eastern Nebraska. The purpose of this study is to update all older data, reconstruct new maps, and reappraise the potential for further exploration. The last comprehensive publications on the area were in 1948 and 1956. The Salina basin includes 12,700 mi/sup 2/ (33,000 km/sup 2/) in north-central Kansas, and approximately 7000 mi/sup 2/ (18,000 km/sup 2/) in east-central Nebraska. The basin is delineated by the zero isopach of Mississippian rocks bordering the basin. The Central Kansas uplift borders the basin on the southwest and Nemaha ridge on the east; the southern limit is an ill-defined saddle in the vicinity of T17S. Boundaries of the Nebraska basin are less well defined, but the axis of the basin trends directly north from the Kansas border along the boundary of Ts10 and 11W, to 41/sup 0/N lat., and then bifurcates to the northwest toward the Siouxiana arch and northeast for an unknown distance. Conventional structure maps have been constructed on several horizons, and a series of cross sections depicts anomalous structures. Recent gravity, magnetic, and seismic reflection profiling also provide information on basement tectonics which may influence structures in the younger sediments. Basement depth ranges from 600 ft (180 m) on the northeast Nemaha ridge boundary of the basin, to a depth of 4750 ft (1450 m) or -3000 ft (-915 m) below sea-level datum in Jewell County; therefore, there may be an approximate total of 10,000 mi/sup 3/ (42,000 km/sup 3/ of sediments for future exploration.

  10. Delaware Basin Monitoring Annual Report

    SciTech Connect (OSTI)

    Washington Regulatory and Environmental Services; Washington TRU Solutions LLC

    2003-09-30T23:59:59.000Z

    The Delaware Basin Drilling Surveillance Program (DBDSP) is designed to monitor drilling activities in the vicinity of the Waste Isolation Pilot Plant (WIPP). This program is based on Environmental Protection Agency (EPA) requirements. The EPA environmental standards for the management and disposal of transuranic (TRU) radioactive waste are codified in 40 CFR Part 191 (EPA 1993). Subparts B and C of the standard address the disposal of radioactive waste. The standard requires the Department of Energy (DOE) to demonstrate the expected performance of the disposal system using a probabilistic risk assessment or performance assessment (PA). This PA must show that the expected repository performance will not release radioactive material above limits set by the EPA's standard. This assessment must include the consideration of inadvertent drilling into the repository at some future time.

  11. Delaware Basin Monitoring Annual Report

    SciTech Connect (OSTI)

    Washington Regulatory and Environmental Services; Washington TRU Solutions LLC

    2005-09-30T23:59:59.000Z

    The Delaware Basin Drilling Surveillance Program (DBDSP) is designed to monitor drilling activities in the vicinity of the Waste Isolation Pilot Plant (WIPP). This program is based on Environmental Protection Agency (EPA) requirements. The EPA environmental standards for the management and disposal of transuranic (TRU) radioactive waste are codified in 40 CFR Part 191 (EPA 1993). Subparts B and C of the standard address the disposal of radioactive waste. The standard requires the Department of Energy (DOE) to demonstrate the expected performance of the disposal system using a probabilistic risk assessment or performance assessment (PA). This PA must show that the expected repository performance will not release radioactive material above limits set by the EPA's standard. This assessment must include the consideration of inadvertent drilling into the repository at some future time.

  12. Delaware Basin Monitoring Annual Report

    SciTech Connect (OSTI)

    Washington Regulatory and Environmental Services; Washington TRU Solutions LLC

    2004-09-30T23:59:59.000Z

    The Delaware Basin Drilling Surveillance Program (DBDSP) is designed to monitor drilling activities in the vicinity of the Waste Isolation Pilot Plant (WIPP). This program is based on Environmental Protection Agency (EPA) requirements. The EPA environmental standards for the management and disposal of transuranic (TRU) radioactive waste are codified in 40 CFR Part 191 (EPA 1993). Subparts B and C of the standard address the disposal of radioactive waste. The standard requires the Department of Energy (DOE) to demonstrate the expected performance of the disposal system using a probabilistic risk assessment or performance assessment (PA). This PA must show that the expected repository performance will not release radioactive material above limits set by the EPA's standard. This assessment must include the consideration of inadvertent drilling into the repository at some future time.

  13. activated sludge characteristics: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental impacts of...

  14. activated sludge unit: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental impacts of...

  15. activated sludge steuerung: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  16. activated sludge biofac: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  17. acclimated activated sludge: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  18. activated sludge deflocculation: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  19. activated sewage sludge: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental impacts...

  20. activated sludge aeration: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  1. activated sludge removing: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  2. activated sludge flocculation: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  3. activated sludge exposed: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  4. aerated active sludge: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  5. activated sludge solubilisation: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  6. activated sludge treating: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  7. activated sludge reactor: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  8. aeration activated sludge: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  9. activated sludge process: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  10. anaerobic sludge blanket: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental impacts...

  11. activated sludge flocs: Topics by E-print Network

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

    of each treatment process, according to the Egyptian conditions, is evaluated. The Life cycle assessment methodology was applied to assess and compare the environmental...

  12. activated sludge microorganisms: Topics by E-print Network

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

    Samples of wastewater were collected from Aslogy wastewater treatment plant, Zagazig, Egypt. The using bacteria embed on granular delivered as powder. Two runs of experimental...

  13. activated sludge biomass: Topics by E-print Network

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

    the wastewater treatment process. Its conventional disposal methods include incineration, landfill, and agricultural land application. As populations grow, the (more) Gong,...

  14. ANALYSIS OF SLUDGE BATCH 4 (MACROBATCH 5) FOR CANISTER S02902 AND SLUDGE BATCH 5 (MACROBATCH 6) FOR CANISTER S03317 DWPF POUR STREAM GLASS SAMPLES

    SciTech Connect (OSTI)

    Reigel, M.; Bibler, N.

    2010-10-04T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 4 (SB4), Macrobatch 5 (MB5) on May 29, 2007. Sludge Batch 4 was a blend of the heel of Tank 40 from Sludge Batch 3 (SB3) and SB4 material qualified in Tank 51. On November 28, 2008, DWPF began processing Sludge Batch 5 (SB5) from Tank 40 which is a blend of the heel of Tank 40 from SB4, SB5 material qualified in Tank 51 and H-Canyon Pu and Np transfers. SB4 was processed using Frit 510 and SB5 used Frit 418. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. During the processing of SB4 and SB5, glass samples were obtained during the pouring of canisters S02902 and S03317, respectively. The samples were transferred to the Savannah River National Laboratory (SRNL) where they were analyzed (durability, chemical and radionuclide composition). The following observations and conclusions are drawn from the analytical results provided in this report: (1) The sum of the oxides for the chemical composition of both the SB4 and SB5 pour stream glasses is within the Product Composition Control System (PCCS) acceptance limits (95 {le} sum of oxides {le} 105). (2) The calculated Sludge Dilution Factor (SDF) for SB4 is 2.52. The measured radionuclide content is in good agreement with the calculated values from the dried sludge results from the SB4 Waste Acceptance Production Specification (WAPS) sample (References 1 and 19). (3) The calculated SDF for SB5 is 2.60. The measured radionuclide content is in good agreement with the calculated values from the dried sludge results from the SB5 WAPS sample (References 2 and 20). (4) Scanning Electron Microscopy (SEM) analysis shows there are noble metal inclusions, primarily ruthenium, present in both pour stream samples. (5) The Product Consistency Test (PCT) results show that the SB4 pour stream glass meets the waste acceptance criteria for durability with a normalized boron release of 0.67 g/L which is an order of magnitude lower than the Environmental Assessment (EA) glass. (6) The PCT results show that the SB5 pour stream glass meets the waste acceptance criteria for durability with a normalized boron release of 0.72 g/ which is an order of magnitude lower than the EA glass. (7) The density of the SB4 glass is 2.5 g/cm{sup 3}. (8) The density of the SB5 glass is 2.6 g/cm{sup 3}.

  15. Death of a carbonate basin: The Niagara-Salina transition in the Michigan basin

    SciTech Connect (OSTI)

    Leibold, A.W.; Howell, P.D. (Univ. of Michigan, Ann Arbor (United States))

    1991-03-01T23:59:59.000Z

    The A-O Carbonate in the Michigan basin comprises a sequence of laminated calcite/anhydrite layers intercalated with bedded halite at the transition between normal marine Niagaran carbonates and lower Salina Group evaporites. The carbonate/anhydrite interbeds represent freshing events during initial evaporative concentration of the Michigan basin. Recent drilling in the Michigan basin delineates two distinct regions of A-O Carbonate development: a 5 to 10 m thick sequence of six 'laminites' found throughout most of the western and northern basin and a 10 to 25 m thick sequence in the southeastern basin containing both thicker 'laminates' and thicker salt interbeds. Additionally, potash deposits of the overlying A-1 evaporite unit are restricted to the northern and western basin regions. The distribution of evaporite facies in these two regions is adequately explained by a source of basin recharge in the southeast-perhaps the 'Clinton Inlet' of earlier workers. This situation suggest either that: (1) the source of basin recharge is alternately supplying preconcentrated brine and more normal marine water, or (2) that the basin received at least two distinct sources of water during A-O deposition.

  16. Assessment of undiscovered carboniferous coal-bed gas resources of the Appalachian Basin and Black Warrior Basin Provinces, 2002

    SciTech Connect (OSTI)

    Milici, R.C.; Hatch, J.R.

    2004-09-15T23:59:59.000Z

    Coalbed methane (CBM) occurs in coal beds of Mississippian and Pennsylvanian (Carboniferous) age in the Appalachian basin, which extends almost continuously from New York to Alabama. In general, the basin includes three structural subbasins: the Dunkard basin in Pennsylvania, Ohio, and northern West Virginia; the Pocahontas basin in southern West Virginia, eastern Kentucky, and southwestern Virginia; and the Black Warrior basin in Alabama and Mississippi. For assessment purposes, the Appalachian basin was divided into two assessment provinces: the Appalachian Basin Province from New York to Alabama, and the Black Warrior Basin Province in Alabama and Mississippi. By far, most of the coalbed methane produced in the entire Appalachian basin has come from the Black Warrior Basin Province. 8 refs., 1 fig., 1 tab.

  17. Progress Update: H4 Basin Concrete Pour

    ScienceCinema (OSTI)

    None

    2012-06-14T23:59:59.000Z

    The Recovery Act funded project in the H area basin. A concrete ditch built longer than half a mile to prevent contaminated water from expanding and to reduce the footprint on the environment.

  18. September 2012 BASIN RESEARCH AND ENERGY GEOLOGY

    E-Print Network [OSTI]

    Suzuki, Masatsugu

    September 2012 BASIN RESEARCH AND ENERGY GEOLOGY STATE UNIVERSITY OF NEW YORK at BINGHAMTON research programs in geochemistry, sedimentary geology, or Earth surface processes with the potential the position, visit the Geological Sciences and Environmental Studies website (www.geology

  19. River Basins Advisory Commissions (South Carolina)

    Broader source: Energy.gov [DOE]

    The Catawba/Wateree and Yadkin/Pee Dee River Basins Advisory Commissions are permanent public bodies jointly established by North and South Carolina. The commissions are responsible for assessing...

  20. Flathead Basin Commission Act of 1983 (Montana)

    Broader source: Energy.gov [DOE]

    This Act establishes the Flathead Basin Commission, the purpose of which is to protect the Flathead Lake aquatic environment, its waters, and surrounding lands and natural resources. The Commission...

  1. Petroleum potential of the Libyan sedimentary basins

    SciTech Connect (OSTI)

    Hammuda, O.S.; Sbeta, A.M.

    1988-08-01T23:59:59.000Z

    Contrary to prevailing opinion, all Libyan sedimentary basins and the Al-Jabal Al-Akhdar platform contain prolific petroleum accumulations with very high prospectivity. A systematic review of the types of traps and pays in this central part of the southern Mediterranean province reveals great variability in reservoir and source rock characteristics. The reservoir rocks are of almost all geologic ages. The thick source rock sequences also vary in nature and organic content. The organic-rich facies have accumulated in intracratonic and passive margin basins or in marginal seas. Most of the oil discovered thus far in these basins is found in large structural traps. Future discoveries of stratigraphic traps or small structural traps will require intensified efforts and detailed studies using up-to-date multidisciplinary techniques in sedimentary tectonics, biostratigraphic facies analysis, and geochemical prospecting in order to develop a better understanding of these basins, thus improving their prospectivity.

  2. K-Basins S/RIDS

    SciTech Connect (OSTI)

    Watson, D.J.

    1997-08-01T23:59:59.000Z

    The Standards/Requirements Identification Document (S/RID) is a list of the Environmental, Safety, and Health (ES{ampersand}H) and Safeguards and Security (SAS) standards/requirements applicable to the K Basins facility.

  3. The Uinta Basin Case Robert J. Bayer

    E-Print Network [OSTI]

    Utah, University of

    Overburden Tailings Oil Shale Mining Open Pit Underground Ex situ extraction Ex situ thermal conversion EIS for Oil Sands and Oil Shale Ongoing concerns with Basin-wide air quality Wildlife and wildlife

  4. K-Basins S/RIDS

    SciTech Connect (OSTI)

    Watson, D.J.

    1995-09-22T23:59:59.000Z

    The Standards/Requirements Identification Document(S/RID) is a list of the Environmental, Safety, and Health (ES&H) and Safeguards and Security (SAS) standards/requirements applicable to the K Basins facility

  5. Design and operation of a coal-washery sludge fired 75 t/h steam fluidized bed combustion boiler

    SciTech Connect (OSTI)

    Jiang, X.; Chi, Y.; Yan, J. [and others

    1999-07-01T23:59:59.000Z

    Based upon the coal-washery sludge fluidized bed agglomerating combustion technology developed by Zhejiang University and the design and operation experience accumulated from the 35 t/h stream fluidized bed boilers, a coal-washery sludge fired 75 t/h steam circulating fluidized bed boiler (12 MWe) for cogeneration application was designed. The design features of the boiler can be summarized as follows: (1) Combination of solid particle impact separator (in furnace circulation) and moderate temperature ({approximately}500 C) uniflow cyclone; (2) Low solid circulation rate; (3) Loop-seal for solid particle recirculation; (4) Air duct oil burner for boiler start-up; and (5) Coal-Washery sludge firing or co-firing of coal-washery sludge and coal. The boiler is installed at Dongtan Coal Mine Cogeneration Plant in Shandong Province of China. The daily disposal capacity of coal-washery sludge is over 300 tons. The first trial operation of the boiler was on Dec. 18, 1997. The cogeneration plant has been in commercial operation since May 1998. This boiler is the largest capacity boiler to dispose of coal-washery sludge in China. The successful operation of this boiler has sped up the commercialization process of the coal-washery sludge fluidized bed combustion technology.

  6. Nepheline Formation Study for Sludge Batch 4 (SB4): Phase 1 Experimental Results

    SciTech Connect (OSTI)

    Peeler, D. K.; Edwards, T. B.; Reamer, I.A.; Workman, R. J.

    2005-09-30T23:59:59.000Z

    Although it is well known that the addition of Al{sub 2}O{sub 3} to borosilicate glasses enhances the durability of the waste form (through creation of network-forming tetrahedral Na+-[AlO{sub 4/2}]{sup -} pairs), the combination of high Al{sub 2}O{sub 3} and Na{sub 2}O can lead to the formation of nepheline (NaAlSiO{sub 4})--which can negatively impact durability. Given the projected high concentration of Al{sub 2}O{sub 3} in SB4 (Lilliston 2005) and the potential use of a high Na{sub 2}O based frit to improve melt rate and a high Na{sub 2}O sludge due to settling problems, the potential formation of nepheline in various SB4 systems continues to be assessed. Twelve SB4-based glasses were fabricated and their durabilities (via the Product Consistency Test [PCT]) measured to assess the potential for nepheline formation and its potential negative impact on durability. In terms of ''acceptability'', the results indicate that all of the study glasses produced are acceptable with respect to durability as defined by the PCT (normalized boron release values for all nepheline (NEPH) glasses were much lower than that of the Environmental Assessment (EA) glass (16.695 g/L)). The most durable glass is NEPH-04 (quenched) with a normalized boron release (NL [B]) of 0.61 g/L, while the least durable glass is NEPH-01 centerline canister cooled (ccc) with an NL [B] of 2.47 g/L (based on the measured composition). In terms of predictability, most of the study glasses are predictable by the {Delta}G{sub p} model. Those that are not predictable (i.e., they fall outside of the prediction limits) actually fall below the prediction interval (i.e., they are over predicted by the model) suggesting the model is conservative. The Phase 1 PCT results suggest that for those glasses prone to nepheline formation (using the 0.62 value developed by Li et al. (2003) as a guide), a statistically significant difference in PCT response was observed for the two heat treatments but the impact on durability was of little or no practical concern. When one couples the PCT responses with the X-Ray Diffraction (XRD) results and/or visual observations, one could conclude that the formation of nepheline in these glasses does have a negative impact on durability. However, that impact may be of statistical significance, but the practical impact may not be sufficient to avoid a specific candidate frit for the SB4 glass system. The results of this study not only suggest that the 0.62 value appears to be a reasonable guide to monitor sludge--frit systems with respect to potential nepheline formation, but also that the impact of nepheline, although statistically significant, has little or no practical impact in the SB4 system to durability as measured by the PCT. This latter statement must be qualified to some extent given only two glasses were selected which were actually ''prone to nepheline formation'' based on this general guide and the relatively volume % of nepheline formed based on XRD results ({approx} 0.5 vol%). If the presence of nepheline has no appreciable, adverse impact on durability for the recently revised SB4 systems, then as decisions regarding the viability of the SB4 options and the down select of candidate frits are pursued, little weight will be given to minimizing the likelihood of nepheline and the decisions will be dominated by waste throughput criteria. That is, the frit selection process will not have to consider the impact of nepheline on the ultimate durability of the product and can focus on recommending a frit that when coupled with the sludge can be processed over a waste loading (WL) interval of interest to the Defense Waste Processing Facility (DWPF) with melt rates meeting production expectations.

  7. Late devonian carbon isotope stratigraphy and sea level fluctuations, Canning Basin, Western Australia

    E-Print Network [OSTI]

    Stephens, N P; Sumner, Dawn Y.

    2003-01-01T23:59:59.000Z

    reef, Canning Basin, Western Australia. Palaeontology 43,the Canning Basin, Western Australia. In: Loucks, R.G. ,Canning Basin, Western Australia. Ph.D Thesis, University of

  8. Application of chlorine dioxide as an oilfield facilities treatment fluid

    SciTech Connect (OSTI)

    Romaine, J.; Strawser, T.G.; Knippers, M.L.

    1995-11-01T23:59:59.000Z

    Both mechanical and chemical treatments are used to clean water flood injection distribution systems whose efficiency has been reduced as a result of plugging material such as iron sulfide sludge. Most mechanical treatments rely on uniform line diameter to be effective, while chemical treatments require good contact with the plugging material for efficient removal. This paper describes the design and operation of a new innovative application using chlorine dioxide for the removal of iron sulfide sludge from water flood injection distribution systems. This technology has evolved from the use of chlorine dioxide in well stimulation applications. The use of chlorine dioxide for continuous treatment of injection brines will also be discussed. Exxon USA`s Hartzog Draw facility in Gillette, Wyoming was the site for the application described. 4,500 barrels of chlorine dioxide was pumped in three phases to clean sixty-six miles of the water flood distribution system. Results indicate that chlorine dioxide was effective in cleaning the well guard screens, the injection lines, frac tanks used to collect the treatment fluids and the injection wells.

  9. Fractal analysis of soil water hysteresis as influenced by sewage sludge application

    E-Print Network [OSTI]

    Perfect, Ed

    Fractal analysis of soil water hysteresis as influenced by sewage sludge application G. Ojeda a,, E) and a loamy sand soil (Typic Haplustalf) from central Catalonia (NE Spain) was investigated using fractal analysis. First, we proposed a composite fractal model that covers both the low and high suction regimes

  10. Investigation of EPS Characteristics and their Effects on Waste Activated Sludge Digestion

    E-Print Network [OSTI]

    Mountziaris, T. J.

    Investigation of EPS Characteristics and their Effects on Waste Activated Sludge Digestion Thomas be accomplished through use of aerobic or anaerobic self digestion, but choice of digestion type in practice on digestibility, especially in regards to the composition of extracellular polymeric substances (EPS). Samples

  11. Impact of EPS on Digestion of Waste Activate Sludge Thomas Gostanian

    E-Print Network [OSTI]

    Mountziaris, T. J.

    Impact of EPS on Digestion of Waste Activate Sludge Thomas Gostanian Faculty Mentor: Professor Chul Park, Civil & Environmental Engineering Digestion by bacteria is a widely used method for organic is by either aerobic or anaerobic self-digestion, in which the bacteria consume their own mass. Currently

  12. Selective Leaching of Chromium from Hanford Tank Sludge 241-U-108

    SciTech Connect (OSTI)

    Rapko, Brian M.; Vienna, John D.

    2002-09-09T23:59:59.000Z

    This study evaluated the oxidants permanganate, MnO4-, and peroxynitrite, ONOO-, as selective chromium-leaching agents from washed 241-U-108 tank sludge under varying conditions of hydroxide concentration, temperature, and time. The mass changes and final sludge compositions were evaluated using glass-property models to ascertain the relative impacts of the various oxidative alkaline leach conditions on the amount of borosilicate glass required to immobilize a given amount of washed 241-U-108 Hanford tank sludge. Only permanganate leaching removes sufficient chromium to make the chromium concentration in the oxidatively alkaline leached solids non-limiting. In the absence of added oxidants, continued washing or caustic leaching have no beneficial effects. Peroxynitrite addition reduces the amount of glass required to immobilize a given amount of washed 241-U-108 tank sludge by approximately a factor of two. Depending on the leach conditions and the exact chromium concentration limits, contact with alkaline permanganate solutions reduces the amount of immobilized high-level waste glass by a factor of 10 to 30.

  13. Evaluation of leaching and ecotoxicological properties of sewage sludge-fly ash mixtures

    SciTech Connect (OSTI)

    C.A. Papadimitriou; I. Haritou; P. Samaras; A.I. Zouboulis [Technological Educational Institute of West Macedonia, Kozani (Greece)

    2008-03-15T23:59:59.000Z

    The objectives of this work were the evaluation of sewage sludge stabilization by mixing with fly ash, the examination of the physicochemical properties of the produced materials and their leachates and the assessment of their environmental impact by the evaluation of the ecotoxic characteristics. Different ratios of fly ash and sewage sludge (1:1, 1:2, 1:3, 1:6, and 1:9) were mixed for 48 and 72 h. After mixing, the liquid phase of the produced materials was analyzed for total coliforms and Escherichia coli, while the solid residue was dried and tested for the leaching characteristics by the application of TCLP and EN 12457-2 standard leaching methods. Furthermore, the produced leachates were analyzed for their content of specific metals, while their ecotoxicological characteristics were determined by the use of toxicity bioassays, using the marine photobacterium Vibrio fischeri and the crustacean Daphnia magna. The phytotoxicity of sewage sludge-fly ash mixtures was also determined by utilizing seeds of three higher plants (one monocotyl and two dicotyls). The mixtures exhibited low metal leaching in all cases, while the ecotoxic properties increased with the increase of fly ash/sewage sludge ratio. The phytotoxicity testing showed increased root length growth inhibition.

  14. SULFATE RETENTION IN HIGH LEVEL WASTE SLUDGE BATCH 4 GLASSES: A PRELIMINARY ASSESSMENT

    SciTech Connect (OSTI)

    Fox, K; Tommy Edwards, T; David Peeler, D

    2006-12-11T23:59:59.000Z

    Early projections of the Sludge Batch 4 (SB4) composition predicted relatively high concentrations of alumina (Al{sub 2}O{sub 3}, 23.5 wt%) and sulfate (SO{sub 4}{sup 2-}, 1.2 wt%) in the sludge. A high concentration of Al{sub 2}O{sub 3} in the sludge, combined with Na{sub 2}O additions in the frit, raises the potential for nepheline crystallization in the glass. However, strategic frit development efforts at the Savannah River National Laboratory (SRNL) have shown that frits containing a relatively high concentration of B{sub 2}O{sub 3} can both suppress nepheline crystallization and improve melt rates. A high sulfate concentration is a concern to the DWPF as it can lead to the formation of sulfate inclusions in the glass and/or the formation of a molten, sulfate-rich phase atop the melt pool. To avoid these issues, a sulfate concentration limit of 0.4 wt% SO{sub 4}{sup 2-} in glass was originally set in the Product Composition Control System (PCCS) used at DWPF. It was later shown that this limit could be increased to 0.6 wt% SO{sub 4}{sup 2-} in glass for the Frit 418, Sludge Batch 3 (SB3) system.

  15. Microbial oxygen uptake in sludge as influenced by compost physical parameters1 Ardavan Mohajer1

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    1 Microbial oxygen uptake in sludge as influenced by compost physical parameters1 Ardavan Mohajer1 The wide range of optimal values reported for the physical parameters of compost2 mixtures suggest: compost, biodegradability, respirometry, moisture content, bulking agent to waste22 ratio, particle size

  16. Cone Penetrometer Shear Strength Measurements of Sludge Waste in Tanks 241-AN-101 and 241-AN-106

    SciTech Connect (OSTI)

    Follett, Jordan R.

    2014-03-06T23:59:59.000Z

    This document presents the resulting shear strength profiles for sludge waste in Tanks 241-AN-101 and 241-AN-106, as determined with a full-flow cone penetrometer. Full-flow penetrometer measurements indicate shear strength profiles that increase roughly uniformly with depth. For Tank 241-AN-101, the undrained shear strength was calculated to range from 500 Pa near the sludge surface to roughly 3,300 Pa at 15 inches above the tank bottom. For 241-AN-106, the undrained shear strength was calculated to range from 500 Pa near the sludge surface to roughly 5,000 Pa at 15 inches above the tank bottom.

  17. Fate of Radionuclides in Wastewater Treatment Plants

    E-Print Network [OSTI]

    Shabani Samgh Abadi, Farzaneh

    2013-01-01T23:59:59.000Z

    were measured by gamma-spectrometry. Also the partition oftreatment process. In gamma-spectrometry of sludge, the

  18. Solidification/stabilization of simulated uranium and nickel contaminated sludges

    E-Print Network [OSTI]

    Ramabhadran, Sanjay

    1996-01-01T23:59:59.000Z

    in this research which focused on better understanding the Solidification/Stabilization (S/S) chemistry, complex waste-binder interactions, and the suitability and effectiveness of additives in the Portland cement based treatment systems. The treatability...

  19. Hydration and leaching characteristics of cement pastes made from electroplating sludge

    SciTech Connect (OSTI)

    Chen, Ying-Liang [Department of Environmental Engineering, National Cheng Kung University, No. 1, University Rd., Tainan City 70101, Taiwan (China); Sustainable Environment Research Center, National Cheng Kung University, No. 1, University Rd., Tainan City 70101, Taiwan (China); Ko, Ming-Sheng [Institute of Mineral Resources Engineering, National Taipei University of Technology, No. 1, Sec. 3, Chunghsiao E. Rd., Taipei City 10608, Taiwan (China); Lai, Yi-Chieh [Department of Bioenvironmental Engineering, Chung Yuan Christian University, No. 200, Chung-Pei Rd., Chung-Li 32023, Taiwan (China); Chang, Juu-En, E-mail: juuen@mail.ncku.edu.tw [Department of Environmental Engineering, National Cheng Kung University, No. 1, University Rd., Tainan City 70101, Taiwan (China); Sustainable Environment Research Center, National Cheng Kung University, No. 1, University Rd., Tainan City 70101, Taiwan (China)

    2011-06-15T23:59:59.000Z

    The purpose of this study was to investigate the hydration and leaching characteristics of the pastes of belite-rich cements made from electroplating sludge. The compressive strength of the pastes cured for 1, 3, 7, 28, and 90 days was determined, and the condensation of silicate anions in hydrates was examined with the {sup 29}Si nuclear magnetic resonance (NMR) technology. The leachabilities of the electroplating sludge and the hardened pastes were studied with the multiple toxicity characteristic leaching procedure (MTCLP) and the tank leaching test (NEN 7345), respectively. The results showed that the electroplating sludge continued to leach heavy metals, including nickel, copper, and zinc, and posed a serious threat to the environment. The belite-rich cement made from the electroplating sludge was abundant in hydraulic {beta}-dicalcium silicate, and it performed well with regard to compressive-strength development when properly blended with ordinary Portland cements. The blended cement containing up to 40% the belite-rich cement can still satisfy the compressive-strength requirements of ASTM standards, and the pastes cured for 90 days had comparable compressive strength to an ordinary Portland cement paste. It was also found that the later hydration reaction of the blended cements was relatively more active, and high fractions of belite-rich cement increased the chain length of silicate hydrates. In addition, by converting the sludge into belite-rich cements, the heavy metals became stable in the hardened cement pastes. This study thus indicates a viable alternative approach to dealing with heavy metal bearing wastes, and the resulting products show good compressive strength and heavy-metal stability.

  20. Combustion of sludge waste in FBC. Distribution of metals and particle sizes

    SciTech Connect (OSTI)

    Kozinski, J.A. [McGill Univ., Montreal, Quebec (Canada); Rink, K.K.; Lighty, J.S. [Univ. of Utah, Salt Lake City, UT (United States)

    1995-12-31T23:59:59.000Z

    Due to the increases in the amounts of sludge generated and increasingly stringent regulations regarding its disposal, alternative methods to landfilling are becoming more important. Fluidized bed combustion is one such alternative, providing permanent disposal of the sludge. In this research, metal-solid particle characteristics during combustion of a sludge waste were studied. The sludge was a result of de-inking process. Experiments were carried out using a pilot-scale circulating fluidized bed combustion facility (CFB). The fluidized bed was operated in the bubbling mode. The sludge was separately burned with silica sand particles, ultrasorb particles, and alumina particles as bed materials. Major flue gas components (CO{sub 2}, CO, O{sub 2}, NO, NO{sub 2}) were measured continuously. Gas temperature profiles were determined using a water-cooled suction pyrometer. Solid particle samples were collected at multiple locations using a dilution tunnel sampling system. The solid samples were analyzed to determine ash structure, size and composition distributions. Metal analyses were performed using a computer-controlled Electron Probe Microanalyzer (EPMA) equipped with four Wavelength-Dispersive Spectrometers. Analyses of individual fly ash particles indicated that heavy metal elements (Pb, Cd, Cr, Cu, Ni) were generally located in regions near the particle`s core. Lighter metals (Si, Al, Ca, Na, K) were present across the entire cross-section of a particle, with the highest concentrations at the particle surface. These distributions were found to be similar regardless of the type of bed material. This suggests that the light metal layers are formed because of the internal rearrangements of a chemical nature as opposed to physical deposition of light metal fragments on particle surfaces.

  1. Effect of acetic acid on lipid accumulation by glucose-fed activated sludge cultures

    SciTech Connect (OSTI)

    Mondala, Andro; Hernandez, Rafael; French, Todd; McFarland, Linda; Sparks, Darrell; Holmes, William; Haque, Monica

    2012-01-01T23:59:59.000Z

    The effect of acetic acid, a lignocellulose hydrolysis by-product, on lipid accumulation by activated sludge cultures grown on glucose was investigated. This was done to assess the possible application of lignocellulose as low-cost and renewable fermentation substrates for biofuel feedstock production. Results: Biomass yield was reduced by around 54% at a 2 g L -1 acetic acid dosage but was increased by around 18% at 10 g L -1 acetic acid dosage relative to the control run. The final gravimetric lipid contents at 2 and 10 g L -1 acetic acid levels were 12.5 ���± 0.7% and 8.8 ���± 3.2% w/w, respectively, which were lower than the control (17.8 ���± 2.8% w/w). However, biodiesel yields from activated sludge grown with acetic acid (5.6 ���± 0.6% w/w for 2 g L -1 acetic acid and 4.2 ���± 3.0% w/w for 10 g L -1 acetic acid) were higher than in raw activated sludge (1-2% w/w). The fatty acid profiles of the accumulated lipids were similar with conventional plant oil biodiesel feedstocks. Conclusions: Acetic acid enhanced biomass production by activated sludge at high levels but reduced lipid production. Further studies are needed to enhance acetic acid utilization by activated sludge microorganisms for lipid biosynthesis.

  2. Investigation of Rheological Impacts on Sludge Batch 3 as Insoluble Solids and Wash Endpoints are Adjusted

    SciTech Connect (OSTI)

    Fellinger, T. L.

    2005-07-12T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) is currently processing and immobilizing radioactive sludge slurry into a durable borosilicate glass. The DWPF has already processed three sludge batches (Sludge Batch 1A, Sludge Batch 1B, and Sludge Batch 2) and is currently processing the fourth sludge batch (Sludge Batch 3). A sludge batch is defined as a single tank of sludge slurry or a combination of sludge slurries from different tanks that has been or will be qualified before being transferred to DWPF. As a part of the Sludge Batch 3 (SB3) qualification task, rheology measurements of the sludge slurry were requested at different insoluble solids loadings. These measurements were requested in order to gain insight into potential processing problems that may occur as the insoluble solids are adjusted up or down (by concentration or dilution) during the process. As a part of this study, a portion of the ''as received'' SB3 sample was washed with inhibited water (0.015 M NaOH and 0.015 M NaNO2) to target 0.5M Na versus a measured 1M Na in the supernate. The purpose of the ''washing'' step was to allow a comparison of the SB3 rheological data to the rheological data collected for Sludge Batch 2 (SB2) and to determine if there was a dependence of the yield stress and consistency as a function of washing. The ''as received'' SB3 rheology data was also compared to SB3 simulants prepared by the Simulant Development Program in order to provide guidance for selecting a simulant that is more representative of the rheological properties of the radioactive sludge slurry. A summary of the observations, conclusions are: (1) The yield stress and plastic viscosity increased as the weight percent insoluble solids were increased for the ''as received'' and ''washed'' SB3 samples, at a fixed pH. (2) For the same insoluble solids loading, the yield stress for the SB2 sample is approximately a factor of three higher than the ''as received'' SB3 sample. There also appears to be small difference in the plastic viscosity. This difference is probably due to the different Na concentrations of the slurries. (3) The yield stress for the SB2 sample at 17.5 wt. % insoluble solids loading is four times higher than the ''washed'' SB3 sample at 16.5 wt. % insoluble solids. There also appears to be small difference in the plastic viscosity. The differences for the yield stress and consistency can be explained by the differences in the Fe and Na concentrations of the sludge slurry and the anion concentrations of the resulting supernates. (4) The rheological properties (i.e. yield stress and plastic viscosity), as the insoluble solids are adjusted, for the ''as received'' and ''washed'' SB3 samples are different. The plastic viscosity curve for the ''as received'' SB3 sample was higher than the plastic viscosity curve for SB3 ''washed'' sample. The yield stress curve for the ''washed'' SB3 sample is slightly lower than the ''as received'' SB3 sample up until {approx}19 wt. % insoluble solids. The ''washed'' SB3 sample then exceeds the yield stress curve for the ''as received'' SB3 sample. This rheological behavior is probably due to the difference in the Na concentration of the supernate for the samples. (5) No unusual behavior, such as air entrainment, was noted for the ''as received'' SB3 sample. (6) The observed physical properties of the SB3 sample changed after washing. The ''washed'' SB3 sample entrained air readily at higher insoluble solids loadings (i.e. 14.1, 16.5, 19.5 wt. %) as it did for SB2. The air entrainment appeared to dissipate for the SB3 sample at the lower insoluble solids loadings (i.e. 9.7 and 11.7 wt. %). (7) The physical behavior of SB3 can be influenced by controlling the Na concentration in the supernate and the wt. % insoluble solids. The cause for the air entrainment in the ''washed'' SB3 sample could be due to a change in the particle size during the washing step. (8) The SB3 simulants prepared for the Simulant Development Program were approximately a factor of 1.6 to 4 times higher for yield stress and 2.6 to 4 times higher

  3. Carboniferous clastic-wedge stratigraphy, sedimentology, and foreland basin evolution: Black Warrior basin, Alabama and Mississippi

    SciTech Connect (OSTI)

    Hines, R.A.

    1986-05-01T23:59:59.000Z

    Carboniferous clastic-wedge stratigraphy and sedimentology in the Black Warrior basin of Alabama and Mississippi indicate deposition in an evolving foreland basin flanking the Appalachian-Ouachita fold-thrust belt. The strata reflect specific responses to foreland basin subsidence, orogenic activity, sediment supply, and dispersal systems. Definition of the regional stratigraphy of the clastic wedge provides for interpretation of the foreland basin subsidence history by enabling quantitative reconstruction of regional compaction and subsidence profiles. Comparison of the interpreted subsidence history with model profiles of foreland basin subsidence (predicted from loading and flexure of continental lithosphere) allows evaluation of mechanical models in terms of observed clastic-wedge sedimentology and stratigraphy. Mechanical modeling of foreland basin subsidence predicts formation of a flexural bulge that migrates cratonward ahead of the subsiding foreland basin during loading. In the Black Warrior basin, local stratigraphic thins, pinch-outs, and areas of marine-reworked sediments suggest migration of the flexural bulge. Comparison of flexural bulge migration with thermal maturation history allows evaluation of timing of stratigraphic trapping mechanisms with respect to onset of hydrocarbon generation.

  4. Quantification of Water Quality Improvement in Sandy Creek, A Tributary Watershed of Jordan Lake in the Cape Fear River Basin,

    E-Print Network [OSTI]

    in the Cape Fear River Basin, After Stream and Riparian Restoration and Wetland Treatment Cell Creation: Final to restoration. The Duke Forest Stream and Wetlands Restoration was established to rectify these problems delivery following watershed development, a three-phase stream and floodplain restoration was planned

  5. An Assessment of Technologies to Provide Extended Sludge Retrieval from Underground Storage Tanks at the Hanford Site

    SciTech Connect (OSTI)

    JA Bamberger

    2000-08-02T23:59:59.000Z

    The purpose of this study was to identify sludge mobilization technologies that can be readily installed in double-shell tanks along with mixer pumps to augment mixer pump operation when mixer pumps do not adequately mobilize waste. The supplementary technologies will mobilize sludge that may accumulate in tank locations out-of-reach of the mixer-pump jet and move the sludge into the mixer-pump range of operation. The identified technologies will be evaluated to determine if their performances and configurations are adequate to meet requirements developed for enhanced sludge removal systems. The study proceeded in three parallel paths to identify technologies that: (1) have been previously deployed or demonstrated in radioactive waste tanks, (2) have been specifically evaluated for their ability to mobilize or dislodge waste simulants with physical and theological properties similar to those anticipated during waste retrieval, and (3) have been used in similar industrial conditions, bu t not specifically evaluated for radioactive waste retrieval.

  6. Utilizing New Binder Materials for Green Building has Zero Waste by Recycling Slag and Sewage Sludge Ash 

    E-Print Network [OSTI]

    Zeedan, S. R.

    2010-01-01T23:59:59.000Z

    binding material to save energy and to produce new innovative zero materials waste . The current research aims to investigate new binder materials as alternative of Portland cement. Alkali activated slag (AAS) blended with sewage sludge ash (SSA...

  7. EA-1042: Proposed Changes to the Sanitary Sludge Land Application Program on the Oak Ridge Reservation, Oak Ridge, Tennesee

    Broader source: Energy.gov [DOE]

    This EA evaluates the environmental impacts of the proposal to raise the sludge land application loading limits from the current, self-imposed conservative 48 metric tons/ha lifetime loading to the...

  8. Structural and stratigraphic evolution of Shira Mountains, central Ucayali Basin, Peru? 

    E-Print Network [OSTI]

    Sanchez Alvarez, Jaime Orlando

    2008-10-10T23:59:59.000Z

    The Ucayali Basin is a Peruvian sub-Andean basin that initially formed during the extensive tectonics of the Early Paleozoic. Originally, the Ucayali Basin was part of a larger basin that extended east of the current ...

  9. Modified Streamflows 1990 Level of Irrigation : Missouri, Colorado, Peace and Slave River Basin, 1928-1989.

    SciTech Connect (OSTI)

    A.G. Crook Company; United States. Bonneville Power Administration

    1993-07-01T23:59:59.000Z

    This report presents data for monthly mean streamflows adjusted for storage change, evaporation, and irrigation, for the years 1928-1990, for the Colorado River Basin, the Missouri River Basin, the Peace River Basin, and the Slave River Basin.

  10. Drying results of K-Basin fuel element 1164M (run 6)

    SciTech Connect (OSTI)

    Oliver, B.M.; Klinger, G.S.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-08-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the sixth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 1164 M. This element (referred to as Element 1164M) was stored underwater in the K-West Basin from 1983 until 1996. Element 1164M was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0, and discussed in Section 6.0.

  11. Drying results of K-Basin fuel element 1990 (Run 1)

    SciTech Connect (OSTI)

    Marschman, S.C.; Abrefah, J.; Klinger, G.S.; Oliver, B.M.; MacFarlan, P.J.; Ritter, G.A.

    1998-06-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100-Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basins have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuels in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first of those tests (Run 1), which was conducted on an N-Reactor inner fuel element (1990) that had been stored underwater in the K-West Basin (see Section 2.0). This fuel element was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The testing was conducted in the Whole Element Furnace Testing System, described in Section 3.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in Section 4.0, and the experimental results provided in Section 5.0. These results are further discussed in Section 6.0.

  12. Drying results of K-Basin fuel element 5744U (Run 4)

    SciTech Connect (OSTI)

    Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

    1998-07-01T23:59:59.000Z

    The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basins have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the fourth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 5744U. This element (referred to as Element 5744U) was stored underwater in the K-West Basin from 1983 until 1996. Element 5744U was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0, and discussed in Section 6.0.

  13. Recent developments in geothermal waste treatment biotechnology

    SciTech Connect (OSTI)

    Premuzic, E.T.; Lin, M.S.; Jin, J.Z.

    1993-05-01T23:59:59.000Z

    Continuing studies at Brookhaven National Laboratory (BNL) have shown that cost-efficient biotechnology for the removal of toxic trace metals from geothermal sludge is feasible. Pilot-scale experiments have shown that fast rates (< 24-h) of metal removal at 55{degree}C--60{degree}C can be achieved with removal efficiencies of better than 80%, yielding a product well within the environmental regulatory limits. Recent studies have shown that radionuclides, such as radium present in low concentrations in some sludges, can also be removed by means of a secondary biotreatment. The process produces an aqueous phase which contains all of the regulatory metals in a soluble form. A follow-up technology for the treatment of the aqueous phase is concurrently being developed at BNL. Preliminary results indicate that a small volume concentrate of metals can be generated producing an aqueous phase which meets drinking water standards. In this paper the current state-of-the-biotechnology will be discussed.

  14. Geochemical Prospecting of Hydrocarbons in Frontier Basins of India* By

    E-Print Network [OSTI]

    B. Kumar; D. J. Patil; G. Kalpana; C. Vishnu Vardhan

    India has 26 sedimentary basins with a basinal area of approximately 1.8x 10 6 km 2 (excluding deep waters), out of which seven are producing basins and two have proven potential. Exploration efforts in other basins, called “frontier basins ” are in progress. These basins are characterized by varied geology, age, tectonics, and depositional environments. Hydrocarbon shows in many of these basins are known, and in few basins oil and gas have flowed in commercial /non-commercial quantities. Within the framework of India Hydrocarbon Vision – 2025 and New Exploration Licensing Policy, there is a continuous increase in area under active exploration. The asset management concept with multi-disciplinary teams has created a demand for synergic application of risk-reduction technologies, including surface geochemical surveys. National Geophysical Research Institute (NGRI), Hyderabad, India has initiated/planned surface geochemical surveys composed of gas chromatographic and carbon isotopic analyses in few of the frontier basins of India. The adsorbed soil gas data in one of the basins (Saurashtra basin, Gujarat) has shown varied concentrations of CH4 to C4H10. The C1 concentration varies between 3 to 766 ppb and ??C2+, 1 to 543 ppb. This basin has thin soil cover and the Mesozoic sediments (probable source rocks) are overlain by thick cover of Deccan Traps. The scope and perspective of geochemical surveys in frontier basins of India are presented here.

  15. Greenhouse and laboratory studies on the effects of an anaerobic digester sludge on growth and nutrient uptake of sorghum

    E-Print Network [OSTI]

    Vincent, John Cooper

    1989-01-01T23:59:59.000Z

    GREENHOUSE AND LABORATORI STUDIES ON THE EFFECTS OF AN ANAEROBIC DIGESTER SLUDGE ON GROWTH AND NUTRIENT UPTAKE OF SORGHUM A Thesis By John Cooper Vincent Submitted to the Office of Graduate Studies Texas A&M University in partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE December 1989 Major Subject: Agronomy GREENHOUSE AND LABORATORy STUDIES ON THE EFFECTS OF AN ANAEROBIC DIGESTER SLUDGE ON GROWTH AND NUTRIENT UPTAKE OF SORGHUM A Thesis by John Cooper Vincent Approved...

  16. Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

    SciTech Connect (OSTI)

    Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)] [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Mayberry, J. [Science Applications International Corp., Idaho Falls, ID (United States)] [Science Applications International Corp., Idaho Falls, ID (United States); Frazier, G. [Univ. of Tennessee, Knoxville, TN (United States)] [Univ. of Tennessee, Knoxville, TN (United States)

    1994-01-01T23:59:59.000Z

    This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well.

  17. ANALYSIS OF DWPF SLUDGE BATCH 6 (MACROBATCH 7) POUR STREAM GLASS SAMPLES

    SciTech Connect (OSTI)

    Johnson, F.

    2012-01-20T23:59:59.000Z

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 6 (SB6), also referred to as Macrobatch 7 (MB7), in June 2010. SB6 is a blend of the heel of Tank 40 from Sludge Batch 5 (SB5), H-Canyon Np transfers and SB6 that was transferred to Tank 40 from Tank 51.1 SB6 was processed using Frit 418. Sludge is received into the DWPF Chemical Processing Cell (CPC) and is processed through the Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator Tank (SME). The treated sludge slurry is then transferred to the Melter Feed Tank (MFT) and fed to the melter. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP) and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. The DWPF requested various analyses of radioactive glass samples obtained from the melter pour stream during processing of SB6 as well as reduction/oxidation (REDOX) analysis of MFT samples to determine the impact of Argon bubbling. Sample analysis followed the Task Technical and Quality Assurance Plan (TTQAP) and an Analytical Study Plan (ASP). Four Pour Stream (PS) glass samples and two MFT slurry samples were delivered to the Savannah River National Laboratory (SRNL) from the DWPF. Table 1-1 lists the sample information for each pour stream glass sample. SB6 PS3 (S03472) was selected as the official pour stream sample for SB6 and full analysis was requested. This report details the visual observations of the as-received SB6 PS No.3 glass sample as well as results for the chemical composition, Product Consistency Test (PCT), radionuclide content, noble metals, and glass density. REDOX results will be provided for all four pour stream samples and vitrified samples of MFT-558 and MFT-568A. Where appropriate, data from other pour stream samples will be provided.

  18. FINE PARTICAL AND TOXIC METAL EMISSIONS FROM THE COMBUSTION OF SEWAGE SLUDGE/COAL MIXTURES: A SYSTEMATIC ASSESSMENT

    SciTech Connect (OSTI)

    Jost O.L. Wendt; Wayne S. Seames; Art Fernandez

    2003-09-21T23:59:59.000Z

    This research project focuses on pollutants from the combustion of mixtures of dried municipal sewage sludge (MSS) and pulverized coal. The objective was to determine potential tradeoffs between CO{sub 2} mitigation through using a CO{sub 2} neutral fuel, such as municipal sewage sludge, and the emergence of other potential problems such as the emission of toxic fly ash particles. The work led to new insight into mechanisms governing the partitioning of major and trace metals from the combustion of sewage sludge, and mixtures of coal and sewage sludge. The research also showed that the co-combustion of coal and sewage sludge emitted fine particulate matter that might potentially cause greater lung injury than that from the combustion of either coal alone or municipal sewage sludge alone. The reason appeared to be that the toxicity measured required the presence of large amounts of both zinc and sulfur in particles that were inhaled. MSS provided the zinc while coal provided the sulfur. Additional research showed that the toxic effects could most likely be engineered out of the process, through the introduction of kaolinite sorbent downstream of the combustion zone, or removing the sulfur from the fuel. These results are consequences of applying ''Health Effects Engineering'' to this issue. Health Effects Engineering is a new discipline arising out of this work, and is derived from using a collaboration of combustion engineers and toxicologists to mitigate the potentially bad health effects from combustion of this biomass fuel.

  19. Relative yields of U-235 fission products measured in a high level radioactive sludge at Savannah River Site

    SciTech Connect (OSTI)

    Bibler, N.E.; Coleman, C.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Kinard, W.F. [Charleston Coll., SC (United States). Dept. of Chemistry

    1992-10-01T23:59:59.000Z

    This paper presents measurements of the concentrations of 42 of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at Savannah River Site. The 42 fision products make up 98% of the waste sludge. We used inductively coupled plasma-mass spectroscopy for the analysis. The relative yields for most of the fission products are in complete agreement with the known relative yields for the beta decay chains of the two asymmetric branches of the slow neutron fission of U-235. Disagreements can be reconciled based on the chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses. This paper presents measurements of the concentrations of 42 (98%) of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at the Savannah River Site. We analyzed the sludge with inductively coupled plasma-mass spectroscopy. The relative yields for most of the fission products agree completely with the known relative vields for the beta decay chains of the two asymmetric: branches of the slow neutron fission of U-235. The chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses explain the differences in the measured and calculated results.

  20. Relative yields of U-235 fission products measured in a high level radioactive sludge at Savannah River Site

    SciTech Connect (OSTI)

    Bibler, N.E.; Coleman, C.J. (Westinghouse Savannah River Co., Aiken, SC (United States)); Kinard, W.F. (Charleston Coll., SC (United States). Dept. of Chemistry)

    1992-01-01T23:59:59.000Z

    This paper presents measurements of the concentrations of 42 of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at Savannah River Site. The 42 fision products make up 98% of the waste sludge. We used inductively coupled plasma-mass spectroscopy for the analysis. The relative yields for most of the fission products are in complete agreement with the known relative yields for the beta decay chains of the two asymmetric branches of the slow neutron fission of U-235. Disagreements can be reconciled based on the chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses. This paper presents measurements of the concentrations of 42 (98%) of the long-lived U-235 fission products in a high-level radioactive waste sludge stored at the Savannah River Site. We analyzed the sludge with inductively coupled plasma-mass spectroscopy. The relative yields for most of the fission products agree completely with the known relative vields for the beta decay chains of the two asymmetric: branches of the slow neutron fission of U-235. The chemistry of the fission products in the caustic waste sludges, the neutron fluences in SRS reactors, or interferences in the ICP-MS analyses explain the differences in the measured and calculated results.

  1. VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY'S (DWPF) PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 7A QUALIFICATION SAMPLE

    SciTech Connect (OSTI)

    Click, D.; Edwards, T.; Jones, M.; Wiedenman, B.

    2011-03-14T23:59:59.000Z

    For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs confirmation of the applicability of the digestion method to be used by the DWPF lab for elemental analysis of Sludge Receipt and Adjustment Tank (SRAT) receipt samples and SRAT product process control samples. DWPF SRAT samples are typically dissolved using a room temperature HF-HNO{sub 3} acid dissolution (i.e., DWPF Cold Chem Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICP-AES). This report contains the results and comparison of data generated from performing the Aqua Regia (AR), Sodium peroxide/Hydroxide Fusion (PF) and DWPF Cold Chem (CC) method digestions of Sludge Batch 7a (SB7a) SRAT Receipt and SB7a SRAT Product samples. The SB7a SRAT Receipt and SB7a SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constituates the SB7a Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 6 (SB6), to form the Sb7a Blend composition.

  2. Tectonic Evolution of the Contaya Arch Ucyali Basin, Peru 

    E-Print Network [OSTI]

    Navarro Zelasco, Luis

    2011-08-08T23:59:59.000Z

    The Contaya arch is an elongated topographic high that divides the Huallaga, Maranon and Ucayali basins in the Peruvian Amazonian plain. Its position well into the foreland basin and well inland from the main Andean thrust ...

  3. active single basin: Topics by E-print Network

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

    subsidence histories of the Aquitaine Basin (Fig.8c) record a minor ac- celeration in subsidence. The shortening of the Australian plate adjacent to the basin is small (from 2...

  4. annapolis basin area: Topics by E-print Network

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

    geology of the Bengal Basin in relation to the regional tectonic framework and basin-fill history Geosciences Websites Summary: ; and this was followed by an increase in the...

  5. annecy basin eastern: Topics by E-print Network

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

    subsidence histories of the Aquitaine Basin (Fig.8c) record a minor ac- celeration in subsidence. The shortening of the Australian plate adjacent to the basin is small (from 2...

  6. Tectonic Evolution of the Contaya Arch Ucyali Basin, Peru

    E-Print Network [OSTI]

    Navarro Zelasco, Luis

    2011-08-08T23:59:59.000Z

    The Contaya arch is an elongated topographic high that divides the Huallaga, Maranon and Ucayali basins in the Peruvian Amazonian plain. Its position well into the foreland basin and well inland from the main Andean thrust belt has proven...

  7. Improved Basin Analog System to Characterize Unconventional Gas Resource

    E-Print Network [OSTI]

    Wu, Wenyan 1983-

    2012-10-02T23:59:59.000Z

    , the BASIN software is combined with PRISE in the UGRA system to estimate unconventional resource potential in frontier basins. The PRISE software contains information about the resources (conventional gas, conventional oil, shale gas, coalbed methane...

  8. K West basin isolation barrier leak rate test

    SciTech Connect (OSTI)

    Whitehurst, R.; McCracken, K.; Papenfuss, J.N.

    1994-10-31T23:59:59.000Z

    This document establishes the procedure for performing the acceptance test on the two isolation barriers being installed in K West basin. This acceptance test procedure shall be used to: First establish a basin water loss rate prior to installation of the two isolation barriers between the main basin and the discharge chute in K-Basin West. Second, perform an acceptance test to verify an acceptable leakage rate through the barrier seals.

  9. Evolution of extensional basins and basin and range topography west of Death Valley, California

    E-Print Network [OSTI]

    Hodges, K. V.; McKenna, L. W.; Stock, J.; Knapp, J.; Page, L.; Sternlof, K.; Silverberg, D.; Wust, G.; Walker, J. Douglas

    1989-06-01T23:59:59.000Z

    TECTONICS, VOL. 8, NO. 3, PAGES 453-467, JUNE 1989 EVOLUTION OF EXTENSIONAL BASINS AND BASIN AND RANGE TOPOGRAPHY WEST OF DEATH VALLEY, CALIFORNIA K.V. Hodges, L.W. McKenna, J. Stock , J. Knapp, L. Page, K. Sternlof, D. Silverberg, G. Wrist 2... of the extensional riders in this area indicates that the sole fault dips less than 15øNW beneath the Nova Formation [Hodges et al., 1989]. Detailed mapping of the structurally lowest portions of the Nova Basin south of Panamint Butte (Figure 2; K.V. Hodges...

  10. Simplified vibratory characterization of alluvial basins

    E-Print Network [OSTI]

    Semblat, Jean-François; Duval, Anne-Marie

    2011-01-01T23:59:59.000Z

    For the analysis of seismic wave amplification, modal methods are interesting tools to study the modal properties of geological structures. Modal approaches mainly lead to information on such parameters as fundamental frequencies and eigenmodes of alluvial basins. For a specific alluvial deposit in Nice (France), a simplified modal approach involving the Rayleigh method is considered. This approach assumes a set of admissible shape functions for the eigenmodes and allows a fast estimation of the fundamental frequency of the basin. The agreement between modal numerical results and experimental ones is satisfactory. The simplified modal method then appears as an efficient mean for the global vibratory characterization of geological structures towards resonance.

  11. Atlas of major Appalachian basin gas plays

    SciTech Connect (OSTI)

    Aminian, K.; Avary, K.L.; Baranoski, M.T.; Flaherty, K.; Humphreys, M.; Smosna, R.A.

    1995-06-01T23:59:59.000Z

    This regional study of gas reservoirs in the Appalachian basin has four main objectives: to organize all of the -as reservoirs in the Appalachian basin into unique plays based on common age, lithology, trap type and other geologic similarities; to write, illustrate and publish an atlas of major gas plays; to prepare and submit a digital data base of geologic, engineering and reservoir parameters for each gas field; and technology transfer to the oil and gas industry during the preparation of the atlas and data base.

  12. K-Area and Par Pond Sewage Sludge Application Sites Groundwater Monitoring Report: Third quarter 1993

    SciTech Connect (OSTI)

    Not Available

    1994-01-01T23:59:59.000Z

    Samples from the three wells at the K-Area Sewage Sludge Application Site (KSS wells) and the three wells at the Par Pond Sewage Sludge Application Site (PSS wells) are analyzed quarterly for constituents required by South Carolina Department of Health and Environmental Control Construction Permit 13,173 and, as requested, for other constituents as part of the Savannah River Site (SRS) Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals, also are required by the permit. Iron and lead, permit-required constituents, and aluminum presently exceed SRS flagging standards in samples from the two sites. Elevated concentrations of metals at these sites, not reported during 1992, may be the reflection of a recent change in analytical methodology.

  13. K-Area and Par Pond Sewage Sludge Application Sites Groundwater Monitoring Report. First quarter 1993

    SciTech Connect (OSTI)

    Not Available

    1993-07-01T23:59:59.000Z

    Samples from the three wells at the K-Area Sewage Sludge Application Site (KSS wells) and the three wells at the Par Pond Sewage Sludge Application Site (PSS wells) are analyzed quarterly for constituents required by South Carolina Department of Health and Environmental Control Construction Permit 13,173 and, as requested, for other constituents as part of the Savannah River Site Groundwater Monitoring Program. Annual analyses for other constituents, primarily metals, also are required by the permit. During first quarter 1993, no permit-required constituents exceeded standards at the two sites except iron, which was elevated in one KSS well and two PSS wells. Aluminum, not required by the permit, was the only other constituent that exceeded standards. Elevated levels of aluminum and iron at these two sites may be concurrent with a change in analytical methodology. As in previous quarters, chlordane concentrations did not exceed the detection limit in any of the wells.

  14. Comparison of Sludge Digestion Methods for High Organic Hanford Tank 241-C-204

    SciTech Connect (OSTI)

    Lindberg, Michael J.; Deutsch, William J.

    2006-12-01T23:59:59.000Z

    This report presents the results of an investigation into methods for digesting sludge in tank 241-C-204 at the Hanford Site in south-central Washington State. The objective of this study was to compare the recovery of uranium, neptunium, and plutonium using three digestion methods: EPA Method 3052, EPA Method 3050B, and alkaline fusion. Results show that EPA Method 3052, microwave assisted acid digestion, is the most efficient digestion method with higher recoveries for both uranium and plutonium. This may also be the case for neptunium; however, the analytical results are uncertain for this element. The microwave digestion method also has the added benefits of being quicker and producing less waste, which lowers the overall cost per sample. Further testing with samples from other tanks will confirm that microwave assisted digestion is a viable method of digesting Hanford tank sludges (including those with a high organic content) for chemical analysis.

  15. Determination of Reportable Radionuclides for DWPF Sludge Batch 3 (Macrobatch 4)

    SciTech Connect (OSTI)

    Bannochie, C

    2005-05-01T23:59:59.000Z

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that ''The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115''. As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, IAEA Safeguards Reporting for HLW, requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The Defense Waste Processing Facility (DWPF) is receiving radioactive sludge slurry from High Level Waste Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the previous contents of Tank 40 (Sludge Batch 2) and the sludge that was transferred to Tank 40 from Tank 51. The blend of sludge from Tank 51 and Tank 40 defines Macrobatch 4 (also referred to as Sludge Batch 3). This report develops the list of reportable radionuclides and associated activities and determines the radionuclide activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Task Technical Request HLW/DWPF/TTR-03-0005, Revision 1 entitled Sludge Batch 3 SRTC Shielded Cells Testing. Specifically, this report details results from performing, in part, Subtask 3 of the TTR and, in part, meets Deliverable 6 of the TTR. The work was performed following the Technical Task and Quality Assurance Plan (TTQAP), WSRC-RP-2003-00249, Rev. 1 and Analytical Study Plan (ASP), WSRC-RP-2004-00262. In order to determine the reportable radionuclides for Sludge Batch 3 (Macro Batch 4), a list of radioisotopes that may meet the criteria as specified by the Department of Energy's (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes excluded from the projection calculations.

  16. NE Pacific Basin --Tagging Data Kate Myers, Ph.D.

    E-Print Network [OSTI]

    Ocean B: NE Pacific Basin --Tagging Data Kate Myers, Ph.D. Principal Investigator, High Seas Salmon ocean tagging research on Columbia River salmon and steelhead migrating in the NE Pacific Basin R. Basin in 1995-2004. Fisheries and Oceans Canada, Pacific Biological Station, Nanaimo, B

  17. ASSESSMENT OF LIVESTOCK WINTERING AREAS IN BRIDGE CREEK BASIN, 1996

    E-Print Network [OSTI]

    #12;ASSESSMENT OF LIVESTOCK WINTERING AREAS IN BRIDGE CREEK BASIN, 1996 DOE FRAP 1996-03 Prepared-96.............................................. 22 LIST OF FIGURES Figure 1. Bridge Creek basin livestock wintering area back assessment, 1996 quality in the Bridge Creek basin are assessed. These sites had been inspected in the winter and spring

  18. Modeling thermal convection in supradetachment basins: example from western Norway

    E-Print Network [OSTI]

    Andersen, Torgeir Bjørge

    Modeling thermal convection in supradetachment basins: example from western Norway A. SOUCHE*, M. DABROWSKI AND T. B. ANDERSEN Physics of Geological Processes (PGP), University of Oslo, Oslo, Norway basins of western Norway are examples of supradetachment basins that formed in the hanging wall

  19. Exploring Geophyte Use in the Northern Great Basin

    E-Print Network [OSTI]

    Provancher, William

    Wild Onion & Balsamroot Gambel Oak Pinyon Pine Salina Wild Rye Sunflower Seed Great Basin Rye IndianExploring Geophyte Use in the Northern Great Basin: nutrient content, handling costs, effects of human settlement, subsistence, and sociopolitical change in Basin/Plateau #12;Problems Geophytes

  20. International Best Practices for Pre-Processing and Co-Processing Municipal Solid Waste and Sewage Sludge in the Cement Industry

    E-Print Network [OSTI]

    Hasanbeigi, Ali

    2013-01-01T23:59:59.000Z

    Co-processing Municipal Solid Waste and Sewage Sludge in theno date. “Integrated Solid Waste Management. ” Presentationincineration of Municipal Solid Waste in Cement Industry. :