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Sample records for processing facility swpf

  1. PERFORMANCE PROPERTIES OF SALTSTONE PRODUCED USING SWPF SIMULANTS

    SciTech Connect

    Harbour, J.; Edwards, T.

    2010-02-16

    The overwhelming majority of waste to be immobilized at the Saltstone Production Facility will come from the waste stream exiting the Salt Waste Processing Facility (SWPF). These SWPF batches are salt solutions that result from pretreatment of the High Level Waste (HLW) supernate by an Actinide Removal Process followed by Caustic Side Solvent Extraction. The concentration of aluminate within these streams will vary and be determined by (1) the concentration in the incoming salt waste stream, (2) the degree of aluminum leaching from the HLW, (3) the method for introducing the aluminate into the waste stream (continuous or batch) and (4) and any operational or regulatory limitations. The overall Performance Assessment outcome for the Saltstone Disposal Facility will depend significantly on the performance properties of the SWPF Saltstone grouts. This report identifies and quantifies, when possible, those factors that drive the performance properties of the projected SWPF grouts. Previous work has identified aluminate concentration in the salt waste stream as a key factor in determining performance. Consequently, significant variation in the aluminate concentration to a maximum level of 0.65 M was investigated in this report. The SWPF baseline grout is a mix with a 0.60 water to cementitious ratio and a premix composition of 45 wt % slag, 45 wt % fly ash and 10 wt % portland cement. The key factors that drive performance of the SWPF mixes were determined to be (1) the time/temperature profile for curing, (2) water to cementitious materials ratio, (3) aluminate concentration in the waste stream, and (4) wt % slag in the premix. An increase in the curing temperature for mixes with 45 wt % slag resulted in a 2.5 times decrease in Young's modulus. The reduction of Young's modulus measured at 60 C versus 22 C was mitigated by an increase in the aluminate concentration but was still significant. For mixes containing 60 wt % slag, the reduction in Young's modulus between these two curing temperatures was significantly lessened. The importance of curing conditions can not be overemphasized. The gain realized in performance by, e.g., a higher level of aluminate or wt % slag or a reduction in w/cm ratio, can be offset by the effects of a higher curing temperature. In fact, the final performance properties of a mix cured at 60 C can be lower than the initial values before any of the performance enhancing changes are introduced. Control of the time/temperature curing profile can be managed by pour schedules and other temperature control measures. The reduction in performance at higher curing temperatures is consistent with results obtained in a separate study. Although preliminary, results from this task on the measurement of hydraulic conductivity at MACTEC showed that curing of a Saltstone mix at 60 C increased the hydraulic conductivity by several orders of magnitude. The permeability data are based on only one mix but, were consistent with a measured reduction in Young's modulus for these same samples. Therefore, it is recommended that impact of curing temperature on performance properties be further investigated. An increase in dynamic Young's modulus (indicator of performance) is observed as the water to cementitious materials (w/cm) ratio decreases. The w/cm ratio is a process parameter which can be adjusted to improve performance as long as the processing properties of the grout are still within an operational window that will lead to successful placement. The same conclusions apply to wt % slag in the premix. That is, an increase in the wt % slag at the expense of fly ash in the premix increases Young's modulus and performance. An increase in wt % slag (as with a decrease in w/cm ratio) increases viscosity and yield stress and a final mix design must be balanced such that acceptable processing properties are obtained. The performance properties of SWPF mixes show a non-linear dependence on aluminate concentration. As the aluminate concentration is increased from 0.1 M to 0.25 M, the Young's modulus and compressive strength increase and the porosity is reduced. Consistent with this improvement in performance is an increase in the heat of hydration, reflective of an increase in the degree of hydration. Higher degrees of hydration in mixes generally lead to better performance. In the region of 0.25 to 0.45 M aluminate, very little additional change is observed in any of the properties. A further increase in the aluminate concentration from 0.45 M to 0.65 M leads to a slight reduction in Young's modulus. It was observed however, that the values of Young's modulus for samples cured at 22 C decreased after approximately 50 days. This was the first time a reduction in Young's modulus was observed as a function of time and is most likely correlated with the high levels of aluminate present in these mixes. This reduction can be accounted for by cracking of the Saltstone samples with time.

  2. BLENDING ANALYSIS FOR RADIOACTIVE SALT WASTE PROCESSING FACILITY

    SciTech Connect

    Lee, S.

    2012-05-10

    Savannah River National Laboratory (SRNL) evaluated methods to mix and blend the contents of the blend tanks to ensure the contents are properly blended before they are transferred from the blend tank such as Tank 21 and Tank 24 to the Salt Waste Processing Facility (SWPF) feed tank. The tank contents consist of three forms: dissolved salt solution, other waste salt solutions, and sludge containing settled solids. This paper focuses on developing the computational model and estimating the operation time of submersible slurry pump when the tank contents are adequately blended prior to their transfer to the SWPF facility. A three-dimensional computational fluid dynamics approach was taken by using the full scale configuration of SRS Type-IV tank, Tank 21H. Major solid obstructions such as the tank wall boundary, the transfer pump column, and three slurry pump housings including one active and two inactive pumps were included in the mixing performance model. Basic flow pattern results predicted by the computational model were benchmarked against the SRNL test results and literature data. Tank 21 is a waste tank that is used to prepare batches of salt feed for SWPF. The salt feed must be a homogeneous solution satisfying the acceptance criterion of the solids entrainment during transfer operation. The work scope described here consists of two modeling areas. They are the steady state flow pattern calculations before the addition of acid solution for tank blending operation and the transient mixing analysis during miscible liquid blending operation. The transient blending calculations were performed by using the 95% homogeneity criterion for the entire liquid domain of the tank. The initial conditions for the entire modeling domain were based on the steady-state flow pattern results with zero second phase concentration. The performance model was also benchmarked against the SRNL test results and literature data.

  3. PRELIMINARY EVALUATION OF DWPF IMPACTS OF BORIC ACID USE IN CESIUM STRIP FOR SWPF AND MCU

    SciTech Connect

    Stone, M.

    2010-09-28

    A new solvent system is being evaluated for use in the Modular Caustic-Side Solvent Extraction Unit (MCU) and in the Salt Waste Processing Facility (SWPF). The new system includes the option to replace the current dilute nitric acid strip solution with boric acid. To support this effort, the impact of using 0.01M, 0.1M, 0.25M and 0.5M boric acid in place of 0.001M nitric acid was evaluated for impacts on the DWPF facility. The evaluation only covered the impacts of boric acid in the strip effluent and does not address the other changes in solvents (i.e., the new extractant, called MaxCalix, or the new suppressor, guanidine). Boric acid additions may lead to increased hydrogen generation during the SRAT and SME cycles as well as change the rheological properties of the feed. The boron in the strip effluent will impact glass composition and could require each SME batch to be trimmed with boric acid to account for any changes in the boron from strip effluent additions. Addition of boron with the strip effluent will require changes in the frit composition and could lead to changes in melt behavior. The severity of the impacts from the boric acid additions is dependent on the amount of boric acid added by the strip effluent. The use of 0.1M or higher concentrations of boric acid in the strip effluent was found to significantly impact DWPF operations while the impact of 0.01M boric acid is expected to be relatively minor. Experimental testing is required to resolve the issues identified during the preliminary evaluation. The issues to be addressed by the testing are: (1) Impact on SRAT acid addition and hydrogen generation; (2) Impact on melter feed rheology; (3) Impact on glass composition control; (4) Impact on frit production; and (5) Impact on melter offgas. A new solvent system is being evaluated for use in the Modular Caustic-Side Solvent Extraction Unit (MCU) and in the Salt Waste Processing Facility (SWPF). The new system includes the option to replace the current dilute nitric acid strip solution with boric acid. To support this effort, the impact of using 0.01M, 0.1M, 0.25M and 0.5M boric acid in place of 0.001M nitric acid was evaluated for impacts on the DWPF facility. The evaluation only covered the impacts of boric acid in the strip effluent and does not address the other changes in solvents (i.e., the new extractant, called MaxCalix, or the new suppressor, guanidine). Experimental testing with the improved solvent is required to determine the impact of any changes in the entrained solvent on DWPF processing.

  4. Spacelab Data Processing Facility

    NASA Technical Reports Server (NTRS)

    1983-01-01

    The capabilities of the Spacelab Data Processing Facility (SPDPF) are highlighted. The capturing, quality monitoring, processing, accounting, and forwarding of vital Spacelab data to various user facilities around the world are described.

  5. IMPACT OF THE SMALL COLUMN ION EXCHANGE PROCESS ON THE DEFENSE WASTE PROCESSING FACILITY - 12112

    SciTech Connect

    Koopman, D.; Lambert, D.; Fox, K.; Stone, M.

    2011-11-07

    The Savannah River Site (SRS) is investigating the deployment of a parallel technology to the Salt Waste Processing Facility (SWPF, presently under construction) to accelerate high activity salt waste processing. The proposed technology combines large waste tank strikes of monosodium titanate (MST) to sorb strontium and actinides with two ion exchange columns packed with crystalline silicotitanate (CST) resin to sorb cesium. The new process was designated Small Column Ion Exchange (SCIX), since the ion exchange columns were sized to fit within a waste storage tank riser. Loaded resins are to be combined with high activity sludge waste and fed to the Defense Waste Processing Facility (DWPF) for incorporation into the current glass waste form. Decontaminated salt solution produced by SCIX will be fed to the SRS Saltstone Facility for on-site immobilization as a grout waste form. Determining the potential impact of SCIX resins on DWPF processing was the basis for this study. Accelerated salt waste treatment is projected to produce a significant savings in the overall life cycle cost of waste treatment at SRS.

  6. Spacelab Data Processing Facility

    NASA Technical Reports Server (NTRS)

    1983-01-01

    The Spacelab Data Processing Facility (SDPF) processes, monitors, and accounts for the payload data from Spacelab and other Shuttle missions and forwards relevant data to various user facilities worldwide. The SLDPF is divided into the Spacelab Input Processing System (SIPS) and the Spacelab Output Processing System (SOPS). The SIPS division demultiplexes, synchronizes, time tags, quality checks, accounts for the data, and formats the data onto tapes. The SOPS division further edits, blocks, formats, and records the data on tape for shipment to users. User experiments must conform to the Spacelab's onboard High Rate Multiplexer (HRM) format for maximum process ability. Audio, analog, instrumentation, high density, experiment data, input/output data, quality control and accounting, and experimental channel tapes along with a variety of spacelab ancillary tapes are provided to the user by SLDPF.

  7. Studsvik Processing Facility Update

    SciTech Connect

    Mason, J. B.; Oliver, T. W.; Hill, G. M.; Davin, P. F.; Ping, M. R.

    2003-02-25

    Studsvik has completed over four years of operation at its Erwin, TN facility. During this time period Studsvik processed over 3.3 million pounds (1.5 million kgs) of radioactive ion exchange bead resin, powdered filter media, and activated carbon, which comprised a cumulative total activity of 18,852.5 Ci (6.98E+08 MBq). To date, the highest radiation level for an incoming resin container has been 395 R/hr (3.95 Sv/h). The Studsvik Processing Facility (SPF) has the capability to safely and efficiently receive and process a wide variety of solid and liquid Low Level Radioactive Waste (LLRW) streams including: Ion Exchange Resins (IER), activated carbon (charcoal), graphite, oils, solvents, and cleaning solutions with contact radiation levels of up to 400 R/hr (4.0 Sv/h). The licensed and heavily shielded SPF can receive and process liquid and solid LLRWs with high water and/or organic content. This paper provides an overview of the last four years of commercial operations processing radioactive LLRW from commercial nuclear power plants. Process improvements and lessons learned will be discussed.

  8. Advanced Polymer Processing Facility

    SciTech Connect

    Muenchausen, Ross E.

    2012-07-25

    Some conclusions of this presentation are: (1) Radiation-assisted nanotechnology applications will continue to grow; (2) The APPF will provide a unique focus for radiolytic processing of nanomaterials in support of DOE-DP, other DOE and advanced manufacturing initiatives; (3) {gamma}, X-ray, e-beam and ion beam processing will increasingly be applied for 'green' manufacturing of nanomaterials and nanocomposites; and (4) Biomedical science and engineering may ultimately be the biggest application area for radiation-assisted nanotechnology development.

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

    SciTech Connect

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

    2012-01-09

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

  10. PAPER STUDY EVALUATIONS OF THE INTRODUCTION OF SMALL COLUMN ION EXCHANGE WASTE STREAMS TO THE DEFENSE WASTE PROCESSING FACILITY

    SciTech Connect

    Fox, K.; Edwards, T.; Stone, M.; Koopman, D.

    2010-06-29

    The objective of this paper study is to provide guidance on the impact of Monosodium Titanate (MST) and Crystalline Silicotitanate (CST) streams from the Small Column Ion Exchange (SCIX) process on the Defense Waste Processing Facility (DWPF) flowsheet and glass waste form. A series of waste processing scenarios was evaluated, including projected compositions of Sludge Batches 8 through 17 (SB8 through SB17), MST additions, CST additions to Tank 40 or to a sludge batch preparation tank (Tank 42 or Tank 51, referred to generically as Tank 51 in this report), streams from the Salt Waste Processing Facility (SWPF), and two canister production rates. A wide array of potential glass frit compositions was used to support this assessment. The sludge and frit combinations were evaluated using the predictive models in the current DWPF Product Composition Control System (PCCS). The results were evaluated based on the number of frit compositions available for a particular sludge composition scenario. A large number of candidate frit compositions (e.g., several dozen to several hundred) is typically a good indicator of a sludge composition for which there is flexibility in forming an acceptable waste glass and meeting canister production rate commitments. The MST and CST streams will significantly increase the concentrations of certain components in glass, such as Nb{sub 2}O{sub 5}, TiO{sub 2}, and ZrO{sub 2}, to levels much higher than have been previously processed at DWPF. Therefore, several important assumptions, described in detail in the report, had to be made in performing the evaluations. The results of the paper studies, which must be applied carefully given the assumptions made concerning the impact of higher Ti, Zr, and Nb concentrations on model validity, provided several observations: (1) There was difficulty in identifying a reasonable number of candidate frits (and in some cases an inability to identify any candidate frits) when a waste loading of 40% is targeted for Sludge Batches 8, 16, and 17, regardless of the addition of SCIX or SWPF streams. This indicates that the blending strategy for these sludge batches should be reevaluated by Savannah River Remediation (SRR). (2) In general, candidate frits were available to accommodate CST additions to either Tank 40 or Tank 51. A larger number of candidate frits were typically available for the sludge batches when CST is added to Tank 51 rather than Tank 40, meaning that more compositional flexibility would be available for frit selection and DWPF operation. Note however that for SB8 and SB17, no candidate frits were available to accommodate CST going to Tank 40 with and without SWPF streams. The addition of SWPF streams generally improves the number of candidate frits available for processing of a given sludge batch. (3) The change in production rate from 40 Sludge Receipt and Adjustment Tank (SRAT) batches per year (i.e., the current production rate) to 75 SRAT batches per year, without SWPF streams included, had varied results in terms of the number of candidate frits available for processing of a given sludge batch. Therefore, this variable is not of much concern in terms of incorporating the SCIX streams. Note that the evaluation at 75 SRAT batches per year (approximately equivalent to 325 canisters per year) is more conservative in terms of the impact of SCIX streams as compared to a production rate of 400 canisters per year. Overall, the outcome of this paper study shows no major issues with the ability to identify an acceptable glass processing window when CST from the SCIX process is transferred to either Tank 40 or Tank 51. The assumptions used and the model limitations identified in this report must be addressed through further experimental studies, which are currently being performed. As changes occur to the planned additions of MST and CST, or to the sludge batch preparation strategy, additional evaluations will be performed to determine the potential impacts. As stated above, the issues with Sludge Batches 8, 16, and 17 should be further evaluated by SRR. A review of Chemical Process Cell (CPC) processing identified no changes to the recommendations from the previous review of the SCIX process impacts. Recommendations for testing were made during the previous review to evaluate the impact of CST on the rheological properties of DWPF process streams and evaluate the impact of CST on catalytic hydrogen generation during CPC processing.

  11. The Facilities Audit. A Process for Improving Facilities Conditions.

    ERIC Educational Resources Information Center

    Kaiser, Harvey H.

    The problems of deferred maintenance and decaying campus infrastructure have troubled higher education for the past two decades. This book, designed to be a tool for facilities managers, describes a process for inspecting and reporting conditions of buildings and infrastructure. The audit process is meant to be a routine part of maintenance…

  12. Springfield Processing Plant (SPP) Facility Information

    SciTech Connect

    Leach, Janice; Torres, Teresa M.

    2012-10-01

    The Springfield Processing Plant is a hypothetical facility. It has been constructed for use in training workshops. Information is provided about the facility and its surroundings, particularly security-related aspects such as target identification, threat data, entry control, and response force data.

  13. AIRBORNE MICROORGANISMS IN SHELL EGG PROCESSING FACILITIES

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Total aerobic bacteria, molds/yeasts, coliforms and pseudomonads were determined in the air of three shell egg processing facilities (in-line, off-line and mixed operations) using MicroBio MB2 Air Samplers. Sites were sampled from each facility on three different days (replication) during the same ...

  14. Rapid-Solidification Processing Facility

    NASA Technical Reports Server (NTRS)

    Glasgow, Thomas K.; Jech, Robert W.; Moore, Thomas J.; Orth, Norman W.

    1987-01-01

    Microstructural changes enhance properties of alloys. Major feature of process is rapid quenching of alloys or intermetallic compounds from liquid to solid state at cooling rates of 10 to the 6th power C/s.

  15. SRS Process Facility Significance Fire Frequency

    SciTech Connect

    Sarrack, A.G.

    1995-10-01

    This report documents the method and assumptions of a study performed to determine a site generic process facility significant fire initiator frequency and explains the proper way this value should be used.

  16. SALTSTONE PROCESSING FACILITY TRANSFER SAMPLE

    SciTech Connect

    Cozzi, A.; Reigel, M.

    2010-08-04

    On May 19, 2010, the Saltstone Production Facility inadvertently transferred 1800 gallons of untreated waste from the salt feed tank to Vault 4. During shut down, approximately 70 gallons of the material was left in the Saltstone hopper. A sample of the slurry in the hopper was sent to Savannah River National Laboratory (SRNL) to analyze the density, pH and the eight Resource Conservation and Recovery Act (RCRA) metals. The sample was hazardous for chromium, mercury and pH. The sample received from the Saltstone hopper was analyzed visually while obtaining sample aliquots and while the sample was allowed to settle. It was observed that the sample contains solids that settle in approximately 20 minutes (Figure 3-1). There is a floating layer on top of the supernate during settling and disperses when the sample is agitated (Figure 3-2). The untreated waste inadvertently transferred from the SFT to Vault 4 was toxic for chromium and mercury. In addition, the pH of the sample is at the regulatory limit. Visually inspecting the sample indicates solids present in the sample.

  17. Skylab materials processing facility experiment developer's report

    NASA Technical Reports Server (NTRS)

    Parks, P. G.

    1975-01-01

    The development of the Skylab M512 Materials Processing Facility is traced from the design of a portable, self-contained electron beam welding system for terrestrial applications to the highly complex experiment system ultimately developed for three Skylab missions. The M512 experiment facility was designed to support six in-space experiments intended to explore the advantages of manufacturing materials in the near-zero-gravity environment of Earth orbit. Detailed descriptions of the M512 facility and related experiment hardware are provided, with discussions of hardware verification and man-machine interfaces included. An analysis of the operation of the facility and experiments during the three Skylab missions is presented, including discussions of the hardware performance, anomalies, and data returned to earth.

  18. The Medina County, Ohio, central processing facility

    SciTech Connect

    White, K.M.

    1994-08-01

    Before deciding on the appropriate county recycling facility for their communities, waste management officials from Medina County, Ohio, spent three years researching their options. First and foremost, they wanted to generate a recycling amount that would at least double House Bill 592's requirements which calls for a 25% reduction in reliance on landfill space. After issuing a request for proposals, the county opted for a central processing facility (CPF)--which was designed, built, and is now operated by Norton Environmental (Independence, Ohio). Currently, the CPF extracts and processes recyclables, materials for refuse-derived fuel (RDF), and compostables from a mixed solid waste stream. After operating for just over one year, the facility, which is located in Seville, Ohio, is well on its way to achieving its goal of recovering two-thirds of the county's incoming mixed solid waste stream, and waste management officials there couldn't be happier with their selection.

  19. Chemical process safety at fuel cycle facilities

    SciTech Connect

    Ayres, D.A.

    1997-08-01

    This NUREG provides broad guidance on chemical safety issues relevant to fuel cycle facilities. It describes an approach acceptable to the NRC staff, with examples that are not exhaustive, for addressing chemical process safety in the safe storage, handling, and processing of licensed nuclear material. It expounds to license holders and applicants a general philosophy of the role of chemical process safety with respect to NRC-licensed materials; sets forth the basic information needed to properly evaluate chemical process safety; and describes plausible methods of identifying and evaluating chemical hazards and assessing the adequacy of the chemical safety of the proposed equipment and facilities. Examples of equipment and methods commonly used to prevent and/or mitigate the consequences of chemical incidents are discussed in this document.

  20. Cogeneration at a milk processing facility

    SciTech Connect

    Jackowski, L.E. Jr.; Coles, R.L. )

    1988-01-01

    This paper describes the design aspects and operational considerations of a base loaded nominal 47MW combustion gas turbine heat recovery cogeneration plant located in Corona, California. The plant will sell electricity and steam to an adjacent milk processing facility and surplus electrical power to the local utility. The plant design incorporates a single General Electric PGLM5000 STIG aircraft derivative type natural gas fired combustion gas turbine with steam injection for nitrogen oxide (NO/sub chi/) suppression and power augmentation and a three pressure level head recovery boiler producing steam for use by the milk facility and the combustion gas turbine.

  1. Implementing change in the facilities planning process

    SciTech Connect

    Williams, J.L.

    1995-08-01

    In the post-Cold War climate of reduced budgets at the national laboratories, the Sites Planning Department at Sandia National Laboratories was faced with the problem of securing funding for capital construction projects in a very competitive environment. The Department of Energy (DOE), felt that requests for new facilities were not always well coordinated with its mission needs. The Sites Planning Department needed to revolutionize the way they were doing business. To be successful in obtaining approval and funding for future facilities, they recognized the need to concentrate their efforts on project proposals that tap strategic programs at DOE. The authors developed a series of new processes to identify, evaluate, prioritize, and develop line item project proposals to request approval and obtain funding. A matrixed group of sites and facilities directors was formed to establish criteria and make preliminary recommendations to upper management. Matrixed working groups were also established at the staff level to develop and prepare projects for the prioritization process. Ultimately, similar processes will be applied to all project types, and a prioritized plan generated for each. These plans will become the blueprint for an overarching strategic site plan. What started as a means of increasing success in obtaining approval and funding of capital projects has launched a whole new approach to project development that permits incorporation of facilities planning into overall corporate strategic planning.

  2. Process Waste Assessment Electroplating Research Facility

    SciTech Connect

    Phillips, N.M.

    1992-06-01

    This process Waste Assessment was conducted on the Electroplating Research Facility to identify waste generating processes with the goal of minimizing hazardous wastes. The primary focus was on the hazardous chemical and toxic waste streams with special attention given to the Oakite 90 alkaline cleaning solution. It was concluded that this facility, which contributes less than 1% of the hazardous wastes to the site`s overall waste stream, is committed to minimization of hazardous wastes. It is recommended that a research program be implemented to study the possibility of replacing the Oakite 90 cleaning solution with a less hazardous one and/or minimizing its volume of waste. Instituting a formal documentation system to keep track of the most used raw materials would be helpful also.

  3. Defense Waste Processing Facility Process Simulation Package Life Cycle

    SciTech Connect

    Reuter, K.

    1991-12-31

    The Defense Waste Processing Facility (DWPF) will be used to immobilize high level liquid radioactive waste into safe, stable, and manageable solid form. The complexity and classification of the facility requires that a performance based operator training to satisfy Department of Energy orders and guidelines. A major portion of the training program will be the application and utilization of Process Simulation Packages to assist in training the Control Room Operators on the fluctionality of the process and the application of the Distribution Control System (DCS) in operating and managing the DWPF process. The packages are being developed by the DWPF Computer and Information Systems Simulation Group. This paper will describe the DWPF Process Simulation Package Life Cycle. The areas of package scope, development, validation, and configuration management will be reviewed and discussed in detail.

  4. Defense Waste Processing Facility Process Simulation Package Life Cycle

    SciTech Connect

    Reuter, K.

    1991-01-01

    The Defense Waste Processing Facility (DWPF) will be used to immobilize high level liquid radioactive waste into safe, stable, and manageable solid form. The complexity and classification of the facility requires that a performance based operator training to satisfy Department of Energy orders and guidelines. A major portion of the training program will be the application and utilization of Process Simulation Packages to assist in training the Control Room Operators on the fluctionality of the process and the application of the Distribution Control System (DCS) in operating and managing the DWPF process. The packages are being developed by the DWPF Computer and Information Systems Simulation Group. This paper will describe the DWPF Process Simulation Package Life Cycle. The areas of package scope, development, validation, and configuration management will be reviewed and discussed in detail.

  5. Salt Waste Processing Pilot Facility Feed Basis for Design

    SciTech Connect

    Pike, J.A.

    2001-10-09

    This paper presents the characterization of potential feed to the Salt Waste Processing Facility pilot facility for design purposes and supercedes any previous representations of feed to the pilot facility.

  6. Node 2 In Space Station Processing Facility

    NASA Technical Reports Server (NTRS)

    2003-01-01

    The U.S. Node 2 awaits launch in the Space Station Processing Facility at the Kennedy Space Center (KSC) since its arrival on June 1, 2003. Node 2, the 'utility hub' and second of three connectors between International Space Station (ISS) modules, was built in the Torino, Italy facility of Alenia Spazio, an International contractor based in Rome. Alenia built Node 2 as part of an agreement between NASA and the European Space Agency (ESA). Weighing in at approximately 30,000 pounds, the Node is more than 20-feet long and 14.5-feet wide. This centerpiece of the ISS will be the next pressurized module installed on the Station and will result in a roomier Station, allowing it to expand from the equivalent space of a 3-bedroom house to a 5-bedroom house once the Japanese and European laboratories are attached to it. The Marshall Space Center in Huntsville, Alabama manages the Node program for NASA.

  7. Process, optimized acidizing reduce production facility upsets

    SciTech Connect

    Ali, S.A.; Hill, D.G.; McConnell, S.B.; Johnson, M.R.

    1997-02-10

    The filtration/absorption process, coupled with optimum treatments, prevent facility upsets that increase the time and resources required for bringing a well back on-line following an acid stimulation. Surface active agents, required in acidizing to improve well productivity, can form oil/water emulsions and cause unacceptable oil and grease levels during acid flowback. But recent offshore experiences after acidizing show that operators can achieve oil and grease discharge limits without facility upsets. To minimize oil and grease, the additives need to be optimized by adding a mutual breakout solvent (MBS). MBS has the dual function of being a mutual solvent and a sludge and emulsion control additive. The paper discusses acidizing problems, acid additives, handling options, and a case history of the Main Pass A field.

  8. A Central Processing Facility within a Distributed Data Processing System

    NASA Astrophysics Data System (ADS)

    de Witte, S.; Rispens, S. M.; van Hees, R. M.

    2009-04-01

    In a complex scientific data processing project, where raw satellite data (Level 1) is processed to end products (Level 2), you may need specific expertise from various groups in different locations. Collaboration between these groups can lead to better results and give the opportunity to try several different scientific approaches and choose, objectively, the best result. Furthermore, such a distributed data processing system or DDPS can be used for independent validation before the end products are released. All participating groups need common and specific data products for their processing. This involves many interfaces needing and producing different data products. Without a central storage location all groups involved have to implement their own checking routines and transformations in order to use the data products. A central processing facility, acting as a single point of interface between the DDPS and the main data provider as well as for all groups within the DDPS, can facilitate in collecting all scientific data necessary for high-level processing, transforming the Level 1 input data to a DDPS internally agreed format, checking all data products on integrity, format and validity, distributing these data products within the DDPS, monitoring the whole data distribution chain and distributing all end products to the main data provider. A DDPS has been implemented for ESA's gravity mission, GOCE (Gravity field and steady-state Ocean Circulation Explorer). GOCE's DDPS is called the High-level Processing Facility (HPF) and is part of the GOCE Ground Segment, developed under ESA contract by the European GOCE Gravity consortium (EGG-c). The HPF is set up as a distributed facility consisting of several sub-processing centers for scientific pre-processing, orbit determination, gravity field analysis and validation. The sub-processing facilities are connected through a central node, the Central Processing Facility (CPF). The CPF has been thoroughly tested and is ready to accept real GOCE data. The CPF concept and its unique features can be very useful for future missions that require complex scientific data processing in different locations.

  9. Process auditing in long term care facilities.

    PubMed

    Hewitt, S M; LeSage, J; Roberts, K L; Ellor, J R

    1985-01-01

    The ECC tool development and audit experiences indicated that there is promise in developing a process audit tool to monitor quality of care in nursing homes; moreover, the tool selected required only one hour per resident. Focusing on the care process and resident needs provided useful information for care providers at the unit level as well as for administrative personnel. Besides incorporating a more interdisciplinary focus, the revised tool needs to define support services most appropriate for nursing homes, includes items related to discharge planning and increases measurement of significant others' involvement in the care process. Future emphasis at the ECC will focus on developing intervention plans to maintain strengths and correct deficiencies identified in the audits. Various strategies to bring about desired changes in the quality of care will be evaluated through regular, periodic monitoring. Having a valid and reliable measure of quality of care as a tool will be an important step forward for LTC facilities. PMID:3919355

  10. Facilities for pyrochemical process studies at ENEA

    SciTech Connect

    De Angelis, G.; Fedeli, C.; Tiranti, G.; Baicchi, E.

    2013-07-01

    Some facilities have successfully been installed at ENEA laboratories for pyrochemical process studies under inactive conditions. PYREL III, MECRYP and OGATA plants allow to perform experiments about electrorefining and electroreduction of simulated fuel, melt crystallization of lithium chloride containing impurities from electroreduction campaigns, and trapping of volatile and semi-volatile fission products. Moreover, an argon-atmosphere glove-box is used for conditioning of chloride salt wastes with sodalite or SAP (SiO{sub 2}-Al{sub 2}O{sub 3}-P{sub 2}O{sub 5}) matrix.

  11. Dialysis Facility Safety: Processes and Opportunities.

    PubMed

    Garrick, Renee; Morey, Rishikesh

    2015-01-01

    Unintentional human errors are the source of most safety breaches in complex, high-risk environments. The environment of dialysis care is extremely complex. Dialysis patients have unique and changing physiology, and the processes required for their routine care involve numerous open-ended interfaces between providers and an assortment of technologically advanced equipment. Communication errors, both within the dialysis facility and during care transitions, and lapses in compliance with policies and procedures are frequent areas of safety risk. Some events, such as air emboli and needle dislodgments occur infrequently, but are serious risks. Other adverse events include medication errors, patient falls, catheter and access-related infections, access infiltrations and prolonged bleeding. A robust safety system should evaluate how multiple, sequential errors might align to cause harm. Systems of care can be improved by sharing the results of root cause analyses, and "good catches." Failure mode effects and analyses can be used to proactively identify and mitigate areas of highest risk, and methods drawn from cognitive psychology, simulation training, and human factor engineering can be used to advance facility safety. PMID:26073909

  12. 10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Requirements for new facilities or new processes at existing facilities. 70.64 Section 70.64 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC... Critical Mass of Special Nuclear Material 70.64 Requirements for new facilities or new processes...

  13. 10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Requirements for new facilities or new processes at existing facilities. 70.64 Section 70.64 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC... Critical Mass of Special Nuclear Material 70.64 Requirements for new facilities or new processes...

  14. 10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Requirements for new facilities or new processes at... Critical Mass of Special Nuclear Material § 70.64 Requirements for new facilities or new processes at... following baseline design criteria in the design of new facilities. Each existing licensee shall address...

  15. Pinellas Plant facts. [Products, processes, laboratory facilities

    SciTech Connect

    Not Available

    1986-09-01

    This plant was built in 1956 in response to a need for the manufacture of neutron generators, a principal component in nuclear weapons. The neutron generators consist of a miniaturized linear ion accelerator assembled with the pulsed electrical power supplies required for its operation. The ion accelerator, or neutron tube, requires ultra clean, high vacuum technology: hermetic seals between glass, ceramic, glass-ceramic, and metal materials: plus high voltage generation and measurement technology. The existence of these capabilities at the Pinellas Plant has led directly to the assignment of the lightning arrester connector, specialty capacitor, vacuum switch, and crystal resonator. Active and reserve batteries and the radioisotopically-powered thermoelectric generator draw on the materials measurement and controls technologies which are required to ensure neutron generator life. A product development and production capability in alumina ceramics, cermet (electrical) feedthroughs, and glass ceramics has become a specialty of the plant; the laboratories monitor the materials and processes used by the plant's commercial suppliers of ferroelectric ceramics. In addition to the manufacturing facility, a production development capability is maintained at the Pinellas Plant.

  16. 10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Requirements for new facilities or new processes at existing facilities. 70.64 Section 70.64 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC... single element of the design, construction, maintenance, or operation of the facility. The net effect...

  17. 15 CFR 923.13 - Energy facility planning process.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Energy facility planning process. 923... RESOURCE MANAGEMENT COASTAL ZONE MANAGEMENT PROGRAM REGULATIONS Uses Subject to Management § 923.13 Energy facility planning process. The management program must contain a planning process for energy...

  18. 15 CFR 923.13 - Energy facility planning process.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 15 Commerce and Foreign Trade 3 2011-01-01 2011-01-01 false Energy facility planning process. 923... RESOURCE MANAGEMENT COASTAL ZONE MANAGEMENT PROGRAM REGULATIONS Uses Subject to Management § 923.13 Energy facility planning process. The management program must contain a planning process for energy...

  19. 9 CFR 590.546 - Albumen flake process drying facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Albumen flake process drying facilities. 590.546 Section 590.546 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.546 Albumen flake process...

  20. 9 CFR 590.546 - Albumen flake process drying facilities.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 9 Animals and Animal Products 2 2013-01-01 2013-01-01 false Albumen flake process drying facilities. 590.546 Section 590.546 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.546 Albumen flake process...

  1. 9 CFR 590.546 - Albumen flake process drying facilities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 9 Animals and Animal Products 2 2012-01-01 2012-01-01 false Albumen flake process drying facilities. 590.546 Section 590.546 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.546 Albumen flake process...

  2. 9 CFR 590.546 - Albumen flake process drying facilities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 9 Animals and Animal Products 2 2014-01-01 2014-01-01 false Albumen flake process drying facilities. 590.546 Section 590.546 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.546 Albumen flake process...

  3. 9 CFR 590.546 - Albumen flake process drying facilities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 9 Animals and Animal Products 2 2011-01-01 2011-01-01 false Albumen flake process drying facilities. 590.546 Section 590.546 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE... INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.546 Albumen flake process...

  4. 15 CFR 923.13 - Energy facility planning process.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 15 Commerce and Foreign Trade 3 2014-01-01 2014-01-01 false Energy facility planning process. 923... RESOURCE MANAGEMENT COASTAL ZONE MANAGEMENT PROGRAM REGULATIONS Uses Subject to Management § 923.13 Energy facility planning process. The management program must contain a planning process for energy...

  5. 15 CFR 923.13 - Energy facility planning process.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 15 Commerce and Foreign Trade 3 2012-01-01 2012-01-01 false Energy facility planning process. 923... RESOURCE MANAGEMENT COASTAL ZONE MANAGEMENT PROGRAM REGULATIONS Uses Subject to Management § 923.13 Energy facility planning process. The management program must contain a planning process for energy...

  6. 15 CFR 923.13 - Energy facility planning process.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 15 Commerce and Foreign Trade 3 2013-01-01 2013-01-01 false Energy facility planning process. 923... RESOURCE MANAGEMENT COASTAL ZONE MANAGEMENT PROGRAM REGULATIONS Uses Subject to Management § 923.13 Energy facility planning process. The management program must contain a planning process for energy...

  7. Safeguards Approaches for Black Box Processes or Facilities

    SciTech Connect

    Diaz-Marcano, Helly; Gitau, Ernest TN; Hockert, John; Miller, Erin; Wylie, Joann

    2013-09-25

    The objective of this study is to determine whether a safeguards approach can be developed for “black box” processes or facilities. These are facilities where a State or operator may limit IAEA access to specific processes or portions of a facility; in other cases, the IAEA may be prohibited access to the entire facility. The determination of whether a black box process or facility is safeguardable is dependent upon the details of the process type, design, and layout; the specific limitations on inspector access; and the restrictions placed upon the design information that can be provided to the IAEA. This analysis identified the necessary conditions for safeguardability of black box processes and facilities.

  8. Northwestern University Facility for Clean Catalytic Process Research

    SciTech Connect

    Marks, Tobin Jay

    2013-05-08

    Northwestern University with DOE support created a Facility for Clean Catalytic Process Research. This facility is designed to further strengthen our already strong catalysis research capabilities and thus to address these National challenges. Thus, state-of-the art instrumentation and experimentation facility was commissioned to add far greater breadth, depth, and throughput to our ability to invent, test, and understand catalysts and catalytic processes, hence to improve them via knowledge-based design and evaluation approaches.

  9. Managing the Rural School Facility Construction Process.

    ERIC Educational Resources Information Center

    Passarelli, Angelo; Goehring, Wade; Harley, Anne

    The decision to renovate or replace a school building is the starting point for a long and challenging journey with many phases: planning, development, and project delivery and construction. Each phase requires different levels of expertise, skills, and activities. The challenge of a rural facility project is to find leadership to provide guidance…

  10. 47 CFR 3.42 - Location of processing facility.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Location of processing facility. 3.42 Section 3.42 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL AUTHORIZATION AND ADMINISTRATION OF... Location of processing facility. Settlement of maritime mobile and maritime mobile-satellite...

  11. 47 CFR 3.42 - Location of processing facility.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... 47 Telecommunication 1 2013-10-01 2013-10-01 false Location of processing facility. 3.42 Section 3.42 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL AUTHORIZATION AND ADMINISTRATION OF... Location of processing facility. Settlement of maritime mobile and maritime mobile-satellite...

  12. 47 CFR 3.42 - Location of processing facility.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... 47 Telecommunication 1 2014-10-01 2014-10-01 false Location of processing facility. 3.42 Section 3.42 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL AUTHORIZATION AND ADMINISTRATION OF... Location of processing facility. Settlement of maritime mobile and maritime mobile-satellite...

  13. 47 CFR 3.42 - Location of processing facility.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 47 Telecommunication 1 2011-10-01 2011-10-01 false Location of processing facility. 3.42 Section 3.42 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL AUTHORIZATION AND ADMINISTRATION OF... Location of processing facility. Settlement of maritime mobile and maritime mobile-satellite...

  14. 47 CFR 3.42 - Location of processing facility.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 47 Telecommunication 1 2012-10-01 2012-10-01 false Location of processing facility. 3.42 Section 3.42 Telecommunication FEDERAL COMMUNICATIONS COMMISSION GENERAL AUTHORIZATION AND ADMINISTRATION OF... Location of processing facility. Settlement of maritime mobile and maritime mobile-satellite...

  15. 40 CFR 52.279 - Food processing facilities.

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS California § 52.279 Food processing facilities. (a) The following regulations are disapproved because they conflict with the requirements of 40 CFR... 40 Protection of Environment 3 2011-07-01 2011-07-01 false Food processing facilities....

  16. 40 CFR 52.279 - Food processing facilities.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... (CONTINUED) APPROVAL AND PROMULGATION OF IMPLEMENTATION PLANS California § 52.279 Food processing facilities. (a) The following regulations are disapproved because they conflict with the requirements of 40 CFR... 40 Protection of Environment 3 2010-07-01 2010-07-01 false Food processing facilities....

  17. 10 CFR 1016.9 - Processing security facility approval.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 4 2014-01-01 2014-01-01 false Processing security facility approval. 1016.9 Section 1016.9 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.9 Processing security facility approval. The following receipt of an acceptable request...

  18. 10 CFR 1016.9 - Processing security facility approval.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 4 2013-01-01 2013-01-01 false Processing security facility approval. 1016.9 Section 1016.9 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.9 Processing security facility approval. The following receipt of an acceptable request...

  19. 10 CFR 1016.9 - Processing security facility approval.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 4 2011-01-01 2011-01-01 false Processing security facility approval. 1016.9 Section 1016.9 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.9 Processing security facility approval. The following receipt of an acceptable request...

  20. 10 CFR 1016.9 - Processing security facility approval.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 4 2012-01-01 2012-01-01 false Processing security facility approval. 1016.9 Section 1016.9 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.9 Processing security facility approval. The following receipt of an acceptable request...

  1. 10 CFR 70.72 - Facility changes and change process.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Facility changes and change process. 70.72 Section 70.72... Material § 70.72 Facility changes and change process. (a) The licensee shall establish a configuration...) The technical basis for the change; (2) Impact of the change on safety and health or control...

  2. 10 CFR 70.72 - Facility changes and change process.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Facility changes and change process. 70.72 Section 70.72... Material § 70.72 Facility changes and change process. (a) The licensee shall establish a configuration...) The technical basis for the change; (2) Impact of the change on safety and health or control...

  3. 10 CFR 70.72 - Facility changes and change process.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Facility changes and change process. 70.72 Section 70.72... Material § 70.72 Facility changes and change process. (a) The licensee shall establish a configuration...) The technical basis for the change; (2) Impact of the change on safety and health or control...

  4. 10 CFR 70.72 - Facility changes and change process.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Facility changes and change process. 70.72 Section 70.72... Material § 70.72 Facility changes and change process. (a) The licensee shall establish a configuration...) The technical basis for the change; (2) Impact of the change on safety and health or control...

  5. An Overview of the Facilities Master Plan Process Purpose.

    ERIC Educational Resources Information Center

    2002

    This paper provides a description of facilities master plans and the process of creating one. According to the paper, the purpose of the plan is to develop and communicate an efficient process to change a district's school facilities to better accommodate and support its current and future educational programs on a regularly updated basis. The

  6. 10 CFR 1016.9 - Processing security facility approval.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Processing security facility approval. 1016.9 Section 1016.9 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security § 1016.9 Processing security facility approval. The following receipt of an acceptable request...

  7. Automation in a material processing/storage facility

    SciTech Connect

    Peterson, K.; Gordon, J.

    1997-05-01

    The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, therefore, be accomplished in a rational and disciplined manner to satisfy the strict operational requirements of the facility. Among the functions to be automated are the transport of containers between process and storage areas via an Automatic Guided Vehicle (AGV), and various processes in the Shipping Package Unpackaging (SPU) area, the Accountability Measurements (AM) area, the Special Isotope Storage (SIS) vault and the Special Nuclear Materials (SNM) vault. Other areas of the facility are also being automated, but are outside the scope of this paper.

  8. Saltstone studies using the scaled continuous processing facility

    SciTech Connect

    Fowley, M. D.; Cozzi, A. D.; Hansen, E. K.

    2015-08-01

    The Savannah River National Laboratory (SRNL) has supported the Saltstone Facility since its conception with bench-scale laboratory experiments, mid-scale testing at vendor facilities, and consultations and testing at the Saltstone Facility. There have been minimal opportunities for the measurement of rheological properties of the grout slurry at the Saltstone Production Facility (SPF); thus, the Scaled Continuous Processing Facility (SCPF), constructed to provide processing data related to mixing, transfer, and other operations conducted in the SPF, is the most representative process data for determining the expected rheological properties in the SPF. These results can be used to verify the laboratory scale experiments that support the SPF using conventional mixing processes that appropriately represent the shear imparted to the slurry in the SPF.

  9. Integration Process for Payloads in the Fluids and Combustion Facility

    NASA Technical Reports Server (NTRS)

    Free, James M.; Nall, Marsha M.

    2001-01-01

    The Fluids and Combustion Facility (FCF) is an ISS research facility located in the United States Laboratory (US Lab), Destiny. The FCF is a multi-discipline facility that performs microgravity research primarily in fluids physics science and combustion science. This facility remains on-orbit and provides accommodations to multi-user and Principal investigator (PI) unique hardware. The FCF is designed to accommodate 15 PI's per year. In order to allow for this number of payloads per year, the FCF has developed an end-to-end analytical and physical integration process. The process includes provision of integration tools, products and interface management throughout the life of the payload. The payload is provided with a single point of contact from the facility and works with that interface from PI selection through post flight processing. The process utilizes electronic tools for creation of interface documents/agreements, storage of payload data and rollup for facility submittals to ISS. Additionally, the process provides integration to and testing with flight-like simulators prior to payload delivery to KSC. These simulators allow the payload to test in the flight configuration and perform final facility interface and science verifications. The process also provides for support to the payload from the FCF through the Payload Safety Review Panel (PSRP). Finally, the process includes support in the development of operational products and the operation of the payload on-orbit.

  10. Development of a Microwave Facility for Processing Lunar Regolith

    NASA Technical Reports Server (NTRS)

    Barmatz, Martin B.; Hays, Charles C.; Meek, T. T.

    2006-01-01

    This viewgraph presentation reviews in this Roadmap for Developing a Lunar Microwave Facility an approach to determine the source of the enhanced microwave heating of Lunar Regolith. A set of microwave heating studies were proposed for a specially designed realistic simulant to determine optimum processing parameters. Apollo lunar soil will be used to validate the heating features found for the simulant. We have also introduced several possible designs for a future lunar microwave processing facility. In the future when sufficient funds become available, a microwave facility for processing regolith on the lunar surface will be ready to be built

  11. Control of DWPF (Defense Waste Processing Facility) melter feed composition

    SciTech Connect

    Edwards, R.E. Jr.; Brown, K.G.; Postles, R.L.

    1990-01-01

    The Defense Waste Processing Facility will be used to immobilize Savannah River Site high-level waste into a stable borosilicate glass for disposal in a geologic repository. Proper control of the melter feed composition in this facility is essential to the production of glass which meets product durability constraints dictated by repository regulations and facility processing constraints dictated by melter design. A technique has been developed which utilizes glass property models to determine acceptable processing regions based on the multiple constraints imposed on the glass product and to display these regions graphically. This system along with the batch simulation of the process is being used to form the basis for the statistical process control system for the facility. 13 refs., 3 figs., 1 tab.

  12. Insect pest management decisions in food processing facilities

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Pest management decision making in food processing facilities such as flour mills, rice mills, human and pet food manufacturing facilities, distribution centers and warehouses, and retail stores is a challenging undertaking. Insect pest management programs require an understanding of the food facili...

  13. 77 FR 823 - Guidance for Fuel Cycle Facility Change Processes

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-06

    ... experience from nuclear fuel cycle facilities shows that past incidents often resulted from changes... Information DG-3037 was published in the Federal Register on July 14, 2011 (76 FR 41527). The public comment... COMMISSION Guidance for Fuel Cycle Facility Change Processes AGENCY: Nuclear Regulatory Commission....

  14. Metals Processing Laboratory User Facility: Facilities capabilities; Interactive programs; Recent experience

    SciTech Connect

    Mackiewicz-Ludtka, G.; Raschke, R.A.

    1998-02-12

    MPLUS is a DOE designated User Facility providing extensive Technical Expertise and Specialized Facilities to assist Industrial and Academic Partners in becoming more Energy Efficient and enhancing US Competitiveness in the World market. MPLUS focusing on 7 major vision industries (aluminum, chemical, forest products, glass, metals castings, refineries, and steel) identified by DOE as being energy intensive, as well as cross-cutting industries such as welding and heat treating. MPLUS consists of four primary facilities: (1) Materials Processing, (2) Materials Joining, (3) Materials Characterization and Properties, and (4) Materials Process Modeling. Each facility provides rapid access to unique, state-of-the-art equipment, capabilities, and technical expertise necessary for solving materials processing issues that limit the development and implementation of emerging technologies. These capabilities include: (1) materials synthesis; (2) deformation processing; (3) materials characterization; (4) joining and mathematical modeling.

  15. Spacelab Data Processing Facility (SLDPF) quality assurance expert systems development

    NASA Technical Reports Server (NTRS)

    Kelly, Angelita C.; Basile, Lisa; Ames, Troy; Watson, Janice; Dallam, William

    1987-01-01

    Spacelab Data Processing Facility (SLDPF) expert system prototypes have been developed to assist in the quality assurance of Spacelab and/or Attached Shuttle Payload (ASP) processed telemetry data. SLDPF functions include the capturing, quality monitoring, processing, accounting, and forwarding of mission data to various user facilities. Prototypes for the two SLDPF functional elements, the Spacelab Output Processing System and the Spacelab Input Processing Element, are described. The prototypes have produced beneficial results including an increase in analyst productivity, a decrease in the burden of tedious analyses, the consistent evaluation of data, and the providing of concise historical records.

  16. Spacelab Data Processing Facility (SLDPF) quality assurance expert systems development

    NASA Technical Reports Server (NTRS)

    Kelly, Angelita C.; Basile, Lisa; Ames, Troy; Watson, Janice; Dallam, William

    1987-01-01

    Spacelab Data Processing Facility (SLDPF) expert system prototypes were developed to assist in the quality assurance of Spacelab and/or Attached Shuttle Payload (ASP) processed telemetry data. The SLDPF functions include the capturing, quality monitoring, processing, accounting, and forwarding of mission data to various user facilities. Prototypes for the two SLDPF functional elements, the Spacelab Output Processing System and the Spacelab Input Processing Element, are described. The prototypes have produced beneficial results including an increase in analyst productivity, a decrease in the burden of tedious analyses, the consistent evaluation of data, and the providing of concise historical records.

  17. Design criteria for Waste Coolant Processing Facility and preliminary proposal 722 for Waste Coolant Processing Facility

    SciTech Connect

    Not Available

    1991-09-27

    This document contains the design criteria to be used by the architect-engineer (A-E) in the performance of Titles 1 and 2 design for the construction of a facility to treat the biodegradable, water soluble, waste machine coolant generated at the Y-12 plant. The purpose of this facility is to reduce the organic loading of coolants prior to final treatment at the proposed West Tank Farm Treatment Facility.

  18. Skylab M512 Materials Processing Facility (MPF) with the M518 Multipurpose Electric Facility (MEF)

    NASA Technical Reports Server (NTRS)

    2004-01-01

    The M512 Materials Processing Facility (MPF) with the M518 Multipurpose Electric Facility (MEF) tested and demonstrated a facility approach for materials process experimentation in space. It also provided a basic apparatus and a common interface for a group of metallic and nonmetallic materials experiments. The MPF consisted of a vacuum work chamber and associated mechanical and electrical controls. The M518 Multipurpose Electric Furnace (MEF) was an electric furnace system in which solidification, crystal growth, and other experiments involving phase changes were performed.

  19. Ninth Processing Campaign in the Waste Calcining Facility

    SciTech Connect

    Childs, K F; Donovan, R I; Swenson, M C

    1982-04-01

    This report discusses the Ninth (and final) Processing Campaign at the Waste Calcining Facility. Several processing interruptions were experienced during this campaign and the emphasis of this report is on process and equipment performance with operating problems and corrective actions discussed in detail.

  20. Opportunities for Process Monitoring Techniques at Delayed Access Facilities

    SciTech Connect

    Curtis, Michael M.; Gitau, Ernest TN; Johnson, Shirley J.; Schanfein, Mark; Toomey, Christopher

    2013-09-20

    Except for specific cases where the International Atomic Energy Agency (IAEA) maintains a continuous presence at a facility (such as the Japanese Rokkasho Reprocessing Plant), there is always a period of time or delay between the moment a State is notified or aware of an upcoming inspection, and the time the inspector actually enters the material balance area or facility. Termed by the authors as “delayed access,” this period of time between inspection notice and inspector entrance to a facility poses a concern. Delayed access also has the potential to reduce the effectiveness of measures applied as part of the Safeguards Approach for a facility (such as short-notice inspections). This report investigates the feasibility of using process monitoring to address safeguards challenges posed by delayed access at a subset of facility types.

  1. Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations

    SciTech Connect

    Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

    1997-06-01

    The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation`s first and world`s largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage.

  2. Defense waste processing facility radioactive operations. Part 1 - operating experience

    SciTech Connect

    Little, D.B.; Gee, J.T.; Barnes, W.M.

    1997-12-31

    The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation`s first and the world`s largest vitrification facility. Following a ten year construction program and a 3 year non-radioactive test program, DWPF began radioactive operations in March 1996. This paper presents the results of the first 9 months of radioactive operations. Topics include: operations of the remote processing equipment reliability, and decontamination facilities for the remote processing equipment. Key equipment discussed includes process pumps, telerobotic manipulators, infrared camera, Holledge{trademark} level gauges and in-cell (remote) cranes. Information is presented regarding equipment at the conclusion of the DWPF test program it also discussed, with special emphasis on agitator blades and cooling/heating coil wear. 3 refs., 4 figs.

  3. Mock Nuclear Processing Facility-Safeguards Training Requirements

    SciTech Connect

    Gibbs, Philip; Hasty, Tim; Johns, Rissell; Baum, Gregory

    2014-08-31

    This document outlines specific training requirements in the topical areas of Material Control and Accounting (MC&A) and Physical Protection(PP) which are to be used as technical input for designing a mock Integrated Security Facility (ISF) at Sandia National Laboratories (SNL). The overall project objective for these requirements is to enhance the ability to deliver training on Material Protection Control and Accounting (MC&A) concepts regarding hazardous material such as irradiated materials with respect to bulk processing facilities.

  4. NASA Construction of Facilities Validation Processes - Total Building Commissioning (TBCx)

    NASA Technical Reports Server (NTRS)

    Hoover, Jay C.

    2004-01-01

    Key Atributes include: Total Quality Management (TQM) System that looks at all phases of a project. A team process that spans boundaries. A Commissioning Authority to lead the process. Commissioning requirements in contracts. Independent design review to verify compliance with Facility Project Requirements (FPR). Formal written Commissioning Plan with Documented Results. Functional performance testing (FPT) against the requirements document.

  5. Overview of the Facility Safeguardability Analysis (FSA) Process

    SciTech Connect

    Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Shirley J.; Wigeland, Roald; Zentner, Michael D.

    2011-10-10

    The safeguards system of the International Atomic Energy Agency (IAEA) provides the international community with credible assurance that a State is fulfilling its nonproliferation obligations. The IAEA draws such conclusions from the evaluation of all available information. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of this “State-level” approach. Efficiently used, the Safeguards by Design (SBD) methodologies , , , now being developed can contribute to effective and cost-efficient facility-level safeguards. The Facility Safeguardability Assessment (FSA) introduced here supports SBD in three areas. 1. It describes necessary interactions between the IAEA, the State regulator, and the owner / designer of a new or modified facility to determine where SBD efforts can be productively applied, 2. It presents a screening approach intended to identify potential safeguard issues for; a) design changes to existing facilities; b) new facilities similar to existing facilities with approved safeguards approaches, and c) new designs, 3. It identifies resources (the FSA toolkit), such as good practice guides, design guidance, and safeguardability evaluation methods that can be used by the owner/designer to develop solutions for potential safeguards issues during the interactions with the State regulator and IAEA. FSA presents a structured framework for the application of the SBD tools developed in other efforts. The more a design evolves, the greater the probability that new safeguards issues could be introduced. Likewise, for first-of-a-kind facilities or research facilities that involve previously unused processes or technologies, it is reasonable to expect that a number of possible safeguards issues might exist. Accordingly, FSA is intended to help the designer and its safeguards experts identify early in the design process: • Areas where elements of previous accepted safeguards approach(es) may be applied to facility modifications or new designs • Modifications of the design that could mitigate a potential safeguards issue or facilitate a more efficient application of the safeguards approach • Possible innovative ideas for more efficient application of safeguards • The potential for changes in elements of the safeguard approach that may be required by IAEA as a result of facility design features and characteristics • Other potential concerns These issues will then be presented to the IAEA and the state regulator to be resolved in a timely manner, ensuring that the planned safeguards approach is acceptable and compatible with the facility design. The proposed approach should be validated by application to suitable facilities to assess its utility, comprehensiveness, and cost-effectiveness. The approach and example application should also be reviewed by industry to confirm the conclusions reached in the DOE review.

  6. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    SciTech Connect

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

  7. Design and construction innovations of the Defense Waste Processing Facility

    SciTech Connect

    McKibben, J.M.; Pair, C.R.; Bethmann, H.K.

    1990-01-01

    Construction of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) is essentially complete. The facility is designed to convert high level radioactive waste, now contained in large steel tanks as aqueous salts and sludge, into borosilicate glass which will solidify in stainless steel canisters. All processing of the radioactive material and operations in a radioactive environment will be done remotely. The stringent requirements dictated by remote operation and new approaches to the glassification process led to the development of a number of first-of-a-kind pieces of equipment, new construction fabrication and erection techniques, and new applications of old techniques. The design features and construction methods used in the vitrification building and its equipment were to accomplish the objective of providing a state-of-the-art vitrification facility. 3 refs., 10 figs.

  8. Facility effluent monitoring plan for the Waste Receiving and Processing Facility Module 1

    SciTech Connect

    Lewis, C.J.

    1995-10-01

    A facility effluent monitoring plan is required by the US Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal state, and local requirements. This facility effluent monitoring plan shall ensure lonq-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years.

  9. Standard process for the roles and responsibilities for facility reuse of DOE Oak Ridge Reservation Facilities

    SciTech Connect

    Loebl, A.S.; Trost, D.G.; Pastel, J.A.; Payne, S.G.; Fleenor, R.M.

    1996-04-01

    The purpose of this report is to provide an understanding of the standard process for the lease or sale of facilities, equipment, and real property for the Oak Ridge Reservation (ORR). The objective of this process is to facilitate the reindustrialization of the ORR for the Department of Energy (DOE). The roles and responsibilities in this standard, as defined in the attached narrative and flow diagrams, were agreed upon among various representatives from the DOE-Oak Ridge Operations Office (DOE-ORO), Lockheed Martin Energy Systems, Inc. (LMES), and the Community Reuse Organization of East Tennessee (CROET). Reindustrialization for the DOE encompasses several areas which include: facilities reuse, materials and equipment recycling, and worker transition activities. The DOE-ORO`s vision for the ORR is to have completed the reindustrialization activities for the K-25 Site by the year 2010. Several steps have already been taken to aggressively pursue this vision, such as determining the most efficient and cost-effective ways to expedite the facilities reuse process. This report provides the time-phased, step-by-step, process for the lease or sale of facilities, equipment, land, and suggestions on streamlining the required regulatory processes.

  10. Spacelab Data Processing Facility (SLDPF) quality assurance expert systems development

    NASA Technical Reports Server (NTRS)

    Basile, Lisa R.; Kelly, Angelita C.

    1987-01-01

    The Spacelab Data Processing Facility (SLDPF) is an integral part of the Space Shuttle data network for missions that involve attached scientific payloads. Expert system prototypes were developed to aid in the performance of the quality assurance function of the Spacelab and/or Attached Shuttle Payloads processed telemetry data. The Spacelab Input Processing System (SIPS) and the Spacelab Output Processing System (SOPS), two expert systems, were developed to determine their feasibility and potential in the quality assurance of processed telemetry data. The capabilities and performance of these systems are discussed.

  11. ANALYTICAL PLANS SUPPORTING THE SWPF GAP ANALYSIS BEING CONDUCTED WITH ENERGYSOLUTIONS AND THE VITREOUS STATE LABORATORY AT THE CUA

    SciTech Connect

    Edwards, T.; Peeler, D.

    2014-10-28

    EnergySolutions (ES) and its partner, the Vitreous State Laboratory (VSL) of The Catholic University of America (CUA), are to provide engineering and technical services support to Savannah River Remediation, LLC (SRR) for ongoing operation of the Defense Waste Processing Facility (DWPF) flowsheet as well as for modifications to improve overall plant performance. SRR has requested that the glass formulation team of Savannah River National Laboratory (SRNL) and ES-VSL develop a technical basis that validates the current Product Composition Control System models for use during the processing of the coupled flowsheet or that leads to the refinements of or modifications to the models that are needed so that they may be used during the processing of the coupled flowsheet. SRNL has developed a matrix of test glasses that are to be batched and fabricated by ES-VSL as part of this effort. This document provides two analytical plans for use by ES-VSL: one plan is to guide the measurement of the chemical composition of the study glasses while the second is to guide the measurement of the durability of the study glasses based upon the results of testing by ASTM’s Product Consistency Test (PCT) Method A.

  12. People, Processes, and Time = Facilities. A "Primer" on Planning New Facilities for Junior Colleges.

    ERIC Educational Resources Information Center

    Reed, Bob H.

    1966-01-01

    The people of the facilities planning process are grouped into two teams: the educational team and the design team. The educational team is described as consisting of the institutional governing body, chief administrator, one or more administrative assistants, department heads, faculty committees, and educational consultants. The design team

  13. PROCESS AND EQUIPMENT CHANGES FOR CLEANER PRODUCTION IN FEDERAL FACILITIES

    EPA Science Inventory

    The paper discusses process and equipment changes for cleaner production in federal facilities. During the 1990s, DoD and EPA conducted joint research and development, aimed at reducing the discharge of hazardous and toxic pollutants from military production and maintenance faci...

  14. Process and facility for making coke suitable for metallurgical purposes

    SciTech Connect

    Calderon, J. L.; Betancourt, H.

    1985-11-05

    Process and facility for upgrading heavy hydrocarbonaceous materials for making coke suitable for metallurgical purposes comprises mixing the heavy hydrocarbonaceous materials with a diluent having a closely controlled boiling range and subjecting the oil diluent mixture to distillation and careful fractionation so as to maximize liquid yields in the coking step.

  15. 10 CFR 95.17 - Processing facility clearance.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... acceptable security review conducted by the NRC; (3) Submitting key management personnel for personnel... SECURITY INFORMATION AND RESTRICTED DATA Physical Security § 95.17 Processing facility clearance. (a... pertinent laws, and the nature of international security and information exchange agreements. The...

  16. 10 CFR 95.17 - Processing facility clearance.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... acceptable security review conducted by the NRC; (3) Submitting key management personnel for personnel... SECURITY INFORMATION AND RESTRICTED DATA Physical Security § 95.17 Processing facility clearance. (a... pertinent laws, and the nature of international security and information exchange agreements. The...

  17. 10 CFR 95.17 - Processing facility clearance.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... acceptable security review conducted by the NRC; (3) Submitting key management personnel for personnel... SECURITY INFORMATION AND RESTRICTED DATA Physical Security § 95.17 Processing facility clearance. (a... pertinent laws, and the nature of international security and information exchange agreements. The...

  18. 10 CFR 95.17 - Processing facility clearance.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... acceptable security review conducted by the NRC; (3) Submitting key management personnel for personnel... SECURITY INFORMATION AND RESTRICTED DATA Physical Security § 95.17 Processing facility clearance. (a... pertinent laws, and the nature of international security and information exchange agreements. The...

  19. 10 CFR 95.17 - Processing facility clearance.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... acceptable security review conducted by the NRC; (3) Submitting key management personnel for personnel... SECURITY INFORMATION AND RESTRICTED DATA Physical Security § 95.17 Processing facility clearance. (a... pertinent laws, and the nature of international security and information exchange agreements. The...

  20. CHEMICAL CONTROL IN MILLING, PROCESSING, AND WAREHOUSE FACILITIES

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Insecticides that are used in milling, processing, and warehouse facilities are classified into general groups and categories according to the method of application. Whole-plant treatments are generally accomplished through the use of fumigants and modified atmospheres, which are in the gaseous pha...

  1. PREVALENCE OF CAMPYLOBACTER WITHIN A SWINE SLAUGHTER AND PROCESSING FACILITY

    Technology Transfer Automated Retrieval System (TEKTRAN)

    The present study examined the prevalence and distribution of Campylobacter in a swine slaughter and processing facility. Samples obtained on three visits over a 30-day period in the summer of 2001 included composite carcass samples (30 total), representing 360 swine carcasses, taken at each of the ...

  2. Evaluation of mercury in the liquid waste processing facilities

    SciTech Connect

    Jain, Vijay; Shah, Hasmukh; Occhipinti, John E.; Wilmarth, William R.; Edwards, Richard E.

    2015-08-13

    This report provides a summary of Phase I activities conducted to support an Integrated Evaluation of Mercury in Liquid Waste System (LWS) Processing Facilities. Phase I activities included a review and assessment of the liquid waste inventory and chemical processing behavior of mercury using a system by system review methodology approach. Gaps in understanding mercury behavior as well as action items from the structured reviews are being tracked. 64% of the gaps and actions have been resolved.

  3. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    SciTech Connect

    Gates, R.; Glukhov, A.; Markowski, F.

    1996-06-01

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes.

  4. Facility Effluent Monitoring Plan for the Waste Receiving and Processing (WRAP) Facility

    SciTech Connect

    DAVIS, W.E.

    2000-03-08

    A facility effluent monitoring plan is required by the U.S. Department of Energy in Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee public safety, or the environment. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether these systems are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan ensures long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and must be updated, as a minimum, every 3 years.

  5. APET methodology for Defense Waste Processing Facility: Mode C operation

    SciTech Connect

    Taylor, R.P. Jr.; Massey, W.M.

    1995-04-01

    Safe operation of SRS facilities continues to be the highest priority of the Savannah River Site (SRS). One of these facilities, the Defense Waste Processing Facility or DWPF, is currently undergoing cold chemical runs to verify the design and construction preparatory to hot startup in 1995. The DWPFF is a facility designed to convert the waste currently stored in tanks at the 200-Area tank farm into a form that is suitable for long term storage in engineered surface facilities and, ultimately, geologic isolation. As a part of the program to ensure safe operation of the DWPF, a probabilistic Safety Assessment of the DWPF has been completed. The results of this analysis are incorporated into the Safety Analysis Report (SAR) for DWPF. The usual practice in preparation of Safety Analysis Reports is to include only a conservative analysis of certain design basis accidents. A major part of a Probabilistic Safety Assessment is the development and quantification of an Accident Progression Event Tree or APET. The APET provides a probabilistic representation of potential sequences along which an accident may progress. The methodology used to determine the risk of operation of the DWPF borrows heavily from methods applied to the Probabilistic Safety Assessment of SRS reactors and to some commercial reactors. This report describes the Accident Progression Event Tree developed for the Probabilistic Safety Assessment of the DWPF.

  6. Design characteristics for facilities which process hazardous particulate

    SciTech Connect

    Abeln, S.P.; Creek, K.; Salisbury, S.

    1998-12-01

    Los Alamos National Laboratory is establishing a research and processing capability for beryllium. The unique properties of beryllium, including light weight, rigidity, thermal conductivity, heat capacity, and nuclear properties make it critical to a number of US defense and aerospace programs. Concomitant with the unique engineering properties are the health hazards associated with processing beryllium in a particulate form and the potential for worker inhalation of aerosolized beryllium. Beryllium has the lowest airborne standard for worker protection compared to all other nonradioactive metals by more than an order of magnitude. This paper describes the design characteristics of the new beryllium facility at Los Alamos as they relate to protection of the workforce. Design characteristics to be reviewed include; facility layout, support systems to minimize aerosol exposure and spread, and detailed review of the ventilation system design for general room air cleanliness and extraction of particulate at the source.

  7. The orbiter Columbia is moved into the Orbiter Processing Facility.

    NASA Technical Reports Server (NTRS)

    1999-01-01

    The Space Shuttle orbiter Columbia sits outside the Orbiter Processing Facility bay 1 after transfer from the Vehicle Assembly Building. Columbia will undergo processing for mission STS-93, targeted for launch in July 1999. The STS-93 mission will deploy the Chandra X-ray Observatory (formerly AXAF) which comprises three major elements: the spacecraft, the telescope, and the science instrument module (SIM). Chandra will allow scientists from around the world to obtain unprecedented X-ray images of a variety of high-energy objects to help understand the structure and evolution of the universe. The STs-93 mission commander is Eileen M. Collins, the first woman to serve in that capacity.

  8. DYMAC digital electronic balance. [LASL Plutonium Processing Facility

    SciTech Connect

    Stephens, M.M.

    1980-06-01

    The Dynamic Materials Accountability (DYMAC) System at LASL integrates nondestructive assay (NDA) instruments with interactive data-processing equipment to provide near-real-time accountability of the nuclear material in the LASL Plutonium Processing Facility. The most widely used NDA instrument in the system is the DYMAC digital electronic balance. The DYMAC balance is a commercial instrument that has been modified at LASL for weighing material in gloveboxes and for transmitting the weight data directly to a central computer. This manual describes the balance components, details the LASL modifications, reviews a DYMAC measurement control program that monitors balance performance, and provides instructions for balance operation and maintenance.

  9. NASA Regional Planetary Image Facility image retrieval and processing system

    NASA Technical Reports Server (NTRS)

    Slavney, Susan

    1986-01-01

    The general design and analysis functions of the NASA Regional Planetary Image Facility (RPIF) image workstation prototype are described. The main functions of the MicroVAX II based workstation will be database searching, digital image retrieval, and image processing and display. The uses of the Transportable Applications Executive (TAE) in the system are described. File access and image processing programs use TAE tutor screens to receive parameters from the user and TAE subroutines are used to pass parameters to applications programs. Interface menus are also provided by TAE.

  10. Accident Fault Trees for Defense Waste Processing Facility

    SciTech Connect

    Sarrack, A.G.

    1999-06-22

    The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses to calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).

  11. Defense Waste Processing Facility (DWPF) startup test program: Glass characterization

    SciTech Connect

    Jantzen, C.M.

    1992-07-01

    Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be processed in the Defense Waste Processing Facility (DWPF) and poured into stainless steel canisters for eventual geologic disposal. Six simulated glass compositions will be processed in the DWPF during initial startup. The glass in 86 of the first 106 full sized canisters will be sampled and characterized. Extensive glass characterization will determine the following: (1) sampling frequency for radioactive operation, (2) verification of the compositionally dependent process-product models, (3) verification of melter mixing, (4) representativeness of the glass from the canister throat sampler, and (5) homogeneity of the canister glass.

  12. Defense Waste Processing Facility (DWPF) startup test program: Glass characterization

    SciTech Connect

    Jantzen, C.M.

    1992-01-01

    Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be processed in the Defense Waste Processing Facility (DWPF) and poured into stainless steel canisters for eventual geologic disposal. Six simulated glass compositions will be processed in the DWPF during initial startup. The glass in 86 of the first 106 full sized canisters will be sampled and characterized. Extensive glass characterization will determine the following: (1) sampling frequency for radioactive operation, (2) verification of the compositionally dependent process-product models, (3) verification of melter mixing, (4) representativeness of the glass from the canister throat sampler, and (5) homogeneity of the canister glass.

  13. The Sodium Process Facility at Argonne National Laboratory-West

    SciTech Connect

    Michelbacher, J.A.; Henslee, S.P. McDermott, M.D.; Price, J.R.; Rosenberg, K.E.; Wells, P.B.

    1998-07-01

    Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal.

  14. Manufacturing Demonstration Facility: Roll-to-Roll Processing

    SciTech Connect

    Datskos, Panos G; Joshi, Pooran C; List III, Frederick Alyious; Duty, Chad E; Armstrong, Beth L; Ivanov, Ilia N; Jacobs, Christopher B; Graham, David E; Moon, Ji Won

    2015-08-01

    This Manufacturing Demonstration Facility (MDF)e roll-to-roll processing effort described in this report provided an excellent opportunity to investigate a number of advanced manufacturing approaches to achieve a path for low cost devices and sensors. Critical to this effort is the ability to deposit thin films at low temperatures using nanomaterials derived from nanofermentation. The overarching goal of this project was to develop roll-to-roll manufacturing processes of thin film deposition on low-cost flexible substrates for electronics and sensor applications. This project utilized ORNL s unique Pulse Thermal Processing (PTP) technologies coupled with non-vacuum low temperature deposition techniques, ORNL s clean room facility, slot dye coating, drop casting, spin coating, screen printing and several other equipment including a Dimatix ink jet printer and a large-scale Kyocera ink jet printer. The roll-to-roll processing project had three main tasks: 1) develop and demonstrate zinc-Zn based opto-electronic sensors using low cost nanoparticulate structures manufactured in a related MDF Project using nanofermentation techniques, 2) evaluate the use of silver based conductive inks developed by project partner NovaCentrix for electronic device fabrication, and 3) demonstrate a suite of low cost printed sensors developed using non-vacuum deposition techniques which involved the integration of metal and semiconductor layers to establish a diverse sensor platform technology.

  15. Decontamination and demolition of a former plutonium processing facility`s process exhaust system, firescreen, and filter plenum buildings

    SciTech Connect

    LaFrate, P.J. Jr.; Stout, D.S.; Elliott, J.W.

    1996-03-01

    The Los Alamos National Laboratory (LANL) Decommissioning Project has decontaminated, demolished, and decommissioned a process exhaust system, two filter plenum buildings, and a firescreen plenum structure at Technical Area 21 (TA-2 1). The project began in August 1995 and was completed in January 1996. These high-efficiency particulate air (HEPA) filter plenums and associated ventilation ductwork provided process exhaust to fume hoods and glove boxes in TA-21 Buildings 2 through 5 when these buildings were active plutonium and uranium processing and research facilities. This paper summarizes the history of TA-21 plutonium and uranium processing and research activities and provides a detailed discussion of integrated work process controls, characterize-as-you-go methodology, unique engineering controls, decontamination techniques, demolition methodology, waste minimization, and volume reduction. Also presented in detail are the challenges facing the LANL Decommissioning Project to safely and economically decontaminate and demolish surplus facilities and the unique solutions to tough problems. This paper also shows the effectiveness of the integrated work package concept to control work through all phases.

  16. Decontamination and demolition of a former plutonium processing facility`s process exhaust system, firescreen, and filter plenum buildings

    SciTech Connect

    LaFrate, P.J. Jr.; Stout, D.S.; Elliott, J.W.

    1996-04-01

    The Los Alamos National Laboratory (LANL) Decommissioning Project has decontaminated, demolished, and decommissioned a process exhaust system, two filter plenum buildings, and a firescreen plenum structure at Technical Area 21 (TA-21). The project began in August 1995 and was completed in January 1996. These high-efficiency particulate air (HEPA) filter plenums and associated ventilation ductwork provided process exhaust to fume hoods and glove boxes in TA-21 Buildings 2 through 5 when these buildings were active plutonium and uranium processing and research facilities. This paper summarizes the history of TA-21 plutonium and uranium processing and research activities and provides a detailed discussion of integrated work process controls, characterize-as-you-go methodology, unique engineering controls, decontamination techniques, demolition methodology, waste minimization, and volume reduction. Also presented in detail are the challenges facing the LANL Decommissioning Project to safely and economically decontaminate and demolish surplus facilities and the unique solutions to tough problems. This paper also shows the effectiveness of the integrated work package concept to control work through all phases.

  17. Tributylphosphate in the In-Tank Precipitation Process Facilities

    SciTech Connect

    Barnes, M.J.; Hobbs, D.T.; Swingle, R.F.

    1993-11-23

    A material balance investigation and evaluation of n- tributylphosphate (TBP) recycle throughout ITP and its carryover to Defense Waste Processing Facility (DWPF) was performed. Criticality and DWPF-related issues were determined to pose no adverse consequences due to TBP addition. Effects of decomposition products were also considered. Flammability of 1-butanol, a TBP decomposition product, in Tank 22 was investigated. Calculations show that Tank 22 would be ventilated with air at a rate sufficient to maintain a 1-butanol concentration (volume percent) well below 25 percent of the lower flammability limit (LFL) for 1-butanol.

  18. Orbiter processing facility service platform failure and redesign

    NASA Technical Reports Server (NTRS)

    Harris, Jesse L.

    1988-01-01

    In a high bay of the Orbiter Processing Facility (OPF) at the Kennedy Space Center, technicians were preparing the space shuttle orbiter Discovery for rollout to the Vehicle Assembly Building (VAB). A service platform, commonly referred to as an OPF Bucket, was being retracted when it suddenly fell, striking a technician and impacting Discovery's payload bay door. A critical component in the OPF Bucket hoist system had failed, allowing the platform to fall. The incident was thoroughly investigated by both NASA and Lockheed, revealing many design deficiencies within the system. The deficiencies and the design changes made to correct them are reviewed.

  19. D-Area Moderator Processing Facility (MPF) startup plan

    SciTech Connect

    Cato, D.M.

    1994-04-01

    This startup plan was written for the restart of the Moderator Processing Facility (MPF). The purpose of the MPF is to remove chemical contaminants from degraded process water prior to it being processed through the Rework Unit (RW). The MPF is designed to remove oil, particular matter, and ionic impurities (with the exception of mercury). Degraded process water in 55-gallon drums is charged to the system using the charging station. The process water is filtered and charged through a de-emulsifier and a decanter to remove oil. Any oil removed is collected in a 5-gallon waste oil container. The oil-free water flows by gravity into a 250-gallon receiving tank. The MPF system pump takes a suction on the receiving tank and discharges the process water through three resin columns (two anion and one cation) in series. The ion-free water from the resin columns then flows through a conductivity cell and into a 500-gallon hold tank that stores processed water. The hold tank contents are either pumped through the RW feed manifold into a predetermined RW feed tank or back to 420-2D. In 420-2D, the water is then drained to 55-gallon product drums.

  20. Standardization of DOE Disposal Facilities Waste Acceptance Process

    SciTech Connect

    SHRADER, T.; MACBETH, P.

    2002-01-01

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

  1. Generator Certification Process for Envirocare's Containerized Class A Disposal Facility

    SciTech Connect

    Rogers, B. C.

    2002-02-25

    On October 19, 2001, the Utah Division of Radiation Control issued Amendment 12 to Radioactive Material License UT2300249 (RML) for Envirocare of Utah, Inc. (Envirocare) disposal operations. The license amendment provides the mechanism for Envirocare to receive and dispose of containerized Class A Low-Level Radioactive Waste (LLRW) at the newly constructed Containerized Waste Facility (CWF). Due to the increased radioactivity and external dose rates of waste that will be shipped to the CWF, a Generator Certification Program has been implemented that eliminates the requirement to sample incoming shipments, thus keeping worker doses to as low as reasonably achievable (ALARA). This paper presents the key elements of the Generator Certification Program and describes the review and approval process for certifying generators to ship waste to the CWF. Each phase of the program will be discussed to assist generators in gaining a better understanding of the certification process. Additionally, the paper will present unique differences between the CWF Waste Acceptance Criteria and the requirements from other commercial disposal facilities.

  2. Energy determination in industrial X-ray processing facilities

    NASA Astrophysics Data System (ADS)

    Cleland, M. R.; Gregoire, O.; Stichelbaut, F.; Gomola, I.; Galloway, R. A.; Schlecht, J.

    2005-12-01

    In industrial irradiation facilities, the determination of maximum photon or electron energy is important for regulated processes, such as food irradiation, and for assurance of treatment reproducibility. With electron beam irradiators, this has been done by measuring the depth-dose distribution in a homogeneous material. For X-ray irradiators, an analogous method has not yet been recommended. This paper describes a procedure suitable for typical industrial irradiation processes, which is based on common practice in the field of therapeutic X-ray treatment. It utilizes a measurement of the slope of the exponential attenuation curve of X-rays in a thick stack of polyethylene plates. Monte Carlo simulations and experimental tests have been performed to verify the suitability and accuracy of the method between 3 MeV and 8 MeV.

  3. Remote lighting systems for the defense waste processing facility

    SciTech Connect

    Heckendorn, F.M.; Divona, C.J.

    1986-01-01

    The Defense Waste Processing Facility (DWPF) is under construction at the Savannah River Plant. In DWPF, an immobilization process solidifies radioactive waste sludge by vitrification into a leach-resistant borosilicate glass. The mixture of waste and glass solidifies in stainless steel containers for eventual transportation to an off-site federal repository. The DWPF contains a number of hot cell canyons that are remotely maintained using only a crane and crane-held impact wrench for replacing the equipment. In general, viewing into these canyons is accomplished through shielded windows and by the use of closed-circuit television (CCTV). Demonstration of the prototype remote light fixtures for the DWPF canyon was completed in 1984, and the actual plant equipment is scheduled for completion this year.

  4. Criticality safety evaluation report for the Cold Vacuum Drying Facility`s process water handling system

    SciTech Connect

    Roblyer, S.D.

    1998-02-12

    This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility (CVDF). The controls and limitations on equipment design and operations to control potential criticality occurrences are identified. The effectiveness of equipment design and operation controls in preventing criticality occurrences during normal and abnormal conditions is evaluated and documented in this report. Spent nuclear fuel (SNF) is removed from existing canisters in both the K East and K West Basins and loaded into a multicanister overpack (MCO) in the K Basin pool. The MCO is housed in a shipping cask surrounded by clean water in the annulus between the exterior of the MCO and the interior of the shipping cask. The fuel consists of spent N Reactor and some single pass reactor fuel. The MCO is transported to the CVDF near the K Basins to remove process water from the MCO interior and from the shipping cask annulus. After the bulk water is removed from the MCO, any remaining free liquid is removed by drawing a vacuum on the MCO`s interior. After cold vacuum drying is completed, the MCO is filled with an inert cover gas, the lid is replaced on the shipping cask, and the MCO is transported to the Canister Storage Building. The process water removed from the MCO contains fissionable materials from metallic uranium corrosion. The process water from the MCO is first collected in a geometrically safe process water conditioning receiver tank. The process water in the process water conditioning receiver tank is tested, then filtered, demineralized, and collected in the storage tank. The process water is finally removed from the storage tank and transported from the CVDF by truck.

  5. Personal dust exposures at a food processing facility.

    PubMed

    Lacey, Steven E; Conroy, Lorraine M; Forst, Linda S; Franke, John E; Wadden, Richard A; Hedeker, Donald R

    2006-01-01

    A field study was performed to quantify personal dust exposures at a food processing facility. A review of the literature shows very little exposure information in the food processing industry. The processing area consisted of a series of four rooms, connected by a closed-loop ventilation system, housed within a larger warehouse-type facility. Workers were exposed to various fruit and vegetable dusts during the grinding, sieving, mixing and packaging of freeze-dried or air-dried products. Eight two-hour periods were monitored over two days. Personal total suspended particulate samples were collected on 37 mm PVC filters with 5 microm pore size according to National Institute for Occupational Safety and Health (NIOSH) Method 0500. The filters were analyzed gravimetrically. The two-hour task sampling personal dust exposures ranged from 0.33-103 mg/m3. For each worker, an eight-hour time weighted average (TWA) concentration was calculated, and these ranged from 3.08-59.8 mg/m3. Although there are no directly appropriate occupational exposure limits that may be used for comparison, we selected the Threshold Limit Value (TLV) for particulates not otherwise classified (PNOC) of 10 mg/m3 for inhalable particles. Neglecting the respiratory protection used, five out of eight of the worker time-weighted averages exceeded the TLV. It should be noted that the TLV is based on the inhalable fraction and in this study total suspended particulate was measured; additionally, the TLV is applicable for dusts that are insoluble or poorly soluble, and have low toxicity, which may have limited protective ability in this case due to the irritant nature of certain dusts (e.g., jalapeno peppers, aloe vera). Sieving resulted in significantly higher exposure than grinding and blending. Measuring area concentrations alone in this environment is not a sufficient method of estimating personal exposures due to work practices for some operations. PMID:16893837

  6. [Design of an HACCP program for a cocoa processing facility].

    PubMed

    Lpez D'Sola, Patrizia; Sandia, Mara Gabriela; Bou Rached, Lizet; Hernndez Serrano, Pilar

    2012-12-01

    The HACCP plan is a food safety management tool used to control physical, chemical and biological hazards associated to food processing through all the processing chain. The aim of this work is to design a HACCP Plan for a Venezuelan cocoa processing facility.The production of safe food products requires that the HACCP system be built upon a solid foundation of prerequisite programs such as Good Manufacturing Practices (GMP) and Sanitation Standard Operating Procedures (SSOP). The existence and effectiveness of these prerequisite programs were previously assessed.Good Agriculture Practices (GAP) audit to cocoa nibs suppliers were performed. To develop the HACCP plan, the five preliminary tasks and the seven HACCP principles were accomplished according to Codex Alimentarius procedures. Three Critical Control Points (CCP) were identified using a decision tree: winnowing (control of ochratoxin A), roasting (Salmonella control) and metallic particles detection. For each CCP, Critical limits were established, the Monitoring procedures, Corrective actions, Procedures for Verification and Documentation concerning all procedures and records appropriate to these principles and their application was established. To implement and maintain a HACCP plan for this processing plant is suggested. Recently OchratoxinA (OTA) has been related to cocoa beans. Although the shell separation from the nib has been reported as an effective measure to control this chemical hazard, ochratoxin prevalence study in cocoa beans produced in the country is recommended, and validate the winnowing step as well PMID:24020255

  7. Waste receiving and processing facility module 1, detailed design report

    SciTech Connect

    Not Available

    1993-10-01

    WRAP 1 baseline documents which guided the technical development of the Title design included: (a) A/E Statement of Work (SOW) Revision 4C: This DOE-RL contractual document specified the workscope, deliverables, schedule, method of performance and reference criteria for the Title design preparation. (b) Functional Design Criteria (FDC) Revision 1: This DOE-RL technical criteria document specified the overall operational criteria for the facility. The document was a Revision 0 at the beginning of the design and advanced to Revision 1 during the tenure of the Title design. (c) Supplemental Design Requirements Document (SDRD) Revision 3: This baseline criteria document prepared by WHC for DOE-RL augments the FDC by providing further definition of the process, operational safety, and facility requirements to the A/E for guidance in preparing the design. The document was at a very preliminary stage at the onset of Title design and was revised in concert with the results of the engineering studies that were performed to resolve the numerous technical issues that the project faced when Title I was initiated, as well as, by requirements established during the course of the Title II design.

  8. Contamination concerns in the modular containerless processing facility

    NASA Technical Reports Server (NTRS)

    Seshan, P. K.; Trinh, E. H.

    1989-01-01

    This paper describes the problems of the control and management of contamination in the Modular Containerless Processing Facility (MCPF), that is being currently developed at the JPL for the Space Station, and in the MCPF's precursor version, called the Drop Physics Module (DPM), which will be carried aboard one or more Space Shuttle missions. Attention is given to the identification of contamination sources, their mode of transport to the sample positioned within the chamber, and the protection of the sample, as well as to the mathematical simulatiom of the contaminant transport. It is emphasized that, in order to choose and implement the most appropriate contamination control strategy for each investigator, a number of simplified mathematical simulations will have to be developed, and ground-based contamination experiments will have to be carried out with identical materials.

  9. Recent National Transonic Facility Test Process Improvements (Invited)

    NASA Technical Reports Server (NTRS)

    Kilgore, W. A.; Balakrishna, S.; Bobbitt, C. W., Jr.; Adcock, J. B.

    2001-01-01

    This paper describes the results of two recent process improvements; drag feed-forward Mach number control and simultaneous force/moment and pressure testing, at the National Transonic Facility. These improvements have reduced the duration and cost of testing. The drag feed-forward Mach number control reduces the Mach number settling time by using measured model drag in the Mach number control algorithm. Simultaneous force/moment and pressure testing allows simultaneous collection of force/moment and pressure data without sacrificing data quality thereby reducing the overall testing time. Both improvements can be implemented at any wind tunnel. Additionally the NTF is working to develop and implement continuous pitch as a testing option as an additional method to reduce costs and maintain data quality.

  10. Containerless Processing in Reduced Gravity Using the TEMPUS Facility

    NASA Technical Reports Server (NTRS)

    Roger, Jan R.; Robinson, Michael B.

    1996-01-01

    Containerless processing provides a high purity environment for the study of high-temperature, very reactive materials. It is an important method which provides access to the metastable state of an undercooled melt. In the absence of container walls, the nucleation rate is greatly reduced and undercooling up to (Tm-Tn)/Tm approx. 0.2 can be obtained, where Tm and Tn are the melting and nucleation temperatures, respectively. Electromagnetic levitation represents a method particularly well-suited for the study of metallic melts. The TEMPUS facility is a research instrument designed to perform electromagnetic levitation studies in reduced gravity. It provides temperatures up to 2600 C, levitation of several grams of material and access to the undercooled state for an extended period of time (up to hours).

  11. The SRTM is moved into the Space Station Processing Facility

    NASA Technical Reports Server (NTRS)

    1999-01-01

    The Shuttle Radar Topography Mission (SRTM) is moved into the Space Station Processing Facility to prepare it for launch targeted for September 1999. The primary payload on mission STS- 99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  12. Recent National Transonic Facility Test Process Improvements (Invited)

    NASA Technical Reports Server (NTRS)

    Kilgore, W. A.; Balakrishna, S.; Bobbitt, C. W., Jr.; Adcock, J. B.

    2001-01-01

    This paper describes the results of two recent process improvements; drag feed-forward Mach number control and simultaneous force/moment and pressure testing, at the National Transonic Facility. These improvements have reduced the duration and cost of testing. The drag feedforward Mach number control reduces the Mach number settling time by using measured model drag in the Mach number control algorithm. Simultaneous force/moment and pressure testing allows simultaneous collection of force/moment and pressure data without sacrificing data quality thereby reducing the overall testing time. Both improvements can be implemented at any wind tunnel. Additionally the NTF is working to develop and implement continuous pitch as a testing option as an additional method to reduce costs and maintain data quality.

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

    SciTech Connect

    Herman, C

    2006-09-20

    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.

  14. Spartan is moved for processing in the Multi-Payload Processing Facility

    NASA Technical Reports Server (NTRS)

    1998-01-01

    The Spartan solar-observing deployable spacecraft is moved onto a workstand in the Multi-Payload Processing Facility at KSC. Spartan is one of the payloads for the STS-95 mission, scheduled to launch Oct. 29. Other research payloads include the Hubble Space Telescope Orbital Systems Test Platform, the International Extreme Ultraviolet Hitchhiker, as well as the SPACEHAB single module with experiments on space flight and the aging process.

  15. Spartan is moved for processing in the Multi-Payload Processing Facility

    NASA Technical Reports Server (NTRS)

    1998-01-01

    The Spartan solar-observing deployable spacecraft is moved from a bridge in the Multi-Payload Processing Facility at KSC where it had been stored for protection from a hurricane threatening the area. Spartan is one of the payloads for the STS-95 mission, scheduled to launch Oct. 29. Other research payloads include the Hubble Space Telescope Orbital Systems Test Platform, the International Extreme Ultraviolet Hitchhiker, as well as the SPACEHAB single module with experiments on space flight and the aging process.

  16. Characterization of emissions from scrap metal processing facilities

    SciTech Connect

    Norco, J.E.; Tyler, T.

    1997-12-31

    To prepare its members for the permitting requirements under Title 5 of the Clean Act, the Institute of Scrap Recycling Industries (ISRI) commissioned a project to develop a Title 5 applicability workbook. A critical element in the preparation of the workbook was the characterization of emissions from processes and equipment typically found in the scrap metal processing industry. This paper describes the approach to the preparation of the workbook with emphasis on characterization of specific emission units which are deemed important for Title 5. The paper describes the methodology employed for acquiring existing emissions information from equipment manufacturers, vendors, and scrap recycling facility operators. The data were aggregated and analyzed to develop a variety of emission tabulations for pollutants requiring analysis under Title 5. The project also involved a survey of numerous state and local air pollution agencies to determine regulatory requirements regarding critical issues in the scrap processing industry. The paper describes a methodology for determining Title 5 applicability with emphasis on the use of emission tabulations and example worksheets. Emissions data are presented for metal shredders to demonstrate the methodology and procedures developed during the project. Finally, the paper discusses the structure of the Title 5 applicability workbook and its dissemination to a major industry trade association.

  17. Dowa process demonstration: Shawnee test facility. Final report

    SciTech Connect

    Puschauer, E.J.; Veitch, J.D.; Jackson, S.B.; Smith, D.B.; Treshier, J.R.; Propp, W.A.

    1982-04-01

    The Dowa flue gas desulfurization process, an aluminum-based double alkali process that uses forced oxidation, limestone neutralization, and produces gypsum, was evaluated at a 10-MW scale on a coal-fired boiler at the EPA Shawnee test facility. Although SO/sub 2/ removal with a Turbulent Contact Absorber was less than expected, SO/sub 2/ removal efficiencies of 90% were obtained at flue gas velocities of 7 to 11 ft/sec and liquid-to-gas ratios of 80 to 95 gal/kaft/sup 3/ by using an adsorber containing 6 to 9 feet of rigid packing with a pressure drip of 2 to 9 inches H/sub 2/O. Efficient air-liquid contact in the in-loop forced oxidation tank and control of absorbent basicity were essential to efficient SO/sub 2/ removal. No scaling or corrosion of high-alloy or organic-coated materials was observed during the six-month test. Fly ash appeared to have served as an oxidation promoter, a function normally served by a metal catalyst. A product consisting of over 99% gypsum filterable to over 80% solids was produced. Further evaluation is needed to completely define Dowa process operation on coal-fired boilers.

  18. Process safety and risk management: Is your facility under control?

    SciTech Connect

    Sulkowski, J.

    1997-08-01

    By 1990, the US Congress had passed two significant pieces of legislation dealing with the prevention of accidents involving hazardous chemical substances--Section 112(r) of the 1990 Clean Air Act Amendments, and legislation that required the Occupational Safety and Health Administration to issue its Process Safety Management regulations. On June 20, 1996, the final Rule on Risk Management Plans (RMP) for Chemical Accident Prevention was published by the Environmental Protection Agency (EPA). The final RMP Rule requires facilities with covered processes to be in full compliance with EPA`s Risk Management and Certification requirements by June 21, 1999. Meanwhile, the OSHA regulations, issued in final form in February 1992 (29CFR1910.119), provided a five-year compliance phase-in. One principal difference between the EPA and OSHA Rules arises from EPA`s position on exemptions: there are none under EPA`s Rule. With the RMP Rule, only the presence of a process containing a regulated substance above its threshold quantity determines applicability; the nature of the business is not considered in determining specific compliance requirements. Compliance of these regulations is discussed.

  19. A survey of decontamination processes applicable to DOE nuclear facilities

    SciTech Connect

    Chen, L.; Chamberlain, D.B.; Conner, C.; Vandegrift, G.F.

    1997-05-01

    The objective of this survey was to select an appropriate technology for in situ decontamination of equipment interiors as part of the decommissioning of U.S. Department of Energy nuclear facilities. This selection depends on knowledge of existing chemical decontamination methods. This report provides an up-to-date review of chemical decontamination methods. According to available information, aqueous systems are probably the most universally used method for decontaminating and cleaning metal surfaces. We have subdivided the technologies, on the basis of the types of chemical solvents, into acid, alkaline permanganate, highly oxidizing, peroxide, and miscellaneous systems. Two miscellaneous chemical decontamination methods (electrochemical processes and foam and gel systems) are also described. A concise technical description of various processes is given, and the report also outlines technical considerations in the choice of technologies, including decontamination effectiveness, waste handing, fields of application, and the advantages and limitations in application. On the basis of this survey, six processes were identified for further evaluation. 144 refs., 2 tabs.

  20. Defense Waste Processing Facility wasteform and canister description: Revision 2

    SciTech Connect

    Baxter, R.G.

    1988-12-01

    This document describes the reference wasteform and canister for the Defense Waste Processing Facility (DWPF). The principal changes include revised feed and glass product compositions, an estimate of glass product characteristics as a function of time after the start of vitrification, and additional data on glass leaching performance. The feed and glass product composition data are identical to that described in the DWPF Basic Data Report, Revision 90/91. The DWPF facility is located at the Savannah River Plant in Aiken, SC, and it is scheduled for construction completion during December 1989. The wasteform is borosilicate glass containing approximately 28 wt % sludge oxides, with the balance consisting of glass-forming chemicals, primarily glass frit. Borosilicate glass was chosen because of its stability toward reaction with potential repository groundwaters, its relatively high ability to incorporate nuclides found in the sludge into the solid matrix, and its reasonably low melting temperature. The glass frit contains approximately 71% SiO/sub 2/, 12% B/sub 2/O/sub 3/, and 10% Na/sub 2/O. Tests to quantify the stability of DWPF waste glass have been performed under a wide variety of conditions, including simulations of potential repository environments. Based on these tests, DWPF waste glass should easily meet repository criteria. The canister is filled with about 3700 lb of glass which occupies 85% of the free canister volume. The filled canister will generate approximately 690 watts when filled with oxides from 5-year-old sludge and precipitate from 15-year-old supernate. The radionuclide activity of the canister is about 233,000 curies, with an estimated radiation level of 5600 rad/hour at the canister surface. 14 figs., 28 tabs.

  1. New Waste Calcining Facility Non-radioactive Process Decontamination

    SciTech Connect

    Swenson, Michael Clair

    2001-09-01

    This report documents the results of a test of the New Calcining Facility (NWCF) process decontamination system. The decontamination system test occurred in December 1981, during non-radioactive testing of the NWCF. The purpose of the decontamination system test was to identify equipment whose design prevented effective calcine removal and decontamination. Effective equipment decontamination was essential to reduce radiation fields for in-cell work after radioactive processing began. The decontamination system test began with a pre-decontamination inspection of the equipment. The pre-decontamination inspection documented the initial condition and cleanliness of the equipment. It provided a basis for judging the effectiveness of the decontamination. The decontamination consisted of a series of equipment flushes using nitric acid and water. A post-decontamination equipment inspection determined the effectiveness of the decontamination. The pre-decontamination and post-decontamination equipment inspections were documented with hotographs. The decontamination system was effective in removing calcine from most of the NWCF equipment as evidenced by little visible calcine residue in the equipment after decontamination. The decontamination test identified four areas where the decontamination system required improvement. These included the Calciner off-gas line, Cyclone off-gas line, fluidizing air line, and the Calciner baffle plates. Physical modifications to enhance decontamination were made to those areas, resulting in an effective NWCF decontamination system.

  2. New Waste Calcining Facility Non-Radioactive Process Decontamination

    SciTech Connect

    Swenson, Michael C.

    2001-09-30

    This report documents the results of a test of the New Calcining Facility (NWCF) process decontamination system. The decontamination system test occurred in December 1981, during non-radioactive testing of the NWCF. The purpose of the decontamination system test was to identify equipment whose design prevented effective calcine removal and decontamination. Effective equipment decontamination was essential to reduce radiation fields for in-cell work after radioactive processing began. The decontamination system test began with a pre-decontamination inspection of the equipment. The pre- decontamination inspection documented the initial condition and cleanliness of the equipment. It provided a basis for judging the effectiveness of the decontamination. The decontamination consisted of a series of equipment flushes using nitric acid and water. A post-decontamination equipment inspection determined the effectiveness of the decontamination. The pre-decontamination and post-decontamination equipment inspections were documented with photographs. The decontamination system was effective in removing calcine from most of the NWCF equipment as evidenced by little visible calcine residue in the equipment after decontamination. The decontamination test identified four areas where the decontamination system required improvement. These included the Calciner off-gas line, Cyclone off-gas line, fluidizing air line, and the Calciner baffle plates. Physical modifications to enhance decontamination were made to those areas, resulting in an effective NWCF decontamination system.

  3. ENGINEERED NEAR SURFACE DISPOSAL FACILITY OF THE INDUSTRIAL COMPLEX FOR SOLID RADWASTE MANAGEMENT AT CHERNOBYL NUCLEAR POWER PLANT

    SciTech Connect

    Ziehm, Ronny; Pichurin, Sergey Grigorevich

    2003-02-27

    As a part of the turnkey project ''Industrial Complex for Solid Radwaste Management (ICSRM) at the Chernobyl Nuclear Power Plant (ChNPP)'' an Engineered Near Surface Disposal Facility (ENSDF, LOT 3) will be built on the VEKTOR site within the 30 km Exclusion Zone of the ChNPP. This will be performed by RWE NUKEM GmbH, Germany, and it governs the design, licensing support, fabrication, assembly, testing, inspection, delivery, erection, installation and commissioning of the ENSDF. The ENSDF will receive low to intermediate level, short lived, processed/conditioned wastes from the ICSRM Solid Waste Processing Facility (SWPF, LOT 2), the ChNPP Liquid Radwaste Treatment Plant (LRTP) and the ChNPP Interim Storage Facility for RBMK Fuel Assemblies (ISF). The ENSDF has a capacity of 55,000 m{sup 3}. The primary functions of the ENSDF are: to receive, monitor and record waste packages, to load the waste packages into concrete disposal units, to enable capping and closure of the disposal unit s, to allow monitoring following closure. The ENSDF comprises the turnkey installation of a near surface repository in the form of an engineered facility for the final disposal of LILW-SL conditioned in the ICSRM SWPF and other sources of Chernobyl waste. The project has to deal with the challenges of the Chernobyl environment, the fulfillment of both Western and Ukrainian standards, and the installation and coordination of an international project team. It will be shown that proven technologies and processes can be assembled into a unique Management Concept dealing with all the necessary demands and requirements of a turnkey project. The paper emphasizes the proposed concepts for the ENSDF and their integration into existing infrastructure and installations of the VEKTOR site. Further, the paper will consider the integration of Western and Ukrainian Organizations into a cohesive project team and the requirement to guarantee the fulfillment of both Western standards and Ukrainian regulations and licensing requirements. The paper provides information on the output of the Detail Design and will reflect the progress of the design work.

  4. Estimating and bidding for the Space Station Processing Facility

    NASA Technical Reports Server (NTRS)

    Brown, Joseph A.

    1993-01-01

    This new, unique Cost Engineering Report introduces the 800-page, C-100 government estimate for the Space Station Processing Facility (SSPF) and Volume IV Aerospace Construction Price Book. At the January 23, 1991, bid opening for the SSPF, the government cost estimate was right on target. Metric, Inc., Prime Contractor, low bid was 1.2 percent below the government estimate. This project contains many different and complex systems. Volume IV is a summary of the cost associated with construction, activation and Ground Support Equipment (GSE) design, estimating, fabrication, installation, testing, termination, and verification of this project. Included are 13 reasons the government estimate was so accurate; abstract of bids, for 8 bidders and government estimate with additive alternates, special labor and materials, budget comparison and system summaries; and comments on the energy credit from local electrical utility. This report adds another project to our continuing study of 'How Does the Low Bidder Get Low and Make Money?' which was started in 1967, and first published in the 1973 AACE Transaction with 10 more ways the low bidder got low. The accuracy of this estimate proves the benefits of our Kennedy Space Center (KSC) teamwork efforts and KSC Cost Engineer Tools which are contributing toward our goals of the Space Station.

  5. Design Considerations for the Construction and Operation of Flour Milling Facilities. Part II: Process Design Considerations

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Flour milling facilities have been the cornerstone of agricultural processing for centuries. Like most agri-industrial production facilities, flour milling facilities have a number of unique design requirements. Design information, to date, has been limited. In an effort to summarize state of the ...

  6. Plantwide Energy Assessment of a Sugarcane Farming and Processing Facility

    SciTech Connect

    Jakeway, L.A.; Turn, S.Q.; Keffer, V.I.; Kinoshita, C.M.

    2006-02-27

    A plantwide energy assessment was performed at Hawaiian Commercial & Sugar Co., an integrated sugarcane farming and processing facility on the island of Maui in the State of Hawaii. There were four main tasks performed for the plantwide energy assessment: 1) pump energy assessment in both field and factory operations, 2) steam generation assessment in the power production operations, 3) steam distribution assessment in the sugar manufacturing operation, and 4) electric power distribution assessment of the company system grid. The energy savings identified in each of these tasks were summarized in terms of fuel savings, electricity savings, or opportunity revenue that potentially exists mostly from increased electric power sales to the local electric utility. The results of this investigation revealed eight energy saving projects that can be implemented at HC&S. These eight projects were determined to have potential for $1.5 million in annual fuel savings or 22,337 MWh equivalent annual electricity savings. Most of the savings were derived from pump efficiency improvements and steam efficiency improvements both in generation and distribution. If all the energy saving projects were implemented and the energy savings were realized as less fuel consumed, there would be corresponding reductions in regulated air pollutants and carbon dioxide emissions from supplemental coal fuel. As HC&S is already a significant user of renewable biomass fuel for its operations, the projected reductions in air pollutants and emissions will not be as great compared to using only coal fuel for example. A classification of implementation priority into operations was performed for the identified energy saving projects based on payback period and ease of implementation.

  7. Proposal for a new categorization of aseptic processing facilities based on risk assessment scores.

    PubMed

    Katayama, Hirohito; Toda, Atsushi; Tokunaga, Yuji; Katoh, Shigeo

    2008-01-01

    Risk assessment of aseptic processing facilities was performed using two published risk assessment tools. Calculated risk scores were compared with experimental test results, including environmental monitoring and media fill run results, in three different types of facilities. The two risk assessment tools used gave a generally similar outcome. However, depending on the tool used, variations were observed in the relative scores between the facilities. For the facility yielding the lowest risk scores, the corresponding experimental test results showed no contamination, indicating that these ordinal testing methods are insufficient to evaluate this kind of facility. A conventional facility having acceptable aseptic processing lines gave relatively high risk scores. The facility showing a rather high risk score demonstrated the usefulness of conventional microbiological test methods. Considering the significant gaps observed in calculated risk scores and in the ordinal microbiological test results between advanced and conventional facilities, we propose a facility categorization based on risk assessment. The most important risk factor in aseptic processing is human intervention. When human intervention is eliminated from the process by advanced hardware design, the aseptic processing facility can be classified into a new risk category that is better suited for assuring sterility based on a new set of criteria rather than on currently used microbiological analysis. To fully benefit from advanced technologies, we propose three risk categories for these aseptic facilities. PMID:19174952

  8. Methodology for Determining Increases in Radionuclide Inventories for the Effluent Treatment Facility Process

    SciTech Connect

    Blanchard, A.

    1998-10-16

    A study is currently underway to determine if the Effluent Treatment Facility can be downgraded from a Hazard Category 3 facility to a Radiological Facility per DOE STD-1027-92. This technical report provides a methodology to determine and monitor increases in the radionuclide inventories of the ETF process columns. It also provides guidelines to ensure that other potential increases to the ETF radionuclide inventory are evaluated as required to ensure that the ETF remains a Radiological Facility.

  9. 10 CFR 70.64 - Requirements for new facilities or new processes at existing facilities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... throughout the life of the facility. (2) Natural phenomena hazards. The design must provide for adequate protection against natural phenomena with consideration of the most severe documented historical events for... selection of engineered controls over administrative controls to increase overall system reliability; and...

  10. Integrating Sustainability Programs into the Facilities Capital Planning Process

    ERIC Educational Resources Information Center

    Buchanan, Susan

    2011-01-01

    With detailed information about the costs and benefits of potential green investments, educational facilities can effectively evaluate which initiatives will ultimately provide the greatest results over the short and long term. Based on its overall goals, every school, college, or university will have different values and therefore different…

  11. Process Control Manual for Aerobic Biological Wastewater Treatment Facilities.

    ERIC Educational Resources Information Center

    Environmental Protection Agency, Washington, DC. Office of Water Programs.

    This Environmental Protection Agency (EPA) publication is an operations manual for activated sludge and trickling filter wastewater treatment facilities. The stated purpose of the manual is to provide an on-the-job reference for operators of these two types of treatment plants. The overall objective of the manual is to aid the operator in

  12. 10 CFR 95.15 - Approval for processing licensees and others for facility clearance.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Approval for processing licensees and others for facility clearance. 95.15 Section 95.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) FACILITY SECURITY CLEARANCE AND SAFEGUARDING OF NATIONAL SECURITY INFORMATION AND RESTRICTED DATA Physical Security 95.15 Approval for processing licensees and...

  13. MOLECULAR CHARACTERIZATION OF LISTERIA MONOCYTOGENES ISOLATED FROM A POULTRY FURTHER PROCESSING FACILITY AND FULLY COOKED PRODUCT

    Technology Transfer Automated Retrieval System (TEKTRAN)

    This study was undertaken to explore environmental sources of L. monocytogenes in a commercial chicken further processing facility and to compare those isolates found to others detected on fully cooked product. A survey was conducted in the processing facility whereby forty environmental sites repr...

  14. Processing of tetraphenylborate precipitates in the Savannah River Site Defense Waste Processing Facility

    SciTech Connect

    Eibling, R.E.

    1990-12-31

    The Savannah River Site has generated 77 million gallons of high level radioactive waste since the early 1950`s. By 1987, evaporation had reduced the concentration of the waste inventory to 35 million gallons. Currently, the wastes reside in large underground tanks as a soluble fraction stored, crystallized salts, and an insoluble fraction, sludge, which consists of hydrated transition metal oxides. The bulk of the radionuclides, 67 percent, are in the sludge while the crystallized salts and supernate are composed of the nitrates, nitrites, sulfates and hydroxides of sodium, potassium, and cesium. The principal radionuclide in the soluble waste is {sup 137}Cs with traces of {sup 90}Sr. The transformation of the high level wastes into a borosilicate glass suitable for permanent disposal is the goal of the Defense Waste Processing Facility (DWPF). To minimize the volume of glass produced, the soluble fraction of the waste is treated with sodium tetraphenylborate and sodium titanate in the waste tanks to precipitate the radioactive cesium ion and absorb the radioactive strontium ion. The precipitate is washed in the waste tanks and is then pumped to the DWPF. The precipitate, as received, is incompatible with the vitrification process because of the high aromatic carbon content and requires further chemical treatment. Within the DWPF, the precipitate is processed in the Salt Processing Cell to remove the aromatic carbon as benzene. The precipitate hydrolysis process hydrolyzes the tetraphenylborate anion to produce borate anion and benzene. The benzene is removed by distillation, decontaminated and transferred out of the DWPF for disposal.

  15. Hardware Development Process for Human Research Facility Applications

    NASA Technical Reports Server (NTRS)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. The source of hardware requirements is the science community and HRF program. The HRF Science Working Group, consisting of SCientists from various medical disciplines, defined a basic set of equipment with functional requirements. This established the performance requirements of the hardware. HRF program requirements focus on making the hardware safe and operational in a space environment. This includes structural, thermal, human factors, and material requirements. Science and HRF program requirements are defined in a hardware requirements document which includes verification methods. Once the hardware is fabricated, requirements are verified by inspection, test, analysis, or demonstration. All data is compiled and reviewed to certify the hardware for flight. Obviously, the basis for all hardware development activities is requirement definition. Full and complete requirement definition is ideal prior to initiating the hardware development. However, this is generally not the case, but the hardware team typically has functional inputs as a guide. The first step is for engineers to conduct market research based on the functional inputs provided by scientists. CommerCially available products are evaluated against the science requirements as well as modifications needed to meet program requirements. Options are consolidated and the hardware development team reaches a hardware development decision point. Within budget and schedule constraints, the team must decide whether or not to complete the hardware as an in-house, subcontract with vendor, or commercial-off-the-shelf (COTS) development. An in-house development indicates NASA personnel or a contractor builds the hardware at a NASA site. A subcontract development is completed off-site by a commercial company. A COTS item is a vendor product available by ordering a specific part number. The team evaluates the pros and cons of each development path. For example, in-bouse developments utilize existing corporate knowledge regarding bow to build equipment for use in space. However, technical expertise would be required to fully understand the medical equipment capabilities, such as for an ultrasound system. It may require additional time and funding to gain the expertise that commercially exists. The major benefit of subcontracting a hardware development is the product is delivered as an end-item and commercial expertise is utilized. On the other hand, NASA has limited control over schedule delays. The final option of COTS or modified COTS equipment is a compromise between in-house and subcontracts. A vendor product may exist that meets all functional requirements but req uires in-house modifications for successful operation in a space environment. The HRF utilizes equipment developed using all of the paths described: inhouse, subcontract, and modified COTS.

  16. Overview of the Facility Safeguardability Analysis (FSA) Process

    SciTech Connect

    Bari, Robert A.; Hockert, John; Wonder, Edward F.; Johnson, Scott J.; Wigeland, Roald; Zentner, Michael D.

    2012-08-01

    Executive Summary The safeguards system of the International Atomic Energy Agency (IAEA) is intended to provide the international community with credible assurance that a State is fulfilling its safeguards obligations. Effective and cost-efficient IAEA safeguards at the facility level are, and will remain, an important element of IAEA safeguards as those safeguards evolve towards a “State-Level approach.” The Safeguards by Design (SBD) concept can facilitate the implementation of these effective and cost-efficient facility-level safeguards (Bjornard, et al. 2009a, 2009b; IAEA, 1998; Wonder & Hockert, 2011). This report, sponsored by the National Nuclear Security Administration’s Office of Nuclear Safeguards and Security, introduces a methodology intended to ensure that the diverse approaches to Safeguards by Design can be effectively integrated and consistently used to cost effectively enhance the application of international safeguards.

  17. Overview of Fiscal Year 2002 Research and Development for Savannah River Site's Salt Waste Processing Facility

    SciTech Connect

    H. D. Harmon, R. Leugemors, PNNL; S. Fink, M. Thompson, D. Walker, WSRC; P. Suggs, W. D. Clark, Jr

    2003-02-26

    The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste program is responsible for storage, treatment, and immobilization of high-level waste for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of the SRS high-level waste effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site's grout facility (Saltstone) and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste and sent as feed to Defense Waste Processing Facility include actinides, strontium, cesium, and entrained sludge. In fiscal year 2002 (FY02), research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility. The SPP R&D focused on advancing the technical maturity, risk reduction, engineering development, and design support for DOE's engineering, procurement, and construction (EPC) contractors for the Salt Waste Processing Facility. Thus, R&D in FY02 addressed the areas of actual waste performance, process chemistry, engineering tests of equipment, and chemical and physical properties relevant to safety. All of the testing, studies, and reports were summarized and provided to the DOE to support the Salt Waste Processing Facility, which began conceptual design in September 2002.

  18. Alaska Synthetic Aperture Radar (SAR) Facility science data processing architecture

    NASA Technical Reports Server (NTRS)

    Hilland, Jeffrey E.; Bicknell, Thomas; Miller, Carol L.

    1991-01-01

    The paper describes the architecture of the Alaska SAR Facility (ASF) at Fairbanks, being developed to generate science data products for supporting research in sea ice motion, ice classification, sea-ice-ocean interaction, glacier behavior, ocean waves, and hydrological and geological study areas. Special attention is given to the individual substructures of the ASF: the Receiving Ground Station (RGS), the SAR Processor System, and the Interactive Image Analysis System. The SAR data will be linked to the RGS by the ESA ERS-1 and ERS-2, the Japanese ERS-1, and the Canadian Radarsat.

  19. Pulmonary Alveolar Proteinosis in Workers at an Indium Processing Facility

    PubMed Central

    Cummings, Kristin J.; Donat, Walter E.; Ettensohn, David B.; Roggli, Victor L.; Ingram, Peter; Kreiss, Kathleen

    2010-01-01

    Two cases of pulmonary alveolar proteinosis, including one death, occurred in workers at a facility producing indium-tin oxide (ITO), a compound used in recent years to make flat panel displays. Both workers were exposed to airborne ITO dust and had indium in lung tissue specimens. One worker was tested for autoantibodies to granulocytemacrophagecolonystimulating factor (GM-CSF) and found to have an elevated level. These cases suggest that inhalational exposure to ITO causes pulmonary alveolar proteinosis, which may occur via an autoimmune mechanism. PMID:20019344

  20. 10 CFR 70.72 - Facility changes and change process.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... management system to evaluate, implement, and track each change to the site, structures, processes, systems... integrated safety analysis, integrated safety analysis summary, or other safety program information... in the integrated safety analysis summary; or (ii) Use new processes, technologies, or...

  1. Measurements of methane emissions from natural gas gathering facilities and processing plants: measurement results.

    PubMed

    Mitchell, Austin L; Tkacik, Daniel S; Roscioli, Joseph R; Herndon, Scott C; Yacovitch, Tara I; Martinez, David M; Vaughn, Timothy L; Williams, Laurie L; Sullivan, Melissa R; Floerchinger, Cody; Omara, Mark; Subramanian, R; Zimmerle, Daniel; Marchese, Anthony J; Robinson, Allen L

    2015-03-01

    Facility-level methane emissions were measured at 114 gathering facilities and 16 processing plants in the United States natural gas system. At gathering facilities, the measured methane emission rates ranged from 0.7 to 700 kg per hour (kg/h) (0.6 to 600 standard cubic feet per minute (scfm)). Normalized emissions (as a % of total methane throughput) were less than 1% for 85 gathering facilities and 19 had normalized emissions less than 0.1%. The range of methane emissions rates for processing plants was 3 to 600 kg/h (3 to 524 scfm), corresponding to normalized methane emissions rates <1% in all cases. The distributions of methane emissions, particularly for gathering facilities, are skewed. For example, 30% of gathering facilities contribute 80% of the total emissions. Normalized emissions rates are negatively correlated with facility throughput. The variation in methane emissions also appears driven by differences between inlet and outlet pressure, as well as venting and leaking equipment. Substantial venting from liquids storage tanks was observed at 20% of gathering facilities. Emissions rates at these facilities were, on average, around four times the rates observed at similar facilities without substantial venting. PMID:25668106

  2. Facility design philosophy: Tank Waste Remediation System Process support and infrastructure definition

    SciTech Connect

    Leach, C.E.; Galbraith, J.D.; Grant, P.R.; Francuz, D.J.; Schroeder, P.J.

    1995-11-01

    This report documents the current facility design philosophy for the Tank Waste Remediation System (TWRS) process support and infrastructure definition. The Tank Waste Remediation System Facility Configuration Study (FCS) initially documented the identification and definition of support functions and infrastructure essential to the TWRS processing mission. Since the issuance of the FCS, the Westinghouse Hanford Company (WHC) has proceeded to develop information and requirements essential for the technical definition of the TWRS treatment processing programs.

  3. Implementing full backtracking facilities for Prolog-based image processing

    NASA Astrophysics Data System (ADS)

    Jones, Andrew C.; Batchelor, Bruce G.

    1995-10-01

    PIP (Prolog image processing) is a system currently under development at UWCC, designed to support interactive image processing using the PROLOG programming language. In this paper we discuss Prolog-based image processing paradigms and present a meta-interpreter developed by the first author, designed to support an approach to image processing in PIP which is more in the spirit of Prolog than was previously possible. This meta-interpreter allows backtracking over image processing operations in a manner transparent to the programmer. Currently, for space-efficiency, the programmer needs to indicate over which operations the system may backtrack in a program; however, a number of extensions to the present work, including a more intelligent approach intended to obviate this need, are mentioned at the end of this paper, which the present meta-interpreter will provide a basis for investigating in the future.

  4. Seismic Qualification Program Plan for continued operation at DOE-SRS Nuclear Material Processing facilities

    SciTech Connect

    Talukdar, B.K.; Kennedy, W.N.

    1991-01-01

    The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.1A requirements. In addition, any of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) has developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards for existing NMP facility structures to continue operation. Professionals involved in similar effort at other DOE facilities may find the program useful.

  5. Seismic Qualification Program Plan for continued operation at DOE-SRS Nuclear Material Processing facilities

    SciTech Connect

    Talukdar, B.K.; Kennedy, W.N.

    1991-12-31

    The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.1A requirements. In addition, any of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) has developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards for existing NMP facility structures to continue operation. Professionals involved in similar effort at other DOE facilities may find the program useful.

  6. A new design concept for an automated peanut processing facility

    SciTech Connect

    Ertas, A.; Tanju, B.T.; Fair, W.T.; Butts, C.

    1996-12-31

    Peanut quality is a major concern in all phases of the peanut industry from production to manufacturing. Postharvest processing of peanuts can have profound effects on the quality and safety of peanut food products. Curing is a key step in postharvest processing. Curing peanuts improperly can significantly reduce quality, and result in significant losses to both farmers and processors. The conventional drying system designed in the 1960`s is still being used in the processing of the peanuts today. The objectives of this paper is to design and develop a new automated peanut drying system for dry climates capable of handling approximately 20 million lbm of peanuts per harvest season.

  7. REPORT ON TWO PROCESS EQUIPMENT CHANGES FOR FEDERAL PAINTING FACILITIES

    EPA Science Inventory

    EPA's National Risk Management Research Laboratory (NRMRL) has actively participated in the Strategic Environmental Research and Development Program (SERDP) to develop innovative technologies and processes for the reduction of environmental pollution. Technology developments fro...

  8. Characterization of decontamination and decommissioning wastes expected from the major processing facilities in the 200 Areas

    SciTech Connect

    Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A.; Duncan, D.R.

    1994-08-01

    This study was intended to characterize and estimate the amounts of equipment and other materials that are candidates for removal and subsequent processing in a solid waste facility when the major processing and handling facilities in the 200 Areas of the Hanford Site are decontaminated and decommissioned. The facilities in this study were selected based on processing history and on the magnitude of the estimated decommissioning cost cited in the Surplus Facilities Program Plan; Fiscal Year 1993 (Winship and Hughes 1992). The facilities chosen for this study include B Plant (221-B), T Plant (221-T), U Plant (221-U), the Uranium Trioxide (UO{sub 3}) Plant (224-U and 224-UA), the Reduction Oxidation (REDOX) or S Plant (202-S), the Plutonium Concentration Facility for B Plant (224-B), and the Concentration Facility for the Plutonium Finishing Plant (PFP) and REDOX (233-S). This information is required to support planning activities for current and future solid waste treatment, storage, and disposal operations and facilities.

  9. Criticality safety evaluation report for the cold vacuum drying facility's process water handling system

    SciTech Connect

    NELSON, J.V.

    1999-05-12

    This report addresses the criticality concerns associated with process water handling in the Cold Vacuum Drying Facility. The controls and limitations on equipment design and operations to control potential criticality occurrences are identified.

  10. 10 CFR 95.15 - Approval for processing licensees and others for facility clearance.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Procedures Plan that outlines the facility's proposed security procedures and controls for the protection of classified information, a floor plan of the area in which the matter is to be used, processed,...

  11. 10 CFR 95.15 - Approval for processing licensees and others for facility clearance.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Procedures Plan that outlines the facility's proposed security procedures and controls for the protection of classified information, a floor plan of the area in which the matter is to be used, processed,...

  12. 10 CFR 95.15 - Approval for processing licensees and others for facility clearance.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Procedures Plan that outlines the facility's proposed security procedures and controls for the protection of classified information, a floor plan of the area in which the matter is to be used, processed,...

  13. 10 CFR 95.15 - Approval for processing licensees and others for facility clearance.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Procedures Plan that outlines the facility's proposed security procedures and controls for the protection of classified information, a floor plan of the area in which the matter is to be used, processed,...

  14. Receipt of the Observatory at the Orbital Processing Facility - Duration: 61 seconds.

    NASA Video Gallery

    These series of photos show the receipt of the observatory at the Orbital processing facility at VAFB. The observatory was received on April 16, 2013 and transferred to its handling fixture and the...

  15. Plutonium production story at the Hanford site: processes and facilities history

    SciTech Connect

    Gerber, M.S., Westinghouse Hanford

    1996-06-20

    This document tells the history of the actual plutonium production process at the Hanford Site. It contains five major sections: Fuel Fabrication Processes, Irradiation of Nuclear Fuel, Spent Fuel Handling, Radiochemical Reprocessing of Irradiated Fuel, and Plutonium Finishing Operations. Within each section the story of the earliest operations is told, along with changes over time until the end of operations. Chemical and physical processes are described, along with the facilities where these processes were carried out. This document is a processes and facilities history. It does not deal with the waste products of plutonium production.

  16. Lax regulation of oil vessels and processing facilities continues

    SciTech Connect

    Sankovitch, N.

    1993-12-31

    Four years after the grounding of the Exxon Valdez on Bligh Reef in 1989, oil spills continue to occur with alarming frequency: In 1992 the Shoko Maru spilled more than 96,000 gallons of crude oil into the Texas City Channel and a leak at an offshore well in Louisiana spilled at least 30,000 gallons; in 1991 alone, there were 677 spills in the Port of New Orleans, 398 spills in New York Harbor, 239 spills in Port of Hampton Roads, 235 spills in Port of Philadelphia, 130 spills in Seattle, and 116 spills in Boston Harbor. The amount of oil spilled in these ports alone in one year exceeded 300,000 gallons. The recent huge spills off foreign coasts-the Shetland Islands, the coasts of Spain and Indonesia-reinforce the importance of regulation. The Oil Pollution Act, passed in August 1992 mandates that all vessels traveling in US waters and all oil transfer and storage facilities take measurable and enforceable actions to reduce spills. However, major problems remain, both with the act and with enforcing it. This article discusses both the problems and the solutions to pollution control of oil spills.

  17. Zero-Release Mixed Waste Process Facility Design and Testing

    SciTech Connect

    Richard D. Boardman; John A. Deldebbio; Robert J. Kirkham; Martin K. Clemens; Robert Geosits; Ping Wan

    2004-02-01

    A zero-release offgas cleaning system for mixed-waste thermal treatment processes has been evaluated through experimental scoping tests and process modeling. The principles can possibly be adapted to a fluidized-bed calcination or stream reforming process, a waste melter, a rotarykiln process, and possibly other waste treatment thermal processes. The basic concept of a zero-release offgas cleaning system is to recycle the bulk of the offgas stream to the thermal treatment process. A slip stream is taken off the offgas recycle to separate and purge benign constituents that may build up in the gas, such as water vapor, argon, nitrogen, and CO2. Contaminants are separated from the slip stream and returned to the thermal unit for eventual destruction or incorporation into the waste immobilization media. In the current study, a standard packed-bed scrubber, followed by gas separation membranes, is proposed for removal of contaminants from the offgas recycle slipstream. The scrub solution is continuously regenerated by cooling and precipitating sulfate, nitrate, and other salts that reach a solubility limit in the scrub solution. Mercury is also separated by the scrubber. A miscible chemical oxidizing agent was shown to effectively oxidize mercury and also NO, thus increasing their removal efficiency. The current study indicates that the proposed process is a viable option for reducing offgas emissions. Consideration of the proposed closed-system offgas cleaning loop is warranted when emissions limits are stringent, or when a reduction in the total gas emissions volume is desired. Although the current closed-loop appears to be technically feasible, economical considerations must be also be evaluated on a case-by-case basis.

  18. Technical feasibility of transuranic tank waste processing in high-level waste vitrification facility

    SciTech Connect

    Crawford, T.W.; Manuel, A.F., Westinghouse Hanford

    1996-07-26

    The objective of this study is to determine the technical feasibility of processing transuranic tank waste in a high-level waste vitrification facility. This is achieved by performing an impact assessment of a reference case high-level waste facility modified to separately process transuranic waste. Data are presented for Hanford Site transuranic wastes and are compared against established waste acceptance criteria for the Waste Isolation Pilot Plant program. Schedule and cost impacts are evaluated for the proposed transuranic campaign.

  19. Grout pump selection process for the Transportable Grout Facility

    SciTech Connect

    McCarthy, D.; Treat, R.L.

    1985-01-01

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

  20. SSOPs and GMPs for commercial shell egg processing facilities

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Hazard analysis and critical control programs (HACCP) will eventually be required for commercial shell egg processing plants. Sanitation is an essential prerequisite program for HACCP and is based upon current Good Manufacturing Practices (cGMPs) as listed in the Code of Federal Regulations. Good ...

  1. Application of artificial intelligence to melter control: Realtime process advisor for the scale melter facility

    SciTech Connect

    Edwards, Jr, R E

    1988-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Plant (SRP) is currently under construction and when completed will process high-level radioactive waste into a borosilicate glass wasteform. This facility will consist of numerous batch chemical processing steps as well as the continuous operation of a joule-heated melter and its off-gas treatment system. A realtime process advisor system based on Artificial Intelligence (AI) techniques has been developed and is currently in use at the semiworks facility, which is operating a 2/3 scale of the DWPF joule-heated melter. The melter advisor system interfaces to the existing data collection and control system and monitors current operations of this facility. The advisor then provides advice to operators and engineers when it identifies process problems. The current system is capable of identifying process problems such as feed system pluggages and thermocouple failures and providing recommended actions. The system also provides facilities normally with distributed control systems. These include the ability to display process flowsheets, monitor alarm conditions, and check the status of process interlocks. 7 figs.

  2. Facilities

    NASA Technical Reports Server (NTRS)

    1999-01-01

    An expansion of medical data collection facilities was necessary to implement the Extended Duration Orbiter Medical Project (EDOMP). The primary objective of the EDOMP was to ensure the capability of crew members to reenter the Earth's atmosphere, land, and egress safely following a 16-day flight. Therefore, access to crew members as soon as possible after landing was crucial for most data collection activities. Also, with the advent of EDOMP, the quantity of investigations increased such that the landing day maximum data collection time increased accordingly from two hours to four hours. The preflight and postflight testing facilities at the Johnson Space Center (JSC) required only some additional testing equipment and minor modifications to the existing laboratories in order to fulfill EDOMP requirements. Necessary modifications at the landing sites were much more extensive.

  3. Leveraging the PASRR process to divert and transition elders with mental illness from nursing facilities.

    PubMed

    O'Connor, Darlene; Ingle, Jennifer S; Wamback, Kimberly N

    2011-01-01

    This study examines how some states use Pre-Admission Screening and Resident Review (PASRR) processes to provide opportunities for nursing facility diversion and/or transition for elders with mental illness and highlights potential promising practices from selected states. Document reviews and interviews were conducted with key informants across 13 states. Key themes presented are 1) philosophies of diversion/transition embedded into PASRR processes, 2) questions on screening tools used to promote diversion/transition, 3) PASRR authorities' collaboration with other initiatives to promote diversion/transition, and 4) the extent to which states used PASRR to help identify mental health supports needed by nursing facility residents. Findings provide policy-relevant information to help states consider enhancement of their PASRR processes to further support nursing facility diversion and transition for persons with mental illness and improved mental health services for those in nursing facilities. PMID:21740204

  4. Progress of the High Level Waste Program at the Defense Waste Processing Facility - 13178

    SciTech Connect

    Bricker, Jonathan M.; Fellinger, Terri L.; Staub, Aaron V.; Ray, Jeff W.; Iaukea, John F.

    2013-07-01

    The Defense Waste Processing Facility at the Savannah River Site treats and immobilizes High Level Waste into a durable borosilicate glass for safe, permanent storage. The High Level Waste program significantly reduces environmental risks associated with the storage of radioactive waste from legacy efforts to separate fissionable nuclear material from irradiated targets and fuels. In an effort to support the disposition of radioactive waste and accelerate tank closure at the Savannah River Site, the Defense Waste Processing Facility recently implemented facility and flowsheet modifications to improve production by 25%. These improvements, while low in cost, translated to record facility production in fiscal years 2011 and 2012. In addition, significant progress has been accomplished on longer term projects aimed at simplifying and expanding the flexibility of the existing flowsheet in order to accommodate future processing needs and goals. (authors)

  5. Development of Advanced Multizone Facilities for Microgravity Processing

    NASA Technical Reports Server (NTRS)

    1998-01-01

    NASA has been interested in experimental ground based study to investigate the fundamental processes involved in phase transformation processes during growth of metallic, nonmetallic and electronic materials. Solidification, vapor growth and solution growth techniques of growing crystals are of special interest because of the inherent importance of convection in the nutrient solution. Convection enhances the mass transport through the nutrient and results in faster growth rates. Availability of low gravity environment of space has provided scientists a new variable to control the extent of convection and thus isolate the diffusive phenomena for their better understanding. The thermal gradient at the liquid-solid interface is determined by the alloy characteristics, the hot zone temperature, cold zone temperature and the width of the insulating zone. The thermal profiles get established by the existing material and geometrical constraints of the experimental set up. The major effort under this research was devoted to designing a programmable furnace which can be used to obtain thermal profiles along the length of the sample as per the demands of the scientists. The furnace did not have active cooling of the zones. Only active heating and passive cooling were utilized.

  6. The performance assessment process for DOE low-level waste disposal facilities

    SciTech Connect

    Wilhite, E.L.

    1992-11-01

    Safety of the low-level waste disposal facilities, as well as al US DOE facilities, is a primary criterion in their design and operation. Safety of low-level waste disposal facilities is evaluated from two perspectives. Operational safety is evaluated based on the perceived level of hazard of the operation. The safety evaluations vary from simple safety assessments to very complex safety analysis reports, depending on the degree of hazard associated with the facility operation. Operational requirements for the Department`s low-level waste disposal facilities, including long-term safety are contained in DOE Order 5820.2A, Radioactive Waste Management (1). This paper will focus on the process of conducting long-term performance analyses rather than on operational safety analysis.

  7. The performance assessment process for DOE low-level waste disposal facilities

    SciTech Connect

    Wilhite, E.L.

    1992-01-01

    Safety of the low-level waste disposal facilities, as well as al US DOE facilities, is a primary criterion in their design and operation. Safety of low-level waste disposal facilities is evaluated from two perspectives. Operational safety is evaluated based on the perceived level of hazard of the operation. The safety evaluations vary from simple safety assessments to very complex safety analysis reports, depending on the degree of hazard associated with the facility operation. Operational requirements for the Department's low-level waste disposal facilities, including long-term safety are contained in DOE Order 5820.2A, Radioactive Waste Management (1). This paper will focus on the process of conducting long-term performance analyses rather than on operational safety analysis.

  8. Multi-user real-time speech processing facility

    NASA Astrophysics Data System (ADS)

    Pisoni, D. B.

    1985-03-01

    Research projects requiring the VAX 11/750 and related peripherals have all focused on speech analysis, perception and recognition. We compared perceptual confusions occurring for natural and synthetic speech syllables which showed that synthetic speech is not equivalent to noisy or degraded natural speech. We conducted a study that indicated that perception of synthetic speech is improved by training. Training with fluent synthetic sentences improves performance for both isolated words and sentences. Training with isolated words improves performance on isolated words but does not improve performance on fluent synthetic sentences. A large-scale series of experiments investigated the effects of noise in a talker's ears on speech production. Words produced in noise are longer, louder and higher in pitch than words produced in the quiet. The tilt of the power spectrum decreased and formant frequencies shifted in noise. nition, I/O, human factors, cognitive processes, and communication sciences.

  9. Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 1

    SciTech Connect

    Not Available

    1994-03-01

    This ACDR was performed following completed of the Conceptual Design Report in July 1992; the work encompassed August 1992 to January 1994. Mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage at Hanford and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford from about DOE sites. This volume provides an introduction to the ACDR process and the scope of the task along with a project summary of the facility, treatment technologies, cost, and schedule. Major areas of departure from the CDR are highlighted. Descriptions of the facility layout and operations are included.

  10. Implementation of the DYMAC system at the new Los Alamos Plutonium Processing Facility. Phase II report

    SciTech Connect

    Malanify, J.J.; Amsden, D.C.

    1982-08-01

    The DYnamic Materials ACcountability System - called DYMAC - performs accountability functions at the new Los Alamos Plutonium Processing Facility where it began operation when the facility opened in January 1978. A demonstration program, DYMAC was designed to collect and assess inventory information for safeguards purposes. It accomplishes 75% of its design goals. DYMAC collects information about the physical inventory through deployment of nondestructive assay instrumentation and video terminals throughout the facility. The information resides in a minicomputer where it can be immediately sorted and displayed on the video terminals or produced in printed form. Although the capability now exists to assess the collected data, this portion of the program is not yet implemented. DYMAC in its present form is an excellent tool for process and quality control. The facility operator relies on it exclusively for keeping track of the inventory and for complying with accountability requirements of the US Department of Energy.

  11. Design of the Waste Receiving and Processing Module 2A Facility

    SciTech Connect

    Lamberd, D.L.

    1993-03-01

    Westinghouse Hanford Company has determined that a facility is required for the treatment of mixed low-level waste at the Hanford Site. The mission of that facility will be to receive, process/treat, package, certify, and ship the contact-handled, mixed low-level waste that must be handled by Hanford Site to permanent disposal. Preconceptual and conceptual design studies were performed by United Engineers and Constructors, and a conceptual design report was issued. This report presents a summary of the conceptual design for a facility that will meet the mission established.

  12. Integrating real-time digital signal processing capability into a large research and development facility

    SciTech Connect

    Manges, W.W.; Mallinak-Glassell, J.T.; Breeding, J.E.; Jansen, J.M. Jr.; Tate, R.M.; Bentz, R.R.

    1992-01-01

    The Instrumentation and Controls Division at Oak Ridge National Laboratory recently developed and installed a large scale, real-time measurement system for the world's largest pressurized water tunnel. This water tunnel, the Large Cavitation Channel (LCC) provides a research and development facility for the study of acoustic phenomena to aid in model testing of new naval ship and submarine designs. The LCC design required the development of a near-field beamformer in addition to extending the range of real-time processing capability to frequencies unavailable at other facilities. The beamformer acquires and processes time-domain acoustic data at 9.5 MB/s from up to 45 hydrophones while. The acoustic processing software provides for the real-time analysis of acoustic data. Up to 128 facility sensors are sampled, time stamped, and stored at 600 kB/s. The system generates information for acoustic phenomena and facility measurements in real time so that the operator can make facility adjustments to control the running experiment This real-time control of facility conditions requires that the measurement system integrate facility and acoustic data for simultaneous display to the operator in engineering units via high-end workstations. A dual-host minicomputer configuration with high-end workstations connected via an Ethernet networking cluster controls and integrates measurement and display subsystems. The system architecture integrates high-performance array processors, matrix switches, signal conditioning amplifiers, antialiasing filter subsystems, high-precision analog-to-digital subsystems, high-performance data disks, and support equipment The hardware and software architecture with its distributed computers and distributed real-time data base, the signal processing algorithms and architecture, and the flexible user interface for facility and measurements integration are described in this paper.

  13. Integrating real-time digital signal processing capability into a large research and development facility

    SciTech Connect

    Manges, W.W.; Mallinak-Glassell, J.T.; Breeding, J.E.; Jansen, J.M. Jr.; Tate, R.M.; Bentz, R.R.

    1992-12-31

    The Instrumentation and Controls Division at Oak Ridge National Laboratory recently developed and installed a large scale, real-time measurement system for the world`s largest pressurized water tunnel. This water tunnel, the Large Cavitation Channel (LCC) provides a research and development facility for the study of acoustic phenomena to aid in model testing of new naval ship and submarine designs. The LCC design required the development of a near-field beamformer in addition to extending the range of real-time processing capability to frequencies unavailable at other facilities. The beamformer acquires and processes time-domain acoustic data at 9.5 MB/s from up to 45 hydrophones while. The acoustic processing software provides for the real-time analysis of acoustic data. Up to 128 facility sensors are sampled, time stamped, and stored at 600 kB/s. The system generates information for acoustic phenomena and facility measurements in real time so that the operator can make facility adjustments to control the running experiment This real-time control of facility conditions requires that the measurement system integrate facility and acoustic data for simultaneous display to the operator in engineering units via high-end workstations. A dual-host minicomputer configuration with high-end workstations connected via an Ethernet networking cluster controls and integrates measurement and display subsystems. The system architecture integrates high-performance array processors, matrix switches, signal conditioning amplifiers, antialiasing filter subsystems, high-precision analog-to-digital subsystems, high-performance data disks, and support equipment The hardware and software architecture with its distributed computers and distributed real-time data base, the signal processing algorithms and architecture, and the flexible user interface for facility and measurements integration are described in this paper.

  14. Preliminary technical data summary No. 3 for the Defense Waste Processing Facility

    SciTech Connect

    Landon, L.F.

    1980-05-01

    This document presents an update on the best information presently available for the purpose of establishing the basis for the design of a Defense Waste Processing Facility. Objective of this project is to provide a facility to fix the radionuclides present in Savannah River Plant (SRP) high-level liquid waste in a high-integrity form (glass). Flowsheets and material balances reflect the alternate CAB case including the incorporation of low-level supernate in concrete. (DLC)

  15. Data reduction complex analog-to-digital data processing requirements for onsite test facilities

    NASA Technical Reports Server (NTRS)

    Debbrecht, J. D.

    1976-01-01

    The analog to digital processing requirements of onsite test facilities are described. The source and medium of all input data to the Data Reduction Complex (DRC) and the destination and medium of all output products of the analog-to-digital processing are identified. Additionally, preliminary input and output data formats are presented along with the planned use of the output products.

  16. 10 CFR 1016.8 - Approval for processing access permittees for security facility approval.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 4 2011-01-01 2011-01-01 false Approval for processing access permittees for security facility approval. 1016.8 Section 1016.8 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.8 Approval for processing access permittees for security...

  17. 10 CFR 1016.8 - Approval for processing access permittees for security facility approval.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 4 2013-01-01 2013-01-01 false Approval for processing access permittees for security facility approval. 1016.8 Section 1016.8 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.8 Approval for processing access permittees for security...

  18. 10 CFR 1016.8 - Approval for processing access permittees for security facility approval.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 4 2014-01-01 2014-01-01 false Approval for processing access permittees for security facility approval. 1016.8 Section 1016.8 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.8 Approval for processing access permittees for security...

  19. 10 CFR 1016.8 - Approval for processing access permittees for security facility approval.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 4 2012-01-01 2012-01-01 false Approval for processing access permittees for security facility approval. 1016.8 Section 1016.8 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security 1016.8 Approval for processing access permittees for security...

  20. AERIAL SHOWING COMPLETED REMOTE ANALYTICAL FACILITY (CPP627) ADJOINING FUEL PROCESSING ...

    Library of Congress Historic Buildings Survey, Historic Engineering Record, Historic Landscapes Survey

    AERIAL SHOWING COMPLETED REMOTE ANALYTICAL FACILITY (CPP-627) ADJOINING FUEL PROCESSING BUILDING AND EXCAVATION FOR HOT PILOT PLANT TO RIGHT (CPP-640). INL PHOTO NUMBER NRTS-60-1221. J. Anderson, Photographer, 3/22/1960 - Idaho National Engineering Laboratory, Idaho Chemical Processing Plant, Fuel Reprocessing Complex, Scoville, Butte County, ID

  1. Assessment of Microbial Contaminants Present on Vacuum Loaders in Shell Egg Processing Facilities

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Previous studies have shown vacuum loader cups in shell egg processing facilities to be a reservoir of high levels of bacteria. This study was conducted to determine the prevalence of pathogens on the surface of the vacuum loaders cups. An off-line and a mixed operation shell egg processing facili...

  2. 10 CFR 1016.8 - Approval for processing access permittees for security facility approval.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Approval for processing access permittees for security facility approval. 1016.8 Section 1016.8 Energy DEPARTMENT OF ENERGY (GENERAL PROVISIONS) SAFEGUARDING OF RESTRICTED DATA Physical Security § 1016.8 Approval for processing access permittees for security...

  3. Enterobacteriaceae and related organisms isolated from nest run cart shelves in commercial shell egg processing facilities

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Enterobacteriaceae, including Salmonella may be recovered from foods and processing facilities. High levels of Enterobacteriaceae in the processing plant environment can be an indication of inadequate sanitation. This experiment was designed to determine if nest run egg carts serve as reservoirs ...

  4. ST. LOUIS DEMONSTRATION: REFUSE PROCESSING PLANT EQUIPMENT, FACILITIES, AND ENVIRONMENTAL EVALUATIONS

    EPA Science Inventory

    This report presents the results of processing plant evaluations of the St. Louis-Union Electric Refuse Fuel Project, including equipment and facilities as well as assessment of environmental emissions at both the processing and power plants. Data on plant material flows and oper...

  5. How Do Noninvasive Imaging Facilities Perceive the Accreditation Process? Results of an Intersocietal Accreditation Commission Survey.

    PubMed

    Manning, Warren J; Farrell, Mary B; Bezold, Louis I; Choi, John Y; Cockroft, Kevin M; Gornik, Heather L; Jerome, Scott D; Katanick, Sandra L; Heller, Gary V

    2015-07-01

    The Intersocietal Accreditation Commission (IAC) accredits vascular, echocardiography, nuclear medicine, computed tomography, and magnetic resonance imaging laboratories. How facilities involved in the accreditation process view accreditation is unknown. The objective of this study was to examine the perception of laboratory accreditation from those who had undergone the process. An electronic survey request was sent to all facilities that had received IAC accreditation at least once. Demographic information, as well as opinions on the perceived value of accreditation as it relates to 15 quality metrics was acquired. Responses were obtained from 2782 facilities. Of the 15 quality metrics examined, the process was perceived as leading to improvements by a majority of respondents for 10 (67%) metrics including: report standardization, adherence to guidelines, test standardization, report completeness, identification of deficiencies, improved staff knowledge, report timeliness, distinguished facility, correction of deficiencies, and image quality. Overall, the perceived improvement was greater for hospital-based facilities (global 66% vs 59%; P < 0.001). Survey data demonstrate that the accreditation process has a positive perceived impact on the majority of examined metrics. These findings suggest that those undergoing the process find value in accreditation. PMID:26072711

  6. Nuclear Solid Waste Processing Design at the Idaho Spent Fuels Facility

    SciTech Connect

    Dippre, M. A.

    2003-02-25

    A spent nuclear fuels (SNF) repackaging and storage facility was designed for the Idaho National Engineering and Environmental Laboratory (INEEL), with nuclear solid waste processing capability. Nuclear solid waste included contaminated or potentially contaminated spent fuel containers, associated hardware, machinery parts, light bulbs, tools, PPE, rags, swabs, tarps, weld rod, and HEPA filters. Design of the nuclear solid waste processing facilities included consideration of contractual, regulatory, ALARA (as low as reasonably achievable) exposure, economic, logistical, and space availability requirements. The design also included non-attended transfer methods between the fuel packaging area (FPA) (hot cell) and the waste processing area. A monitoring system was designed for use within the FPA of the facility, to pre-screen the most potentially contaminated fuel canister waste materials, according to contact- or non-contact-handled capability. Fuel canister waste materials which are not able to be contact-handled after attempted decontamination will be processed remotely and packaged within the FPA. Noncontact- handled materials processing includes size-reduction, as required to fit into INEEL permitted containers which will provide sufficient additional shielding to allow contact handling within the waste areas of the facility. The current design, which satisfied all of the requirements, employs mostly simple equipment and requires minimal use of customized components. The waste processing operation also minimizes operator exposure and operator attendance for equipment maintenance. Recently, discussions with the INEEL indicate that large canister waste materials can possibly be shipped to the burial facility without size-reduction. New waste containers would have to be designed to meet the drop tests required for transportation packages. The SNF waste processing facilities could then be highly simplified, resulting in capital equipment cost savings, operational time savings, and significantly improved ALARA exposure.

  7. Waste Receiving and Processing (WRAP) Facility Final Safety Analysis Report (FSAR)

    SciTech Connect

    TOMASZEWSKI, T.A.

    2000-04-25

    The Waste Receiving and Processing Facility (WRAP), 2336W Building, on the Hanford Site is designed to receive, confirm, repackage, certify, treat, store, and ship contact-handled transuranic and low-level radioactive waste from past and present U.S. Department of Energy activities. The WRAP facility is comprised of three buildings: 2336W, the main processing facility (also referred to generically as WRAP); 2740W, an administrative support building; and 2620W, a maintenance support building. The support buildings are subject to the normal hazards associated with industrial buildings (no radiological materials are handled) and are not part of this analysis except as they are impacted by operations in the processing building, 2336W. WRAP is designed to provide safer, more efficient methods of handling the waste than currently exist on the Hanford Site and contributes to the achievement of as low as reasonably achievable goals for Hanford Site waste management.

  8. Nonradioactive air emissions notice of construction for the Waste Receiving And Processing facility

    SciTech Connect

    Not Available

    1993-02-01

    The mission of the Waste Receiving And Processing (WRAP) Module 1 facility (also referred to as WRAP 1) is to examine assay, characterize, treat, and repackage solid radioactive and mixed waste to enable permanent disposal of the wastes in accordance with all applicable regulations. WRAP 1 will contain equipment and facilities necessary for non-destructive examination (NDE) of wastes and to perform a non-destructive examination assay (NDA) of the total radionuclide content of the wastes, without opening the outer container (e.g., 55-gal drum). WRAP 1 will also be equipped to open drums which do not meet waste acceptance and shipping criteria, and to perform limited physical treatment of the wastes to ensure that storage, shipping, and disposal criteria are met. The solid wastes to be handled in the WRAP 1 facility include low level waste (LLW), transuranic (TRU) waste, and transuranic and low level mixed wastes (LLMW). The WRAP 1 facility will only accept contact handler (CH) waste containers. A Best Available Control Technology for Toxics (TBACT) assessment has been completed for the WRAP 1 facility (WHC 1993). Because toxic emissions from the WRAP 1 facility are sufficiently low and do not pose any health or safety concerns to the public, no controls for volatile organic compounds (VOCs), and installation of HEPA filters for particulates satisfy TBACT for the facility.

  9. Facility siting as a decision process at the Savannah River Site

    SciTech Connect

    Wike, L.D.

    1995-12-31

    Site selection for new facilities at Savannah River Site (SRS) historically has been a process dependent only upon specific requirements of the facility. While this approach is normally well suited to engineering and operational concerns, it can have serious deficiencies in the modern era of regulatory oversight and compliance requirements. There are many issues related to the site selection for a facility that are not directly related to engineering or operational requirements; such environmental concerns can cause large schedule delays and budget impact,s thereby slowing or stopping the progress of a project. Some of the many concerns in locating a facility include: waste site avoidance, National Environmental Policy Act requirements, Clean Water Act, Clean Air Act, wetlands conservation, US Army Corps of Engineers considerations, US Fish and Wildlife Service statutes including threatened and endangered species issues, and State of South Carolina regulations, especially those of the Department of Health and Environmental Control. In addition, there are SRS restrictions on research areas set aside for National Environmental Research Park (NERP), Savannah River Ecology Laboratory, Savannah River Forest Station, University of South Carolina Institute of Archaeology and Anthropology, Southeastern Forest Experimental Station, and Savannah River Technology Center (SRTC) programs. As with facility operational needs, all of these siting considerations do not have equal importance. The purpose of this document is to review recent site selection exercises conducted for a variety of proposed facilities, develop the logic and basis for the methods employed, and standardize the process and terminology for future site selection efforts.

  10. Onboard experiment data support facility. Task 2 report: Definition of onboard processing requirements

    NASA Technical Reports Server (NTRS)

    1976-01-01

    The onboard experiment data support facility (OEDSF) will provide data processing support to various experiment payloads on board the space shuttle. The OEDSF study will define the conceptual design and generate specifications for an OEDSF which will meet the following objectives: (1) provide a cost-effective approach to end-to-end processing requirements, (2) service multiple disciplines (3) satisfy user needs, (4) reduce the amount and improve the quality of data collected, stored and processed, and (5) embody growth capacity.

  11. Performance of a coal-gas-cleanup process-evaluation facility

    SciTech Connect

    Rib, D M; Kimura, S G; Smith, D P

    1982-06-09

    A coal gasification combined cycle process evaluation facility has been operated. The gas cleanup process, which contains the major functional elements of a commercial low temperature gas cleanup process has been evaluated. The critical unit operations, which include H/sub 2/S removal with a Benfield acid gas scrubbing system, particulate scrubbing, and condensate reutilization have been evaluated. Results indicate that all functional, environmental, and gas turbine specifications can be met.

  12. The Establishment of a New Friction Stir Welding Process Development Facility at NASA/MSFC

    NASA Technical Reports Server (NTRS)

    Carter, Robert W.

    2009-01-01

    Full-scale weld process development is being performed at MSFC to develop the tools, fixtures, and facilities necessary for Ares I production. Full scale development in-house at MSFC fosters technical acuity within the NASA engineering community, and allows engineers to identify and correct tooling and equipment shortcomings before they become problems on the production floor. Finally, while the new weld process development facility is currently being outfitted in support of Ares I development, it has been established to support all future Constellation Program needs. In particular, both the RWT and VWT were sized with the larger Ares V hardware in mind.

  13. Design and testing of the defense waste processing facility melter drain valve

    SciTech Connect

    Edwards, R. Jr.; Glascock, J.

    1986-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Plant will use a joule-heated glass melter to process high-level radioactive defense waste into a borosilicate glass waste form. A prototype of a valve to drain the remaining glass from the melter at the end of its useful life is being tested at the Equipment Test Facility of the Savannah River Laboratory. The objective is to demonstrate the mechanical functionality of the valve and to uncover and solve problems related to its operation in the DWPF. 4 refs., 2 figs.

  14. Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 2

    SciTech Connect

    Not Available

    1994-03-01

    This volume presents the Total Estimated Cost (TEC) for the WRAP (Waste Receiving and Processing) 2A facility. The TEC is $81.9 million, including an overall project contingency of 25% and escalation of 13%, based on a 1997 construction midpoint. (The mission of WRAP 2A is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage, and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford site from about 20 DOE sites.)

  15. Waste minimization and the goal of an environmentally benign plutonium processing facility: A strategic plan

    SciTech Connect

    Pillay, K.K.S.

    1994-02-01

    To maintain capabilities in nuclear weapons technologies, the Department of Energy (DOE) has to maintain a plutonium processing facility that meets all the current and emerging standards of environmental regulations. A strategic goal to transform the Plutonium Processing Facility at Los Alamos into an environmentally benign operation is identified. A variety of technologies and systems necessary to meet this goal are identified. Two initiatives now in early stages of implementation are described in some detail. A highly motivated and trained work force and a systems approach to waste minimization and pollution prevention are necessary to maintain technical capabilities, to comply with regulations, and to meet the strategic goal.

  16. Inline Monitors for Measuring Cs-137 in the SRS Caustic Side Solvent Extraction Process

    SciTech Connect

    Casella, V

    2006-04-24

    The Department of Energy (DOE) selected Caustic-Side Solvent Extraction (CSSX) as the preferred technology for the removal of radioactive cesium from High-Level Waste (HLW) at the Savannah River Site (SRS). Before the full-scale Salt Waste Processing Facility (SWPF) becomes operational, a portion of dissolved saltcake waste will be processed through a Modular CSSX Unit (MCU). The MCU employs the CSSX process, a continuous process that uses a novel solvent to extract cesium from waste and concentrate it in dilute nitric acid. Of primary concern is Cs-137 which makes the solution highly radioactive. Since the MCU does not have the capacity to wait for sample results while continuing to operate, the Waste Acceptance Strategy is to perform inline analyses. Gamma-ray monitors are used to: measure the Cs-137 concentration in the decontaminated salt solution (DSS) before entering the DSS Hold Tank; measure the Cs-137 concentration in the strip effluent (SE) before entering the SE Hold Tank; and verify proper operation of the solvent extraction system by verifying material balance within the process. Since this gamma ray monitoring system application is unique, specially designed shielding was developed and software was written and acceptance tested by Savannah River National Laboratory (SRNL) personnel. The software is a LabView-based application that serves as a unified interface for controlling the monitor hardware and communicating with the host Distributed Control System. This paper presents the design, fabrication and implementation of this monitoring system.

  17. Conceptual design for the Waste Receiving and Processing facility Module 2A

    SciTech Connect

    Not Available

    1992-07-01

    This is a Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility at Hanford Reservation. The mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. The primary sources of waste to be treated at WRAP Module 2A include the currently stored waste from the 183-H solar basin evaporators, secondary solids from the future Hanford site liquid effluent treatment facilities, thermal treatment facility ash, other WRAP modules, and other, miscellaneous waste from storage and onsite/offsite waste generators consisting of compactible and non-compactible solids, contaminated soils, and metals. This volume, Volume 1 provides a narrative of the project background, objective and justification. A description of the WRAP 2A mission, operations and project scope is also included. Significant project requirements such as security, health, safety, decontamination and decomissioning, maintenance, data processing, and quality are outlined. Environmental compliance issues and regulatory permits are identified, and a preliminary safety evaluation is provided.

  18. Critical Protection Item classification for a waste processing facility at Savannah River Site

    SciTech Connect

    Ades, M.J.; Garrett, R.J.

    1993-10-01

    This paper describes the methodology for Critical Protection Item (CPI) classification and its application to the Structures, Systems and Components (SSC) of a waste processing facility at the Savannah River Site (SRS). The WSRC methodology for CPI classification includes the evaluation of the radiological and non-radiological consequences resulting from postulated accidents at the waste processing facility and comparison of these consequences with allowable limits. The types of accidents considered include explosions and fire in the facility and postulated accidents due to natural phenomena, including earthquakes, tornadoes, and high velocity straight winds. The radiological analysis results indicate that CPIs are not required at the waste processing facility to mitigate the consequences of radiological release. The non-radiological analysis, however, shows that the Waste Storage Tank (WST) and the dike spill containment structures around the formic acid tanks in the cold chemical feed area and waste treatment area of the facility should be identified as CPIs. Accident mitigation options are provided and discussed.

  19. Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

    SciTech Connect

    Coles, Garill A.; Hockert, John; Gitau, Ernest TN; Zentner, Michael D.

    2013-01-26

    FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

  20. Trial Application of the Facility Safeguardability Assessment Process to the NuScale SMR Design

    SciTech Connect

    Coles, Garill A.; Gitau, Ernest TN; Hockert, John; Zentner, Michael D.

    2012-11-09

    FSA is a screening process intended to focus a facility designer’s attention on the aspects of their facility or process design that would most benefit from application of SBD principles and practices. The process is meant to identify the most relevant guidance within the SBD tools for enhancing the safeguardability of the design. In fiscal year (FY) 2012, NNSA sponsored PNNL to evaluate the practical application of FSA by applying it to the NuScale small modular nuclear power plant. This report documents the application of the FSA process, presenting conclusions regarding its efficiency and robustness. It describes the NuScale safeguards design concept and presents functional "infrastructure" guidelines that were developed using the FSA process.

  1. A New Concept: Use of Negotiations in the Hazardous Waste Facility Permitting Process in New Mexico

    SciTech Connect

    Johnson, G.J.; Rose, W.M.; Domenici, P.V.; Hollingsworth, L.

    2007-07-01

    This paper describes a unique negotiation process leading to authorization of the U.S. Department of Energy (DOE) to manage and dispose remote-handled (RH) transuranic (TRU) mixed wastes at the Waste Isolation Pilot Plant (WIPP). The negotiation process involved multiple entities and individuals brought together under authority of the New Mexico Environment Department (NMED) to discuss and resolve technical and facility operational issues flowing from an NMED-issued hazardous waste facility Draft Permit. The novel negotiation process resulted in numerous substantive changes to the Draft Permit, which were ultimately memorialised in a 'Draft Permit as Changed'. This paper discusses various aspects of the negotiation process, including events leading to the negotiations, regulatory basis for the negotiations, negotiation participants, and benefits of the process. (authors)

  2. 40 CFR 372.20 - Process for modifying covered chemicals and facilities.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... chemicals and facilities. 372.20 Section 372.20 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SUPERFUND, EMERGENCY PLANNING, AND COMMUNITY RIGHT-TO-KNOW PROGRAMS TOXIC CHEMICAL RELEASE REPORTING: COMMUNITY RIGHT-TO-KNOW Reporting Requirements § 372.20 Process for modifying covered...

  3. Spatio-temporal distribution of stored-product inects around food processing and storage facilities

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Grain storage and processing facilities consist of a landscape of indoor and outdoor habitats that can potentially support stored-product insect pests, and understanding patterns of species diversity and spatial distribution in the landscape surrounding structures can provide insight into how the ou...

  4. Risk analysis and decision processes: The siting of liquefied gas facilities in four countries

    SciTech Connect

    Kunreuther, H.C.; Linnerooth, J.

    1983-01-01

    This book investigates the decision processes for siting liquified energy gas facilities in West Germany, The Netherlands, the United Kingdom, and the United States. It considers the role of risk analysis in such decisions. The problems with cultural and political structure in these cases are included.

  5. Project management plan, Waste Receiving and Processing Facility, Module 1, Project W-026

    SciTech Connect

    Starkey, J.G.

    1993-05-01

    The Hanford Waste Receiving and Processing Facility Module 1 Project (WRAP 1) has been established to support the retrieval and final disposal of approximately 400K grams of plutonium and quantities of hazardous components currently stored in drums at the Hanford Site.

  6. A SURVEY OF COMMON PRACTICES IN SHELL EGG PROCESSING FACILITIES AND THEIR EFFECTS ON WATER USE

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Shell egg processing facilities in the US were surveyed for common production practices and water use. Results were compiled and analyzed for frequency and significance via Chi-square. Of the respondents, 62.5% (P < 0.001) utilized wells as their primary source of water. Only 22% (P < 0.01) of th...

  7. Enterobacteriaceae and related organisms recovered from biofilms in a commercial shell egg processing facility.

    Technology Transfer Automated Retrieval System (TEKTRAN)

    During six visits, biofilms from egg contact and non-contact surfaces in a commercial shell egg processing facility were sampled. Thirty-five different sample sites were selected: Pre-wash and wash tanks (lids, screens, tank interiors, nozzle guards), post-wash spindles, blower filters, belts (far...

  8. CRITICAL ISSUES IN THE DEVELOPMENT AND INTERPRETATION OF PEST MONITORING PROGRAMS FOR FOOD PROCESSING FACILITIES

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Pest management in commercial food processing facilities such as flour mills continues to rely heavily on methyl bromide fumigations. The pending loss of this fumigant has triggered a great deal of interest in developing alternative strategies, but the lack of effective monitoring programs and data...

  9. COMPARISON OF METHODS FOR SAMPLING BACTERIA AT SOLID WASTE PROCESSING FACILITIES

    EPA Science Inventory

    The report is an assessment of the field sampling methodologies used to measure concentrations of airborne bacteria and viruses in and around waste handling and processing facilities. The sampling methods are discussed as well as the problems encountered and subsequent changes ma...

  10. Skylab experiment performance evaluation manual. Appendix E: Experiment M512 Materials processing facility (MSFC)

    NASA Technical Reports Server (NTRS)

    Thomas, O. H., Jr.

    1973-01-01

    Analyses for Experiment M512, Materials Processing Facility (MSFC), to be used for evaluating the performance of the Skylab corollary experiments under preflight, inflight, and post-flight conditions are presented. Experiment contingency plan workaround procedure and malfunction analyses are presented in order to assist in making the experiment operationally successful.

  11. 40 CFR 80.513 - What provisions apply to transmix processing facilities?

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false What provisions apply to transmix processing facilities? 80.513 Section 80.513 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Motor Vehicle Diesel Fuel; Nonroad, Locomotive, and Marine Diesel Fuel;...

  12. Measurements of methane emissions from natural gas gathering facilities and processing plants: measurement methods

    NASA Astrophysics Data System (ADS)

    Roscioli, J. R.; Yacovitch, T. I.; Floerchinger, C.; Mitchell, A. L.; Tkacik, D. S.; Subramanian, R.; Martinez, D. M.; Vaughn, T. L.; Williams, L.; Zimmerle, D.; Robinson, A. L.; Herndon, S. C.; Marchese, A. J.

    2014-12-01

    Increased natural gas production in recent years has spurred intense interest in methane (CH4) emissions associated with its production, gathering, processing, transmission and distribution. Gathering and processing facilities (G&P facilities) are unique in that the wide range of gas sources (shale, coal-bed, tight gas, conventional, etc.) results in a wide range of gas compositions, which in turn requires an array of technologies to prepare the gas for pipeline transmission and distribution. We present an overview and detailed description of the measurement method and analysis approach used during a 20-week field campaign studying CH4 emissions from the natural gas G&P facilities between October 2013 and April 2014. Dual tracer flux measurements and onsite observations were used to address the magnitude and origins of CH4 emissions from these facilities. The use of a second tracer as an internal standard revealed plume-specific uncertainties in the measured emission rates of 20-47%, depending upon plume classification. Combining downwind methane, ethane (C2H6), carbon monoxide (CO), carbon dioxide (CO2), and tracer gas measurements with onsite tracer gas release allows for quantification of facility emissions, and in some cases a more detailed picture of source locations.

  13. Measurements of methane emissions from natural gas gathering facilities and processing plants: measurement methods

    NASA Astrophysics Data System (ADS)

    Roscioli, J. R.; Yacovitch, T. I.; Floerchinger, C.; Mitchell, A. L.; Tkacik, D. S.; Subramanian, R.; Martinez, D. M.; Vaughn, T. L.; Williams, L.; Zimmerle, D.; Robinson, A. L.; Herndon, S. C.; Marchese, A. J.

    2015-05-01

    Increased natural gas production in recent years has spurred intense interest in methane (CH4) emissions associated with its production, gathering, processing, transmission, and distribution. Gathering and processing facilities (G&P facilities) are unique in that the wide range of gas sources (shale, coal-bed, tight gas, conventional, etc.) results in a wide range of gas compositions, which in turn requires an array of technologies to prepare the gas for pipeline transmission and distribution. We present an overview and detailed description of the measurement method and analysis approach used during a 20-week field campaign studying CH4 emissions from the natural gas G&P facilities between October 2013 and April 2014. Dual-tracer flux measurements and on-site observations were used to address the magnitude and origins of CH4 emissions from these facilities. The use of a second tracer as an internal standard revealed plume-specific uncertainties in the measured emission rates of 20-47%, depending upon plume classification. Combining downwind methane, ethane (C2H6), carbon monoxide (CO), carbon dioxide (CO2), and tracer gas measurements with on-site tracer gas release allows for quantification of facility emissions and in some cases a more detailed picture of source locations.

  14. Accident Management & Risk-Based Compliance With 40 CFR 68 for Chemical Process Facilities

    SciTech Connect

    O`Kula, K.R.; Taylor, R.P. Jr.; Ashbaugh, S.G.

    1995-08-23

    A risk-based logic model is suggested as an appropriate basis for better predicting accident progression and ensuing source terms to the environment from process upset conditions in complex chemical process facilities. Under emergency conditions, decision-makers may use the Accident Progression Event Tree approach to identify the best countermeasure for minimizing deleterious consequences to receptor groups before the atmospheric release has initiated. It is concluded that the chemical process industry may use this methodology as a supplemental information provider to better comply with the Environmental Protection Agency`s proposed 40 CFR 68 Risk Management Program rule. An illustration using a benzene-nitric acid potential interaction demonstrates the value of the logic process. The identification of worst-case releases and planning for emergency response are improved through these methods, at minimum. It also provides a systematic basis for prioritizing facility modifications to correct vulnerabilities.

  15. Evaluation of mercury in liquid waste processing facilities - Phase I report

    SciTech Connect

    Jain, V.; Occhipinti, J. E.; Shah, H.; Wilmarth, W. R.; Edwards, R. E.

    2015-07-01

    This report provides a summary of Phase I activities conducted to support an Integrated Evaluation of Mercury in Liquid Waste System (LWS) Processing Facilities. Phase I activities included a review and assessment of the liquid waste inventory and chemical processing behavior of mercury using a system by system review methodology approach. Gaps in understanding mercury behavior as well as action items from the structured reviews are being tracked. 64% of the gaps and actions have been resolved.

  16. Evaluation of Mercury in Liquid Waste Processing Facilities - Phase I Report

    SciTech Connect

    Jain, V.; Occhipinti, J.; Shah, H.; Wilmarth, B.; Edwards, R.

    2015-07-01

    This report provides a summary of Phase I activities conducted to support an Integrated Evaluation of Mercury in Liquid Waste System (LWS) Processing Facilities. Phase I activities included a review and assessment of the liquid waste inventory and chemical processing behavior of mercury using a system by system review methodology approach. Gaps in understanding mercury behavior as well as action items from the structured reviews are being tracked. 64% of the gaps and actions have been resolved.

  17. Checkout and start-up of the integrated DWPF (Defense Waste Processing Facility) melter system

    SciTech Connect

    Smith, M.E.; Hutson, N.D.; Miller, D.H.; Morrison, J.; Shah, H.; Shuford, J.A.; Glascock, J.; Wurzinger, F.H.; Zamecnik, J.R.

    1989-11-11

    The Integrated DWPF Melter System (IDMS) is a one-ninth-scale demonstration of the Defense Waste Processing Facility (DWPF) feed preparation, melter, and off-gas systems. The IDMS will be the first engineering-scale melter system at SRL to process mercury and flowsheet levels of halides and sulfates. This report includes a summary of the IDMS program objectives, system and equipment descriptions, and detailed discussions of the system checkout and start-up. 10 refs., 44 figs., 20 tabs.

  18. Trace component analysis of process hydrogen streams at the Wilsonville Advanced Coal Liquefaction Facility

    SciTech Connect

    Bronfenbrenner, J.C.

    1983-09-01

    This report summarizes subcontracted work done by the Radian Corporation to analyze trace components in process hydrogen streams at the Advanced Coal Liquefaction Facility in Wilsonville, Alabama. The data will be used to help define whether the gas streams to be treated in the hydrogen processing unit in the SRC-I Demonstration Plant will require further treatment to remove trace contaminants that could be explosive under certain conditions. 2 references.

  19. Waste Receiving and Processing Facility Module 1 Data Management System Software Requirements Specification

    SciTech Connect

    Brann, E.C. II

    1994-09-09

    This document provides the software requirements for Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-026). The DMS will collect, store and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal.

  20. Waste Receiving and Processing Facility Module 1 Data Management System software requirements specification

    SciTech Connect

    Rosnick, C.K.

    1996-04-19

    This document provides the software requirements for Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS). The DMS is one of the plant computer systems for the new WRAP 1 facility (Project W-0126). The DMS will collect, store and report data required to certify the low level waste (LLW) and transuranic (TRU) waste items processed at WRAP 1 as acceptable for shipment, storage, or disposal.

  1. Safeguards design strategies: designing and constructing new uranium and plutonium processing facilities in the United States

    SciTech Connect

    Scherer, Carolynn P; Long, Jon D

    2010-09-28

    In the United States, the Department of Energy (DOE) is transforming its outdated and oversized complex of aging nuclear material facilities into a smaller, safer, and more secure National Security Enterprise (NSE). Environmental concerns, worker health and safety risks, material security, reducing the role of nuclear weapons in our national security strategy while maintaining the capability for an effective nuclear deterrence by the United States, are influencing this transformation. As part of the nation's Uranium Center of Excellence (UCE), the Uranium Processing Facility (UPF) at the Y-12 National Security Complex in Oak Ridge, Tennessee, will advance the U.S.'s capability to meet all concerns when processing uranium and is located adjacent to the Highly Enriched Uranium Materials Facility (HEUMF), designed for consolidated storage of enriched uranium. The HEUMF became operational in March 2010, and the UPF is currently entering its final design phase. The designs of both facilities are for meeting anticipated security challenges for the 21st century. For plutonium research, development, and manufacturing, the Chemistry and Metallurgy Research Replacement (CMRR) building at the Los Alamos National Laboratory (LANL) in Los Alamos, New Mexico is now under construction. The first phase of the CMRR Project is the design and construction of a Radiological Laboratory/Utility/Office Building. The second phase consists of the design and construction of the Nuclear Facility (NF). The National Nuclear Security Administration (NNSA) selected these two sites as part of the national plan to consolidate nuclear materials, provide for nuclear deterrence, and nonproliferation mission requirements. This work examines these two projects independent approaches to design requirements, and objectives for safeguards, security, and safety (3S) systems as well as the subsequent construction of these modern processing facilities. Emphasis is on the use of Safeguards-by-Design (SBD), incorporating Systems Engineering (SE) principles for these two projects.

  2. SEISMIC DESIGN REQUIREMENTS SELECTION METHODOLOGY FOR THE SLUDGE TREATMENT & M-91 SOLID WASTE PROCESSING FACILITIES PROJECTS

    SciTech Connect

    RYAN GW

    2008-04-25

    In complying with direction from the U.S. Department of Energy (DOE), Richland Operations Office (RL) (07-KBC-0055, 'Direction Associated with Implementation of DOE-STD-1189 for the Sludge Treatment Project,' and 08-SED-0063, 'RL Action on the Safety Design Strategy (SDS) for Obtaining Additional Solid Waste Processing Capabilities (M-91 Project) and Use of Draft DOE-STD-I 189-YR'), it has been determined that the seismic design requirements currently in the Project Hanford Management Contract (PHMC) will be modified by DOE-STD-1189, Integration of Safety into the Design Process (March 2007 draft), for these two key PHMC projects. Seismic design requirements for other PHMC facilities and projects will remain unchanged. Considering the current early Critical Decision (CD) phases of both the Sludge Treatment Project (STP) and the Solid Waste Processing Facilities (M-91) Project and a strong intent to avoid potentially costly re-work of both engineering and nuclear safety analyses, this document describes how Fluor Hanford, Inc. (FH) will maintain compliance with the PHMC by considering both the current seismic standards referenced by DOE 0 420.1 B, Facility Safety, and draft DOE-STD-1189 (i.e., ASCE/SEI 43-05, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, and ANSI!ANS 2.26-2004, Categorization of Nuclear Facility Structures, Systems and Components for Seismic Design, as modified by draft DOE-STD-1189) to choose the criteria that will result in the most conservative seismic design categorization and engineering design. Following the process described in this document will result in a conservative seismic design categorization and design products. This approach is expected to resolve discrepancies between the existing and new requirements and reduce the risk that project designs and analyses will require revision when the draft DOE-STD-1189 is finalized.

  3. Metals Processing Laboratory Users (MPLUS) Facility Annual Report FY 2002 (October 1, 2001-September 30, 2002)

    SciTech Connect

    Angelini, P

    2004-04-27

    The Metals Processing Laboratory Users Facility (MPLUS) is a Department of Energy (DOE), Energy Efficiency and Renewable Energy, Industrial Technologies Program, user facility designated to assist researchers in key industries, universities, and federal laboratories in improving energy efficiency, improving environmental aspects, and increasing competitiveness. The goal of MPLUS is to provide access to the specialized technical expertise and equipment needed to solve metals processing issues that limit the development and implementation of emerging metals processing technologies. The scope of work can also extend to other types of materials. MPLUS has four primary user centers: (1) Processing--casting, powder metallurgy, deformation processing (including extrusion, forging, rolling), melting, thermomechanical processing, and high-density infrared processing; (2) Joining--welding, monitoring and control, solidification, brazing, and bonding; (3) Characterization--corrosion, mechanical properties, fracture mechanics, microstructure, nondestructive examination, computer-controlled dilatometry, and emissivity; and (4) Materials/Process Modeling--mathematical design and analyses, high-performance computing, process modeling, solidification/deformation, microstructure evolution, thermodynamic and kinetic, and materials databases A fully integrated approach provides researchers with unique opportunities to address technologically related issues to solve metals processing problems and probe new technologies. Access is also available to 16 additional Oak Ridge National Laboratory (ORNL) user facilities ranging from state-of-the-art materials characterization capabilities, and high-performance computing to manufacturing technologies. MPLUS can be accessed through a standardized user-submitted proposal and a user agreement. Nonproprietary (open) or proprietary proposals can be submitted. For open research and development, access to capabilities is provided free of charge, while for proprietary efforts, the user pays the entire project costs based on DOE guidelines for ORNL costs.

  4. Metals Processing Laboratory Users (MPLUS) Facility Annual Report: October 1, 2000 through September 30, 2001

    SciTech Connect

    Angelini, P

    2004-04-27

    The Metals Processing Laboratory Users Facility (MPLUS) is a Department of Energy (DOE), Energy Efficiency and Renewable Energy, Industrial Technologies Program user facility designated to assist researchers in key industries, universities, and federal laboratories in improving energy efficiency, improving environmental aspects, and increasing competitiveness. The goal of MPLUS is to provide access to the specialized technical expertise and equipment needed to solve metals processing issues that limit the development and implementation of emerging metals processing technologies. The scope of work can also extend to other types of materials. MPLUS has four primary User Centers including: (1) Processing--casting, powder metallurgy, deformation processing including (extrusion, forging, rolling), melting, thermomechanical processing, high density infrared processing; (2) Joining--welding, monitoring and control, solidification, brazing, bonding; (3) Characterization--corrosion, mechanical properties, fracture mechanics, microstructure, nondestructive examination, computer-controlled dilatometry, and emissivity; (4) Materials/Process Modeling--mathematical design and analyses, high performance computing, process modeling, solidification/deformation, microstructure evolution, thermodynamic and kinetic, and materials data bases. A fully integrated approach provides researchers with unique opportunities to address technologically related issues to solve metals processing problems and probe new technologies. Access is also available to 16 additional Oak Ridge National Laboratory (ORNL) user facilities ranging from state of the art materials characterization capabilities, high performance computing, to manufacturing technologies. MPLUS can be accessed through a standardized User-submitted Proposal and a User Agreement. Nonproprietary (open) or proprietary proposals can be submitted. For open research and development, access to capabilities is provides free of charge while for proprietary efforts, the user pays the entire project costs based on DOE guidelines for ORNL costs.

  5. Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility

    SciTech Connect

    TRINER, G.C.

    1999-11-01

    The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge.

  6. Electromagnetic containerless processing requirements and recommended facility concept and capabilities for space lab

    NASA Technical Reports Server (NTRS)

    Frost, R. T.; Bloom, H. L.; Napaluch, L. J.; Stockhoff, E. H.; Wouch, G.

    1974-01-01

    Containerless melting, reaction, and solidification experiments and processes which potentially can lead to new understanding of material science and production of new or improved materials in the weightless space environment are reviewed in terms of planning for spacelab. Most of the experiments and processes discussed are amenable to the employment of electromagnetic position control and electromagnetic induction or electron beam heating and melting. The spectrum of relevant properties of materials, which determine requirements for a space laboratory electromagnetic containerless processing facility are reviewed. Appropriate distributions and associated coil structures are analyzed and compared on the basis of efficiency, for providing the functions of position sensing, control, and induction heating. Several coil systems are found capable of providing these functions. Exchangeable modular coils in appropriate sizes are recommended to achieve the maximum power efficiencies, for a wide range of specimen sizes and resistivities, in order to conserve total facility power.

  7. Human Engineering Operations and Habitability Assessment: A Process for Advanced Life Support Ground Facility Testbeds

    NASA Technical Reports Server (NTRS)

    Connolly, Janis H.; Arch, M.; Elfezouaty, Eileen Schultz; Novak, Jennifer Blume; Bond, Robert L. (Technical Monitor)

    1999-01-01

    Design and Human Engineering (HE) processes strive to ensure that the human-machine interface is designed for optimal performance throughout the system life cycle. Each component can be tested and assessed independently to assure optimal performance, but it is not until full integration that the system and the inherent interactions between the system components can be assessed as a whole. HE processes (which are defining/app lying requirements for human interaction with missions/systems) are included in space flight activities, but also need to be included in ground activities and specifically, ground facility testbeds such as Bio-Plex. A unique aspect of the Bio-Plex Facility is the integral issue of Habitability which includes qualities of the environment that allow humans to work and live. HE is a process by which Habitability and system performance can be assessed.

  8. The environmental impact assessment process for nuclear facilities: An examination of the Indian experience

    SciTech Connect

    Ramana, M.V.; Rao, Divya Badami

    2010-07-15

    India plans to construct numerous nuclear plants and uranium mines across the country, which could have significant environmental, health, and social impacts. The national Environmental Impact Assessment process is supposed to regulate these impacts. This paper examines how effective this process has been, and the extent to which public inputs have been taken into account. In addition to generic problems associated with the EIA process for all kinds of projects in India, there are concerns that are specific to nuclear facilities. One is that some nuclear facilities are exempt from the environmental clearance process. The second is that data regarding radiation baseline levels and future releases, which is the principle environmental concern with respect to nuclear facilities, is controlled entirely by the nuclear establishment. The third is that members of the nuclear establishment take part in almost every level of the environmental clearance procedure. For these reasons and others, the EIA process with regard to nuclear projects in India is of dubious quality. We make a number of recommendations that could address these lacunae, and more generally the imbalance of power between the nuclear establishment on the one hand, and civil society and the regulatory agencies on the other.

  9. Project C-018H, 242-A Evaporator/PUREX Plant Process Condensate Treatment Facility, functional design criteria. Revision 3

    SciTech Connect

    Sullivan, N.

    1995-05-02

    This document provides the Functional Design Criteria (FDC) for Project C-018H, the 242-A Evaporator and Plutonium-Uranium Extraction (PUREX) Plant Condensate Treatment Facility (Also referred to as the 200 Area Effluent Treatment Facility [ETF]). The project will provide the facilities to treat and dispose of the 242-A Evaporator process condensate (PC), the Plutonium-Uranium Extraction (PUREX) Plant process condensate (PDD), and the PUREX Plant ammonia scrubber distillate (ASD).

  10. Assessment of nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility

    SciTech Connect

    Ha, B.C.

    1993-05-10

    A panel of experts in the fields of process engineering, process chemistry, and safety analysis met together on January 26, 1993, and February 19, 1993, to discuss nuclear safety and nuclear criticality potential in the Defense Waste Processing Facility (DWPF) processes. Nuclear safety issues and possibilities of nuclear criticality incidents in the DWPF were examined in depth. The discussion started at the receipt of slurry feeds: The Low Point Pump Pit Precipitate Tank (LPPPPT) and the Low Point Pump Pit Sludge Tank (LPPPST), and went into detail the whole DWPF processes. This report provides discussion of each of the areas and processes of the DWPF in terms of potential nuclear safety issues and nuclear criticality concerns.

  11. Commercial Light Water Reactor -Tritium Extraction Facility Process Waste Assessment (Project S-6091)

    SciTech Connect

    Hsu, R.H.; Delley, A.O.; Alexander, G.J.; Clark, E.A.; Holder, J.S.; Lutz, R.N.; Malstrom, R.A.; Nobles, B.R.; Carson, S.D.; Peterson, P.K.

    1997-11-30

    The Savannah River Site (SRS) has been tasked by the Department of Energy (DOE) to design and construct a Tritium Extraction Facility (TEF) to process irradiated tritium producing burnable absorber rods (TPBARs) from a Commercial Light Water Reactor (CLWR). The plan is for the CLWR-TEF to provide tritium to the SRS Replacement Tritium Facility (RTF) in Building 233-H in support of DOE requirements. The CLWR-TEF is being designed to provide 3 kg of new tritium per year, from TPBARS and other sources of tritium (Ref. 1-4).The CLWR TPBAR concept is being developed by Pacific Northwest National Laboratory (PNNL). The TPBAR assemblies will be irradiated in a Commercial Utility light water nuclear reactor and transported to the SRS for tritium extraction and processing at the CLWR-TEF. A Conceptual Design Report for the CLWR-TEF Project was issued in July 1997 (Ref. 4).The scope of this Process Waste Assessment (PWA) will be limited to CLWR-TEF processing of CLWR irradiated TPBARs. Although the CLWR- TEF will also be designed to extract APT tritium-containing materials, they will be excluded at this time to facilitate timely development of this PWA. As with any process, CLWR-TEF waste stream characteristics will depend on process feedstock and contaminant sources. If irradiated APT tritium-containing materials are to be processed in the CLWR-TEF, this PWA should be revised to reflect the introduction of this contaminant source term.

  12. Phase Equilibrium Studies of Savannah River Tanks and Feed Streams for the Salt Waste Processing Facility

    SciTech Connect

    Weber, C.F.

    2001-06-19

    A chemical equilibrium model is developed and used to evaluate supersaturation of tanks and proposed feed streams to the Salt Waste Processing Facility. The model uses Pitzer's model for activity coefficients and is validated by comparison with a variety of thermodynamic data. The model assesses the supersaturation of 13 tanks at the Savannah River Site (SRS), indicating that small amounts of gibbsite and or aluminosilicate may form. The model is also used to evaluate proposed feed streams to the Salt Waste Processing Facility for 13 years of operation. Results indicate that dilutions using 3-4 M NaOH (about 0.3-0.4 L caustic per kg feed solution) should avoid precipitation and reduce the Na{sup +} ion concentration to 5.6 M.

  13. The Mixed Waste Management Facility: Technology selection and implementation plan, Part 2, Support processes

    SciTech Connect

    Streit, R.D.; Couture, S.A.

    1995-03-01

    The purpose of this document is to establish the foundation for the selection and implementation of technologies to be demonstrated in the Mixed Waste Management Facility, and to select the technologies for initial pilot-scale demonstration. Criteria are defined for judging demonstration technologies, and the framework for future technology selection is established. On the basis of these criteria, an initial suite of technologies was chosen, and the demonstration implementation scheme was developed. Part 1, previously released, addresses the selection of the primary processes. Part II addresses process support systems that are considered ``demonstration technologies.`` Other support technologies, e.g., facility off-gas, receiving and shipping, and water treatment, while part of the integrated demonstration, use best available commercial equipment and are not selected against the demonstration technology criteria.

  14. Feasibility Study for a Plasma Dynamo Facility to Investigate Fundamental Processes in Plasma Astrophysics. Final report

    SciTech Connect

    Forest, Cary B.

    2013-09-19

    The scientific equipment purchased on this grant was used on the Plasma Dynamo Prototype Experiment as part of Professor Forest's feasibility study for determining if it would be worthwhile to propose building a larger plasma physics experiment to investigate various fundamental processes in plasma astrophysics. The initial research on the Plasma Dynamo Prototype Experiment was successful so Professor Forest and Professor Ellen Zweibel at UW-Madison submitted an NSF Major Research Instrumentation proposal titled "ARRA MRI: Development of a Plasma Dynamo Facility for Experimental Investigations of Fundamental Processes in Plasma Astrophysics." They received funding for this project and the Plasma Dynamo Facility also known as the "Madison Plasma Dynamo Experiment" was constructed. This experiment achieved its first plasma in the fall of 2012 and U.S. Dept. of Energy Grant No. DE-SC0008709 "Experimental Studies of Plasma Dynamos," now supports the research.

  15. Critical Protection Item Classification for a waste processing facility at Savannah River Site. Revision 1

    SciTech Connect

    Ades, M.J.; Garrett, R.J.

    1993-12-31

    As a part of its compliance with the Department of Energy requirements for safety of nuclear facilities at the Savannah River Site (SRS), Westinghouse Savannah River Company (WSRC) assigns functional classifications to structures, systems and components (SSCs). As a result, changes in design, operations, maintenance, testing, and inspections of SSCs are performed and backfit requirements are established. This paper describes the Critical Protection Item (CPI) Classification for waste processing facility (WPF) at SRS. The descriptions of the WPF and the processes considered are provided elsewhere. The proposed CPI classification methodology includes the evaluation of the onsite radiological consequences, and the onsite and offsite non-radiological consequences from postulated accidents at the WPF, and comparison of these consequences with allowable frequency-dependent limits. When allowable limits are exceeded, CPIs are identified for accident mitigation.

  16. Payload/GSE/data system interface: Users guide for the VPF (Vertical Processing Facility)

    NASA Technical Reports Server (NTRS)

    1993-01-01

    Payload/GSE/data system interface users guide for the Vertical Processing Facility is presented. The purpose of the document is three fold. First, the simulated Payload and Ground Support Equipment (GSE) Data System Interface, which is also known as the payload T-0 (T-Zero) System is described. This simulated system is located with the Cargo Integration Test Equipment (CITE) in the Vertical Processing Facility (VPF) that is located in the KSC Industrial Area. The actual Payload T-0 System consists of the Orbiter, Mobile Launch Platforms (MLPs), and Launch Complex (LC) 39A and B. This is referred to as the Pad Payload T-0 System (Refer to KSC-DL-116 for Pad Payload T-0 System description). Secondly, information is provided to the payload customer of differences between this simulated system and the actual system. Thirdly, a reference guide of the VPF Payload T-0 System for both KSC and payload customer personnel is provided.

  17. Risk-based process safety assessment and control measures design for offshore process facilities.

    PubMed

    Khan, Faisal I; Sadiq, Rehan; Husain, Tahir

    2002-09-01

    Process operation is the most hazardous activity next to the transportation and drilling operation on an offshore oil and gas (OOG) platform. Past experiences of onshore and offshore oil and gas activities have revealed that a small mis-happening in the process operation might escalate to a catastrophe. This is of especial concern in the OOG platform due to the limited space and compact geometry of the process area, less ventilation, and difficult escape routes. On an OOG platform, each extra control measure, which is implemented, not only occupies space on the platform and increases congestion but also adds extra load to the platform. Eventualities in the OOG platform process operation can be avoided through incorporating the appropriate control measures at the early design stage. In this paper, the authors describe a methodology for risk-based process safety decision making for OOG activities. The methodology is applied to various offshore process units, that is, the compressor, separators, flash drum and driers of an OOG platform. Based on the risk potential, appropriate safety measures are designed for each unit. This paper also illustrates that implementation of the designed safety measures reduces the high Fatal accident rate (FAR) values to an acceptable level. PMID:12141993

  18. Foam testing of an alternative antifoam agent for the processing of radioactive sludge in the Defense Waste Processing Facility

    SciTech Connect

    Koopman, D.C.

    2000-01-26

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site is responsible for immobilizing high level radioactive waste (HLW) as glass-filled steel canisters for permanent storage. In the DWPF facility, the HLW sludge undergoes chemical treatment to prepare it for vitrification in a melter. The generation of stable foams is possible during treatment. The current DWPF antifoam is ineffective in preventing and minimizing the formation of foam. The adverse consequences of excess foam can be severe enough to cause foam to exit the evaporator and collect in the condensate. A foamover will contaminate the relatively clean condensate with HLW solids. It can also potentially lead to the production of an unsuitable melter feed that would not make quality glass. Both of these consequences are costly and time consuming to correct. A new antifoam agent was developed by the Illinois Institute of Technology, IIT, for DWPF in an attempt to minimize or eliminate the frequency of these foamovers. This antifoam agent was demonstrated to be superior to the existing DWPF antifoam agent in laboratory scale experiments. However, the DWPF evaporation heat flux was not achievable in the laboratory scale equipment. A 1/240th-scale pilot facility was built to achieve this heat flux and determine whether the existing or new antifoam agent was superior. The pilot facility was built out of glass to allow observation of the foam formation during processing. The experiments used a non-radioactive simulant slurry similar to HLW. The IIT antifoam agent was found to be much more effective than the DWPF antifoam at the current conditions of maximum foam formation. The IIT antifoam agent was comparable or superior to the present DWPF antifoam under all conditions tested. This report summarizes the results of the antifoam agent comparison testing.

  19. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

    SciTech Connect

    Scott, D.E.; Pechmann, J.H.K.; Knox, J.N.; Estes, R.A.; McGregor, J.H.; Bailey, K.

    1988-12-01

    The Savannah River Ecology Laboratory has completed 10 years of ecological studies related to the construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site. This progress report examines water quality studies on streams peripheral to the DWPF construction site and examines the effectiveness of refuge ponds'' in ameliorating the effects of construction on local amphibians. Individual papers on these topics are indexed separately. 93 refs., 15 figs., 15 tabs. (MHB)

  20. Automation of a cryogenic facility by commercial process-control computer

    SciTech Connect

    Sondericker, J.H.; Campbell, D.; Zantopp, D.

    1983-01-01

    To insure that Brookhaven's superconducting magnets are reliable and their field quality meets accelerator requirements, each magnet is pre-tested at operating conditions after construction. MAGCOOL, the production magnet test facility, was designed to perform these tests, having the capacity to test ten magnets per five day week. This paper describes the control aspects of MAGCOOL and the advantages afforded the designers by the implementation of a commercial process control computer system.

  1. Design and verification of shielding for the advanced spent fuel conditioning process facility.

    PubMed

    Cho, I J; Kook, D H; Kwon, K C; Lee, E P; Choung, W M; You, G S

    2008-05-01

    An Advanced spent fuel Conditioning Process Facility (ACPF) has recently been constructed by a modification of previously unused cells. ACPF is a hot cell with two rooms located in the basement of the Irradiated Materials Experiment Facility (IMEF) at the Korea Atomic Energy Research Institute. This is for demonstrating the advanced spent fuel conditioning process being proposed in Korea, which is an electrolytic reduction process of spent oxide fuels into a metallic form. The ACPF was designed with a more than 90 cm thick high density concrete shield wall to handle 1.38 PBq (37,430 Ci) of radioactive materials with dose rates lower than 10 muSv h in the operational areas (7,000 zone) and 150 muSv h in the service areas (8,000 zone). In Monte Carlo calculations with a design basis source inventory, the results for the bounding wall showed a maximum of 3 muSv h dose rate at an exterior surface of the ACPF for gamma radiation and 0.76 muSv h for neutrons. All the bounding structures of the ACPF were investigated to check on the shielding performance of the facility to ensure the radiation safety of the facility. A test was performed with a 2.96 TBq (80 Ci) 60Co source unit and the test results were compared with the calculation results. A few failure points were discovered and carefully fixed to meet the design criteria. After fixing the problems, the failure points were rechecked and the safety of the shielding structures was confirmed. In conclusion, it was confirmed that all the investigated parts of the ACPF passed the shielding safety limits by using this program and the ACPF is ready to fulfill its tasks for the advanced spent fuel conditioning process. PMID:18403959

  2. Compressed Air System Renovation Project Improves Production at a Food Processing Facility (Mead-Johnson Nutritionals, Bristol-Myers Squib)

    SciTech Connect

    2001-06-01

    This case study is one in a series on industrial firms who are implementing energy efficient technologies and system improvements into their manufacturing processes. This case study documents the activities, savings, and lessons learned on the food processing facility project.

  3. A process for establishing a financial assurance plan for LLW disposal facilities

    SciTech Connect

    Smith, P.

    1993-04-01

    This document describes a process by which an effective financial assurance program can be developed for new low-level radioactive waste (LLW) disposal facilities. The report identifies examples of activities that might cause financial losses and the types of losses they might create, discusses mechanisms that could be used to quantify and ensure against the various types of potential losses identified and describes a decision process to formulate a financial assurance program that takes into account the characteristics of both the potential losses and available mechanisms. A sample application of the concepts described in the report is provided.

  4. Startup of Savannah River`s Defense Waste Processing Facility to produce radioactive glass

    SciTech Connect

    Bennett, W.M.

    1997-08-06

    The Savannah River Site (SRS) began production of radioactive glass in the Defense Waste Process Facility (DWPF) in 1996 following an extensive test program discussed earlier. Currently DWPF is operating in a `sludge only` mode to produce radioactive glass consisting of washed high-level waste sludge and glass frit. Future operations will produce radioactive glass consisting of washed high-level waste sludge, precipitated cesium, and glass frit. This paper provides an update of processing activities to date, operational problems encountered since entering radioactive operations, and the programs underway to solve them.

  5. A knowledge acquisition process to analyse operational problems in solid waste management facilities.

    PubMed

    Dokas, Ioannis M; Panagiotakopoulos, Demetrios C

    2006-08-01

    The available expertise on managing and operating solid waste management (SWM) facilities varies among countries and among types of facilities. Few experts are willing to record their experience, while few researchers systematically investigate the chains of events that could trigger operational failures in a facility; expertise acquisition and dissemination, in SWM, is neither popular nor easy, despite the great need for it. This paper presents a knowledge acquisition process aimed at capturing, codifying and expanding reliable expertise and propagating it to non-experts. The knowledge engineer (KE), the person performing the acquisition, must identify the events (or causes) that could trigger a failure, determine whether a specific event could trigger more than one failure, and establish how various events are related among themselves and how they are linked to specific operational problems. The proposed process, which utilizes logic diagrams (fault trees) widely used in system safety and reliability analyses, was used for the analysis of 24 common landfill operational problems. The acquired knowledge led to the development of a web-based expert system (Landfill Operation Management Advisor, http://loma.civil.duth.gr), which estimates the occurrence possibility of operational problems, provides advice and suggests solutions. PMID:16941992

  6. DOE final report, phase one startup, Waste Receiving and Processing Facility (WRAP)

    SciTech Connect

    Jasen, W.G.

    1998-01-07

    This document is to validate that the WRAP facility is physically ready to start up phase 1, and that the managers and operators are prepared to safely manage and operate the facility when all pre-start findings have been satisfactorily corrected. The DOE Readiness Assessment (RA) team spent a week on-site at Waste Receiving and Processing Module 1 (WRAP-1) to validate the readiness for phase 1 start up of facility. The Contractor and DOE staff were exceptionally cooperative and contributed significantly to the overall success of the RA. The procedures and Conduct of Operations areas had significant discrepancies, many of which should have been found by the contractor review team. In addition the findings of the contractor review team should have led the WRAP-1 management team to correcting the root causes of the findings prior to the DOE RA team review. The findings and observations include many issues that the team believes should have been found by the contractor review and corrective actions taken. A significantly improved Operational Readiness Review (ORR) process and corrective actions of root causes must be fully implemented by the contractor prior to the performance of the contractor ORR for phase 2 operations. The pre-start findings as a result of this independent DOE Readiness Assessment are presented.

  7. Dynamics of Listeria monocytogenes colonisation in a newly-opened meat processing facility.

    PubMed

    Bolocan, Andrei Sorin; Nicolau, Anca Ioana; Alvarez-Ordóñez, Avelino; Borda, Daniela; Oniciuc, Elena Alexandra; Stessl, Beatrix; Gurgu, Leontina; Wagner, Martin; Jordan, Kieran

    2016-03-01

    This study determined the colonisation scenario of Listeria monocytogenes in a newly-opened ready-to-eat meat processing facility using a combination of classical microbiology and molecular biology techniques. Samples (n=183), including food contact surfaces, non-food contact surfaces, raw materials and food samples, collected on four sampling occasions, were analysed for L. monocytogenes by the ISO 11290:1996 standard method and by real-time PCR applied to the second enrichment broth from the ISO method. No L. monocytogenes were detected on the first sampling occasion, but by the second sampling occasion a persistent clone had colonised the facility. Analysis of the second enrichment of the ISO method by real-time PCR was more sensitive for the detection of L. monocytogenes than the ISO method alone. In order to reduce the risk of cross contamination and the public health risk, awareness and proactive measures are required to control L. monocytogenes from the first days of production in a newly opened meat processing facility. PMID:26599913

  8. Cancer incidence in municipalities near two former nuclear materials processing facilities in Pennsylvania.

    PubMed

    Boice, John D; Bigbee, William L; Mumma, Michael T; Blot, William J

    2003-12-01

    Because nuclear facilities can release radionuclides into the surrounding environment accidentally or during normal operations, there has been public concern over the possibility of adverse health effects. Two former nuclear materials processing facilities in Armstrong County Pennsylvania have been the focus of such public concern for over 20 y. The Apollo and Parks facilities processed uranium and plutonium fuels for use in nuclear applications. To evaluate the possibility of increased cancer rates in the communities near the Apollo-Parks nuclear processing materials plants, cancer incidence rates were assessed for the years 1993-1997, or nearly 40 y after the plants had begun operation in 1957 and 1960, respectively. The rates of cancer were evaluated among the approximately 17,000 persons living in 1 of 8 municipalities encompassing or near these nuclear sites. Numbers of cancers and mailing addresses (n = 935) were obtained from the Pennsylvania Department of Health. Because mailing addresses in small rural areas do not always reflect actual residences within a municipality, each of 935 addresses was validated (and corrections made when indicated) by contacting area postmasters and using Census Bureau geocoding information, street maps, and aerial photographs. Standardized Incidence Ratios (SIRs) were computed as the ratio of observed numbers of cancers in the study area compared to the expected number derived from general population rates of Pennsylvania. Forty percent of the mailing addresses were found not to be within the boundaries of the study municipalities. After excluding these persons who did not reside in one of the eight municipalities near the Apollo-Parks facilities, 581 cancers remained in contrast to 574.0 expected (SIR 1.01; 95% confidence interval 0.93-1.10). Based upon knowledge of the tissues where uranium or plutonium likely would be deposited after intake, cancers of the lung (SIR 0.88), kidney (SIR 1.05), non-Hodgkin's lymphoma (SIR 1.10), liver (SIR 0.61), and bone (2 observed vs. 1.19 expected) were carefully evaluated, but no significant excesses were noted at these sites. Cancers of the female breast and thyroid and leukemia also were not significantly increased, as expected since these tissues are not sites where uranium or plutonium would concentrate. Overall, no increase in cancer risk could be attributed to living near the two former nuclear materials processing facilities. However, misleading elevations in cancer risks would have been suggested if mailing addresses had not been corrected to exclude addresses that were not within the boundaries of the municipalities for which population data were available. The study had sufficient power to exclude increased cancer risks of 10% or greater. PMID:14626319

  9. Diagnostic control, data acquisition and data processing at MFTF-B (Mirror Fusion Test Facility)

    SciTech Connect

    Preckshot, G.G.

    1986-01-01

    Diagnostic instruments at the Mirror Fusion Test Facility (MFTF-B) are operated by a distributed computer system which provides an integrated control, data acquisition and data processing interface. Instrument control settings, operator inputs and lists of data to be acquired are combined with data acquired by instrument data recorders, to be used downstream by data processing codes; data processing programs are automatically informed of operator control and setpoint actions without operator intervention. The combined diagnostic control and results presentation interface is presented to experimentalist users by a network of high-resolution graphics workstations. Control coordination, data processing and database management are handled by a shared-memory network of 32-bit super minicomputers. Direct instrument control, data acquisition, data packaging and instrument status monitoring are performed by a network of dedicated local control microcomputers.

  10. Integration of distributed plant process computer systems to nuclear power generation facilities

    SciTech Connect

    Bogard, T.; Finlay, K.

    1996-11-01

    Many operating nuclear power generation facilities are replacing their plant process computer. Such replacement projects are driven by equipment obsolescence issues and associated objectives to improve plant operability, increase plant information access, improve man machine interface characteristics, and reduce operation and maintenance costs. This paper describes a few recently completed and on-going replacement projects with emphasis upon the application integrated distributed plant process computer systems. By presenting a few recent projects, the variations of distributed systems design show how various configurations can address needs for flexibility, open architecture, and integration of technological advancements in instrumentation and control technology. Architectural considerations for optimal integration of the plant process computer and plant process instrumentation & control are evident from variations of design features.

  11. Tritium Facilities Modernization and Consolidation Project Process Waste Assessment (Project S-7726)

    SciTech Connect

    Hsu, R.H.; Oji, L.N.

    1997-11-14

    Under the Tritium Facility Modernization {ampersand} Consolidation (TFM{ampersand}C) Project (S-7726) at the Savannah River Site (SS), all tritium processing operations in Building 232-H, with the exception of extraction and obsolete/abandoned systems, will be reestablished in Building 233-H. These operations include hydrogen isotopic separation, loading and unloading of tritium shipping and storage containers, tritium recovery from zeolite beds, and stripping of nitrogen flush gas to remove tritium prior to stack discharge. The scope of the TFM{ampersand}C Project also provides for a new replacement R&D tritium test manifold in 233-H, upgrading of the 233- H Purge Stripper and 233-H/234-H building HVAC, a new 234-H motor control center equipment building and relocating 232-H Materials Test Facility metallurgical laboratories (met labs), flow tester and life storage program environment chambers to 234-H.

  12. Fluids and Combustion Facility Acoustic Emissions Controlled by Aggressive Low-Noise Design Process

    NASA Technical Reports Server (NTRS)

    Cooper, Beth A.; Young, Judith A.

    2004-01-01

    The Fluids and Combustion Facility (FCF) is a dual-rack microgravity research facility that is being developed by Northrop Grumman Information Technology (NGIT) for the International Space Station (ISS) at the NASA Glenn Research Center. As an on-orbit test bed, FCF will host a succession of experiments in fluid and combustion physics. The Fluids Integrated Rack (FIR) and the Combustion Integrated Rack (CIR) must meet ISS acoustic emission requirements (ref. 1), which support speech communication and hearing-loss-prevention goals for ISS crew. To meet these requirements, the NGIT acoustics team implemented an aggressive low-noise design effort that incorporated frequent acoustic emission testing for all internal noise sources, larger-scale systems, and fully integrated racks (ref. 2). Glenn's Acoustical Testing Laboratory (ref. 3) provided acoustical testing services (see the following photograph) as well as specialized acoustical engineering support as part of the low-noise design process (ref. 4).

  13. Conceptual design of a solar cogeneration facility industrial process heat, category A. Executive summary

    NASA Astrophysics Data System (ADS)

    Joy, P.; Brzeczek, M.; Seilestad, H.; Silverman, C.; Yenetchi, G.

    1981-07-01

    The conceptual design of a central receiver solar cogeneration facility at a California oil field is described. The process of selecting the final cogeneration system configuration is described and the various system level and subsystem level tradeoff studies are presented, including the system configuration study, technology options, and system sizing. The facility is described, and the functional aspects, requirements operational characteristics, and performance are discussed. Capital and operating costs, safety, environmental, regulatory issues and potential limiting considerations for the design are included. Each subsystem is described in detail including a discussion of the functional requirements, design, operating characteristics performance estimates and a top level cost estimate. An economic assessment is performed to determine the near-term economic viability of the project and to examine the impact of variations in major economic parameters such as capital and operating and maintenance costs on economic viability. Two measures of economic viability used are levelized energy cost and net present value.

  14. Waste Receiving and Processing (WRAP) Facility Public Address System Review Findings

    SciTech Connect

    HUMPHRYS, K.L.

    1999-11-03

    Public address system operation at the Waste Receiving and Processing (WRAP) facility was reviewed. The review was based on an Operational Readiness Review finding that public address performance was not adequate in parts of the WRAP facility. Several improvements were made to the WRAP Public Address (PA) system to correct the deficiencies noted. Speaker gain and position was optimized. A speech processor was installed to boost intelligibility in high noise areas. Additional speakers were added to improve coverage in the work areas. The results of this evaluation indicate that further PA system enhancements are not warranted. Additional speakers cannot compensate for the high background sound and high reverberation levels found in the work areas. Recommendations to improve PA system intelligibility include minor speaker adjustments, enhanced PA announcement techniques, and the use of sound reduction and abatement techniques where economically feasible.

  15. Review of Catalytic Hydrogen Generation in the Defense Waste Processing Facility (DWPF) Chemical Processing Cell

    SciTech Connect

    Koopman, D. C.

    2004-12-31

    This report was prepared to fulfill the Phase I deliverable for HLW/DWPF/TTR-98-0018, Rev. 2, ''Hydrogen Generation in the DWPF Chemical Processing Cell'', 6/4/2001. The primary objective for the preliminary phase of the hydrogen generation study was to complete a review of past data on hydrogen generation and to prepare a summary of the findings. The understanding was that the focus should be on catalytic hydrogen generation, not on hydrogen generation by radiolysis. The secondary objective was to develop scope for follow-up experimental and analytical work. The majority of this report provides a summary of past hydrogen generation work with radioactive and simulated Savannah River Site (SRS) waste sludges. The report also includes some work done with Hanford waste sludges and simulants. The review extends to idealized systems containing no sludge, such as solutions of sodium formate and formic acid doped with a noble metal catalyst. This includes general information from the literature, as well as the focused study done by the University of Georgia for the SRS. The various studies had a number of points of universal agreement. For example, noble metals, such as Pd, Rh, and Ru, catalyze hydrogen generation from formic acid and formate ions, and more acid leads to more hydrogen generation. There were also some points of disagreement between different sources on a few topics such as the impact of mercury on the noble metal catalysts and the identity of the most active catalyst species. Finally, there were some issues of potential interest to SRS that apparently have not been systematically studied, e.g. the role of nitrite ion in catalyst activation and reactivity. The review includes studies covering the period from about 1924-2002, or from before the discovery of hydrogen generation during simulant sludge processing in 1988 through the Shielded Cells qualification testing for Sludge Batch 2. The review of prior studies is followed by a discussion of proposed experimental work, additional data analysis, and future modeling programs. These proposals have led to recent investigations into the mercury issue and the effect of co-precipitating noble metals which will be documented in two separate reports. SRS hydrogen generation work since 2002 will also be collected and summarized in a future report on the effect of noble metal-sludge matrix interactions on hydrogen generation. Other potential factors for experimental investigation include sludge composition variations related to both the washing process and to the insoluble species with particular attention given to the role of silver and to improving the understanding of the interaction of nitrite ion with the noble metals.

  16. Darlington tritium removal facility and station upgrading plant dynamic process simulation

    SciTech Connect

    Busigin, A.; Williams, G. I. D.; Wong, T. C. W.; Kulczynski, D.; Reid, A.

    2008-07-15

    Ontario Power Generation Nuclear (OPGN) has a 4 x 880 MWe CANDU nuclear station at its Darlington Nuclear Div. located in Bowmanville. The station has been operating a Tritium Removal Facility (TRF) and a D{sub 2}O station Upgrading Plant (SUP) since 1989. Both facilities were designed with a Distributed Control System (DCS) and programmable logic controllers (PLC) for process control. This control system was replaced with a DCS only, in 1998. A dynamic plant simulator was developed for the Darlington TRF (DTRF) and the SUP, as part of the computer control system replacement. The simulator was used to test the new software, required to eliminate the PLCs. The simulator is now used for operator training and testing of process control software changes prior to field installation. Dynamic simulation will be essential for the ITER isotope separation system, where the process is more dynamic than the relatively steady-state DTRF process. This paper describes the development and application of the DTRF and SUP dynamic simulator, its benefits, architecture, and the operational experience with the simulator. (authors)

  17. Modelling of post-fragmentation waste stream processing within UK shredder facilities.

    PubMed

    Coates, Gareth; Rahimifard, Shahin

    2009-01-01

    With the introduction of producer responsibility legislation within the UK (i.e., waste electrical and electronic equipment directive and end-of-life vehicles directive), specific recycling and recovery targets have been imposed to improve the sustainability of end-of-life products. With the introduction of these targets, and the increased investment in post-fragmentation facilities, automated material separation technologies are playing an integral role within the UK's end-of-life waste management strategy. Post-fragmentation facilities utilise a range of purification technologies that target certain material attributes (e.g., density, magnetism, volume) to isolate materials from the shredded waste stream. High ferrous prices have historically meant that UK facilities have been primarily interested in recovering iron and steel, establishing processing routes that are very effective at removing these material types, but as a consequence are extremely rigid and inflexible. With the proliferation of more exotic materials within end-of-life products, combined with more stringent recycling targets, there is therefore a need to optimise the current waste reclamation processes to better realise effort-to-value returns. This paper provides a background as to the current post-fragmentation processing adopted within the UK, and describes the development of a post-fragmentation modelling approach, capable of simulating the value-added processing that a piece of automated separation equipment can have on a fragmented waste stream. These include the modelling of the inefficiencies of the technology, the effects of material entanglement on separation, determination of typical material sizing and an appreciation for compositional value. The implementation of this approach within a software decision-support system is described, before the limitations, calibration and further validation of the approach are discussed. PMID:18472415

  18. Modelling of post-fragmentation waste stream processing within UK shredder facilities

    SciTech Connect

    Coates, Gareth Rahimifard, Shahin

    2009-01-15

    With the introduction of producer responsibility legislation within the UK (i.e., waste electrical and electronic equipment directive and end-of-life vehicles directive), specific recycling and recovery targets have been imposed to improve the sustainability of end-of-life products. With the introduction of these targets, and the increased investment in post-fragmentation facilities, automated material separation technologies are playing an integral role within the UK's end-of-life waste management strategy. Post-fragmentation facilities utilise a range of purification technologies that target certain material attributes (e.g., density, magnetism, volume) to isolate materials from the shredded waste stream. High ferrous prices have historically meant that UK facilities have been primarily interested in recovering iron and steel, establishing processing routes that are very effective at removing these material types, but as a consequence are extremely rigid and inflexible. With the proliferation of more exotic materials within end-of-life products, combined with more stringent recycling targets, there is therefore a need to optimise the current waste reclamation processes to better realise effort-to-value returns. This paper provides a background as to the current post-fragmentation processing adopted within the UK, and describes the development of a post-fragmentation modelling approach, capable of simulating the value-added processing that a piece of automated separation equipment can have on a fragmented waste stream. These include the modelling of the inefficiencies of the technology, the effects of material entanglement on separation, determination of typical material sizing and an appreciation for compositional value. The implementation of this approach within a software decision-support system is described, before the limitations, calibration and further validation of the approach are discussed.

  19. Examination of Listeria monocytogenes in Seafood Processing Facilities and Smoked Salmon in the Republic of Ireland.

    PubMed

    Leong, Dara; Alvarez-Ordóñez, Avelino; Zaouali, Sarah; Jordan, Kieran

    2015-12-01

    Listeria monocytogenes is a foodborne pathogen that causes listeriosis, a relatively rare but life-threatening disease primarily affecting immunocompromised individuals. The aim of this study was to determine the prevalence of L. monocytogenes in the seafood processing industry in the Republic of Ireland. The occurrence of L. monocytogenes was determined by regular sampling of both food samples and processing environment swabs at eight seafood processing facilities over two calendar years. All samples were analyzed by the International Organization for Standardization 11290-1 standard method, and the isolates were characterized by PCR, pulsed-field gel electrophoresis, serotyping, and the occurrence of some genes related to survival under stress (SSI-1, Tn6188, and bcrABC). A prevalence of 2.5% in 508 samples (433 environmental swabs and 75 food samples) was found. From the isolates obtained, eight different pulsed-field gel electrophoresis profiles were identified, two occurring in more than one facility and one occurring in food and the environment. Five of the eight pulsotypes identified contained at least one of the three stress survival-related genes tested. The tolerance of the isolates to benzalkonium chloride, a representative quaternary ammonium compound, was also examined and ranged from 5.5 ± 0.5 to 8.5 ± 0.5 ppm of benzalkonium chloride. To evaluate the ability of smoked salmon to support the growth of L. monocytogenes, including the T4 widespread pulsotype that was isolated, a challenge test was performed on cold-smoked salmon obtained from two separate producers. The results showed clearly that both types of smoked salmon supported the growth of L. monocytogenes. Although occurrence of L. monocytogenes on seafood was low, this study showed that the smoked salmon used in this study can support the growth of L. monocytogenes; therefore, vigilance is required in the processing facilities to reduce the associated risk. PMID:26613913

  20. RECENT PROCESS AND EQUIPMENT IMPROVEMENTS TO INCREASE HIGH LEVEL WASTE THROUGHPUT AT THE DEFENSE WASTE PROCESSING FACILITY

    SciTech Connect

    Odriscoll, R; Allan Barnes, A; Jim Coleman, J; Timothy Glover, T; Robert Hopkins, R; Dan Iverson, D; Jeff Leita, J

    2008-01-15

    The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) began stabilizing high level waste (HLW) in a glass matrix in 1996. Over the past few years, there have been several process and equipment improvements at the DWPF to increase the rate at which the high level waste can be stabilized. These improvements have either directly increased waste processing rates or have desensitized the process to upsets, thereby minimizing downtime and increasing production. Improvements due to optimization of waste throughput with increased HLW loading of the glass resulted in a 6% waste throughput increase based upon operational efficiencies. Improvements in canister production include the pour spout heated bellows liner (5%), glass surge (siphon) protection software (2%), melter feed pump software logic change to prevent spurious interlocks of the feed pump with subsequent dilution of feed stock (2%) and optimization of the steam atomized scrubber (SAS) operation to minimize downtime (3%) for a total increase in canister production of 12%. A number of process recovery efforts have allowed continued operation. These include the off gas system pluggage and restoration, slurry mix evaporator (SME) tank repair and replacement, remote cleaning of melter top head center nozzle, remote melter internal inspection, SAS pump J-Tube recovery, inadvertent pour scenario resolutions, dome heater transformer bus bar cooling water leak repair and new Infra-red camera for determination of glass height in the canister are discussed.

  1. First Results from the CARIBU Facility: Mass Measurements on the r-Process Path

    NASA Astrophysics Data System (ADS)

    Van Schelt, J.; Lascar, D.; Savard, G.; Clark, J. A.; Bertone, P. F.; Caldwell, S.; Chaudhuri, A.; Levand, A. F.; Li, G.; Morgan, G. E.; Orford, R.; Segel, R. E.; Sharma, K. S.; Sternberg, M. G.

    2013-08-01

    The Canadian Penning Trap mass spectrometer has made mass measurements of 33 neutron-rich nuclides provided by the new Californium Rare Isotope Breeder Upgrade facility at Argonne National Laboratory. The studied region includes the Sn132 double shell closure and ranges in Z from In to Cs, with Sn isotopes measured out to A=135, and the typical measurement precision is at the 100 ppb level or better. The region encompasses a possible major waiting point of the astrophysical r process, and the impact of the masses on the r process is shown through a series of simulations. These first-ever simulations with direct mass information on this waiting point show significant increases in waiting time at Sn and Sb in comparison with commonly used mass models, demonstrating the inadequacy of existing models for accurate r-process calculations.

  2. High level waste vitrification at the SRP (Savannah River Plant) (DWPF (Defense Waste Processing Facility) summary)

    SciTech Connect

    Weisman, A F; Knight, J R; McIntosh, D L; Papouchado, L M

    1988-01-01

    The Savannah River Plant has been operating a nuclear fuel cycle since the early 1950's. Fuel and target elements are fabricated and irradiated to produce nuclear materials. After removal from the reactors, the fuel elements are processed to extract the products, and waste is stored. During the thirty years of operation including evaporation, about 30 million gallons of high level radioactive waste has accumulated. The Defense Waste Processing Facility (DWPF) under construction at Savannah River will process this waste into a borosilicate glass for long-term geologic disposal. The construction of the DWPF is about 70% complete; this paper will describe the status of the project, including design demonstrations, with an emphasis on the melter system. 9 figs.

  3. Data acquisition and processing system at the NOVETTE laser-fusion facility

    SciTech Connect

    Auerbach, J.M.; Severyn, J.R.; Kroepfl, D.J.

    1982-01-01

    The computer hardware and software used for acquisition and processing of data from experiments at the NOVETTE laser fusion facility are described. Nearly two hundred sensors are used to measure the performance of millimeter extent targets irradiated by multi-kilojoule laser pulses. Sensor output is recorded on CAMAC based digitizers, CCD arrays, and film. CAMAC instrument outputs are acquired and collected by a network of LSI-11 microprocessors centrally controlled by a VAX 11/780. The user controls the system through menus presented on color video displays equipped with touch panels. The control VAX collects data from all microprocessors and CCD arrays and stores them in a file for transport to a second VAX 11/780 which is used for processing and final analysis. Transfer is done through a high speed fiber-optic link. Relational data bases are used extensively in the processing and archiving of data.

  4. Decisional tool to assess current and future process robustness in an antibody purification facility.

    PubMed

    Stonier, Adam; Simaria, Ana Sofia; Smith, Martin; Farid, Suzanne S

    2012-07-01

    Increases in cell culture titers in existing facilities have prompted efforts to identify strategies that alleviate purification bottlenecks while controlling costs. This article describes the application of a database-driven dynamic simulation tool to identify optimal purification sizing strategies and visualize their robustness to future titer increases. The tool harnessed the benefits of MySQL to capture the process, business, and risk features of multiple purification options and better manage the large datasets required for uncertainty analysis and optimization. The database was linked to a discrete-event simulation engine so as to model the dynamic features of biopharmaceutical manufacture and impact of resource constraints. For a given titer, the tool performed brute force optimization so as to identify optimal purification sizing strategies that minimized the batch material cost while maintaining the schedule. The tool was applied to industrial case studies based on a platform monoclonal antibody purification process in a multisuite clinical scale manufacturing facility. The case studies assessed the robustness of optimal strategies to batch-to-batch titer variability and extended this to assess the long-term fit of the platform process as titers increase from 1 to 10 g/L, given a range of equipment sizes available to enable scale intensification efforts. Novel visualization plots consisting of multiple Pareto frontiers with tie-lines connecting the position of optimal configurations over a given titer range were constructed. These enabled rapid identification of robust purification configurations given titer fluctuations and the facility limit that the purification suites could handle in terms of the maximum titer and hence harvest load. PMID:22641562

  5. Putative Cross-Contamination Routes of Listeria monocytogenes in a Meat Processing Facility in Romania.

    PubMed

    Bolocan, Andrei Sorin; Oniciuc, Elena Alexandra; Alvarez-Ordóñez, Avelino; Wagner, Martin; Rychli, Kathrin; Jordan, Kieran; Nicolau, Anca Ioana

    2015-09-01

    Putative routes of Listeria monocytogenes contamination, based on the workflow of the employees, were studied in a meat processing facility by investigating 226 samples collected from food contact surfaces, non-food contact surfaces, raw materials, and ready-to-eat meat products on four occasions over a 1-year period. In total, 19.7% of non-food contact surfaces, 22.9% of food contact surfaces, 45% of raw materials, and 20% of ready-to-eat meat products were positive for L. monocytogenes (analyzed by the International Organization for Standardization standard method ISO 11290). Pulsed-field gel electrophoresis (PFGE) profiles were determined for a representative subset of these isolates, and 11 distinct pulsotypes were identified, two of which were frequently isolated (T4 and T8) and considered persistent. Strains from the various pulsotypes were screened for the presence of bcrABC and qacH, the genes responsible for tolerance responses to quaternary ammonium compounds. Two strains harbored bcrABC, and these strains had a higher benzalkonium chloride tolerance; however, they were not considered persistent strains. The frequently isolated PFGE pulsotype T8 strains were highly adhesive to abiotic surfaces at 10 and 20°C; however, the pulsotype T6 strain, which was isolated only at the last sampling time, had the highest adhesion ability, and the pulsotype T4 strain (the second most persistent pulsotype) had only modest adhesion. Four putative cross-contamination routes were confirmed by mapping the persistent and other isolates. This information could allow a food safety manager to adjust the work flow to improve the hygienic conditions in a meat processing facility. This study revealed the prevalence and persistence of L. monocytogenes strains in a meat processing facility and established the importance of developing strategies to avoid cross-contamination, recalls, and outbreaks of listeriosis. PMID:26319720

  6. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC... and Approving Abandonment under Section 7 of the Natural Gas Act, as Amended, Concerning Any...

  7. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2013 CFR

    2013-04-01

    ... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC... and Approving Abandonment under Section 7 of the Natural Gas Act, as Amended, Concerning Any...

  8. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2012 CFR

    2012-04-01

    ... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC... and Approving Abandonment under Section 7 of the Natural Gas Act, as Amended, Concerning Any...

  9. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC... and Approving Abandonment under Section 7 of the Natural Gas Act, as Amended, Concerning Any...

  10. 18 CFR 157.21 - Pre-filing procedures and review process for LNG terminal facilities and other natural gas...

    Code of Federal Regulations, 2011 CFR

    2011-04-01

    ... and review process for LNG terminal facilities and other natural gas facilities prior to filing of... COMMISSION, DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF PUBLIC... and Approving Abandonment under Section 7 of the Natural Gas Act, as Amended, Concerning Any...

  11. A shielded storage and processing facility for radioisotope thermoelectric generator heat source production

    SciTech Connect

    Sherrell, D.L.

    1992-06-01

    This report discusses a shielded storage rack which has been installed as part of the Radioisotope Power Systems Facility (RPSF) at the US Department of Energy's (DOE) Hanford Site in Washington State. The RPSF is designed to replace an existing facility at DOE's Mound Site near Dayton, Ohio, where General Purpose Heat Source (GPHS) modules are currently assembled and installed into Radioisotope Thermoelectric Generators (RTG). The overall design goal of the RPSF is to increase annual production throughput, while at the same time reducing annual radiation exposure to personnel. The shield rack design successfully achieved this goal for the Module Reduction and Monitoring Facility (MRMF), which process and stores assembled GPHS modules, prior to their installation into RTGS. The shield rack design is simple and effective, with the result that background radiation levels within Hanford's MRMF room are calculated at just over three percent of those typically experienced during operation of the existing MRMF at Mound, despite the fact that Hanford's calculations assume five times the GPHS inventory of that assumed for Mound.

  12. A shielded storage and processing facility for radioisotope thermoelectric generator heat source production

    SciTech Connect

    Sherrell, D.L.

    1992-06-01

    This report discusses a shielded storage rack which has been installed as part of the Radioisotope Power Systems Facility (RPSF) at the US Department of Energy`s (DOE) Hanford Site in Washington State. The RPSF is designed to replace an existing facility at DOE`s Mound Site near Dayton, Ohio, where General Purpose Heat Source (GPHS) modules are currently assembled and installed into Radioisotope Thermoelectric Generators (RTG). The overall design goal of the RPSF is to increase annual production throughput, while at the same time reducing annual radiation exposure to personnel. The shield rack design successfully achieved this goal for the Module Reduction and Monitoring Facility (MRMF), which process and stores assembled GPHS modules, prior to their installation into RTGS. The shield rack design is simple and effective, with the result that background radiation levels within Hanford`s MRMF room are calculated at just over three percent of those typically experienced during operation of the existing MRMF at Mound, despite the fact that Hanford`s calculations assume five times the GPHS inventory of that assumed for Mound.

  13. Seismic margins assessment of the plutonium processing facility Los Alamos National Laboratory

    SciTech Connect

    Goen, L.K.; Salmon, M.W.

    1995-12-01

    Results of the recently completed seismic evaluation at the Los Alamos National Laboratory site indicate a need to consider seismic loads greater than design basis for many structures systems and components (SSCs). DOE Order 5480.28 requires that existing SSCs be evaluated to determine their ability to withstand the effects of earthquakes when changes in the understanding of this hazard results in greater loads. In preparation for the implementation of DOE Order 5480.28 and to support the update of the facility Safety Analysis Report, a seismic margin assessment of SSCs necessary for a monitored passive safe shutdown of the Plutonium Processing Facility (PF-4) was performed. The seismic margin methodology is given in EPRI NP-6041-SL, ``A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)``. In this methodology, high confidence of low probability of failure (HCLPF) capacities for SSCs are estimated in a deterministic manner. For comparison to the performance goals given in DOE Order 5480.28, the results of the seismic margins assessment were used to estimate the annual probability of failure for the evaluated SSCs. In general, the results show that the capacity for the SSCs comprising PF-4 is high. This is to be expected for a newer facility as PF-4 was designed in the early 1970`s. The methodology and results of this study are presented in this paper.

  14. Design analysis of levitation facility for space processing applications. [Skylab program, space shuttles

    NASA Technical Reports Server (NTRS)

    Frost, R. T.; Kornrumpf, W. P.; Napaluch, L. J.; Harden, J. D., Jr.; Walden, J. P.; Stockhoff, E. H.; Wouch, G.; Walker, L. H.

    1974-01-01

    Containerless processing facilities for the space laboratory and space shuttle are defined. Materials process examples representative of the most severe requirements for the facility in terms of electrical power, radio frequency equipment, and the use of an auxiliary electron beam heater were used to discuss matters having the greatest effect upon the space shuttle pallet payload interfaces and envelopes. Improved weight, volume, and efficiency estimates for the RF generating equipment were derived. Results are particularly significant because of the reduced requirements for heat rejection from electrical equipment, one of the principal envelope problems for shuttle pallet payloads. It is shown that although experiments on containerless melting of high temperature refractory materials make it desirable to consider the highest peak powers which can be made available on the pallet, total energy requirements are kept relatively low by the very fast processing times typical of containerless experiments and allows consideration of heat rejection capabilities lower than peak power demand if energy storage in system heat capacitances is considered. Batteries are considered to avoid a requirement for fuel cells capable of furnishing this brief peak power demand.

  15. IMPACTS OF ANTIFOAM ADDITIONS AND ARGON BUBBLING ON DEFENSE WASTE PROCESSING FACILITY REDUCTION/OXIDATION

    SciTech Connect

    Jantzen, C.; Johnson, F.

    2012-06-05

    During melting of HLW glass, the REDOX of the melt pool cannot be measured. Therefore, the Fe{sup +2}/{Sigma}Fe ratio in the glass poured from the melter must be related to melter feed organic and oxidant concentrations to ensure production of a high quality glass without impacting production rate (e.g., foaming) or melter life (e.g., metal formation and accumulation). A production facility such as the Defense Waste Processing Facility (DWPF) cannot wait until the melt or waste glass has been made to assess its acceptability, since by then no further changes to the glass composition and acceptability are possible. therefore, the acceptability decision is made on the upstream process, rather than on the downstream melt or glass product. That is, it is based on 'feed foward' statistical process control (SPC) rather than statistical quality control (SQC). In SPC, the feed composition to the melter is controlled prior to vitrification. Use of the DWPF REDOX model has controlled the balanjce of feed reductants and oxidants in the Sludge Receipt and Adjustment Tank (SRAT). Once the alkali/alkaline earth salts (both reduced and oxidized) are formed during reflux in the SRAT, the REDOX can only change if (1) additional reductants or oxidants are added to the SRAT, the Slurry Mix Evaporator (SME), or the Melter Feed Tank (MFT) or (2) if the melt pool is bubble dwith an oxidizing gas or sparging gas that imposes a different REDOX target than the chemical balance set during reflux in the SRAT.

  16. 200 Area effluent treatment facility process control plan 98-02

    SciTech Connect

    Le, E.Q.

    1998-01-30

    This Process Control Plan (PCP) provides a description of the background information, key objectives, and operating criteria defining Effluent Treatment Facility (ETF) Campaign 98-02 as required per HNF-IP-0931 Section 37, Process Control Plans. Campaign 98-62 is expected to process approximately 18 millions gallons of groundwater with an assumption that the UP-1 groundwater pump will be shut down on June 30, 1998. This campaign will resume the UP-1 groundwater treatment operation from Campaign 97-01. The Campaign 97-01 was suspended in November 1997 to allow RCRA waste in LERF Basin 42 to be treated to meet the Land Disposal Restriction Clean Out requirements. The decision to utilize ETF as part of the selected interim remedial action of the 200-UP-1 Operable Unit is documented by the Declaration of the Record of Decision, (Ecology, EPA and DOE 1997). The treatment method was chosen in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), the Hanford Federal Facility Agreement and Consent Order (known as the Tri-Party Agreement or TPA), and to the extent practicable, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP).

  17. Carbon nanotubes/magnetite hybrids prepared by a facile synthesis process and their magnetic properties

    NASA Astrophysics Data System (ADS)

    Zhang, Li; Ni, Qing-Qing; Natsuki, Toshiaki; Fu, Yaqin

    2009-07-01

    In this paper, a facile synthesis process is proposed to prepare multiwalled carbon nanotubes/magnetite (MWCNTs/Fe 3O 4) hybrids. The process involves two steps: (1) water-soluble CNTs are synthesized by one-pot modification using potassium persulfate (KPS) as oxidant. (2) Fe 3O 4 is assembled along the treated CNTs by employing a facile hydrothermal process with the presence of hydrazine hydrate as the mineralizer. The treated CNTs can be easily dispersed in aqueous solvent. Moreover, X-ray photoelectron spectroscopy (XPS) analysis reveals that several functional groups such as potassium carboxylate (-COOK), carbonyl (-C dbnd O) and hydroxyl (-C-OH) groups are formed on the nanotube surfaces. The MWCNTs/Fe 3O 4 hybrids are characterized with respect to crystal structure, morphology, element composition and magnetic property by X-ray diffraction (XRD), transmission electron microscopy (TEM), XPS and superconducting quantum interference device (SQUID) magnetometer. XRD and TEM results show that the Fe 3O 4 nanoparticles with diameter in the range of 20-60 nm were firmly assembled on the nanotube surface. The magnetic property investigation indicated that the CNTs/Fe 3O 4 hybrids exhibit a ferromagnetic behavior and possess a saturation magnetization of 32.2 emu/g. Further investigation indicates that the size of assembled Fe 3O 4 nanoparticles can be turned by varying experiment factors. Moreover, a probable growth mechanism for the preparation of CNTs/Fe 3O 4 hybrids was discussed.

  18. An ecological perspective of Listeria monocytogenes biofilms in food processing facilities.

    PubMed

    Valderrama, Wladir B; Cutter, Catherine N

    2013-01-01

    Listeria monocytogenes can enter the food chain at virtually any point. However, food processing environments seem to be of particular importance. From an ecological point of view, food processing facilities are microbial habitats that are constantly disturbed by cleaning and sanitizing procedures. Although L. monocytogenes is considered ubiquitous in nature, it is important to recognize that not all L. monocytogenes strains appear to be equally distributed; the distribution of the organism seems to be related to certain habitats. Currently, no direct evidence exists that L. monocytogenes-associated biofilms have played a role in food contamination or foodborne outbreaks, likely because biofilm isolation and identification are not part of an outbreak investigation, or the definition of biofilm is unclear. Because L. monocytogenes is known to colonize surfaces, we suggest that contamination patterns may be studied in the context of how biofilm formation is influenced by the environment within food processing facilities. In this review, direct and indirect epidemiological and phenotypic evidence of lineage-related biofilm formation capacity to specific ecological niches will be discussed. A critical view on the development of the biofilm concept, focused on the practical implications, strengths, and weaknesses of the current definitions also is discussed. The idea that biofilm formation may be an alternative surrogate for microbial fitness is proposed. Furthermore, current research on the influence of environmental factors on biofilm formation is discussed. PMID:23768144

  19. Design of a lunar propellant processing facility. NASA/USRA advanced program

    NASA Technical Reports Server (NTRS)

    Batra, Rajesh; Bell, Jason; Campbell, J. Matt; Cash, Tom; Collins, John; Dailey, Brian; France, Angelique; Gareau, Will; Gleckler, Mark; Hamilton, Charles

    1993-01-01

    Mankind's exploration of space will eventually lead to the establishment of a permanent human presence on the Moon. Essential to the economic viability of such an undertaking will be prudent utilization of indigenous lunar resources. The design of a lunar propellant processing system is presented. The system elements include facilities for ore processing, ice transportation, water splitting, propellant storage, personnel and materials transportation, human habitation, power generation, and communications. The design scenario postulates that ice is present in the lunar polar regions, and that an initial lunar outpost was established. Mining, ore processing, and water transportation operations are located in the polar regions. Water processing and propellant storage facilities are positioned near the equator. A general description of design operations is outlined below. Regolith containing the ice is mined from permanently-shaded polar craters. Water is separated from the ore using a microwave processing technique, and refrozen into projectiles for launch to the equatorial site via railgun. A mass-catching device retrieves the ice. This ice is processed using fractional distillation to remove impurities, and the purified liquid water is fed to an electrolytic cell that splits the water into vaporous hydrogen and oxygen. The hydrogen and oxygen are condensed and stored separately in a tank farm. Electric power for all operations is supplied by SP-100 nuclear reactors. Transportation of materials and personnel is accomplished primarily using chemical rockets. Modular living habitats are used which provide flexibility for the placement and number of personnel. A communications system consisting of lunar surface terminals, a lunar relay satellite, and terrestrial surface stations provides capabilities for continuous Moon-Moon and Moon-Earth transmissions of voice, picture, and data.

  20. The Shuttle Radar Topography Mission is uncrated in the Multi- Payload Processing Facility

    NASA Technical Reports Server (NTRS)

    1999-01-01

    The Shuttle Radar Topography Mission (SRTM) sits uncovered inside the Multi-Payload Processing Facility. The primary payload on mission STS-99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission scheduled for September 1999. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  1. A facile water-based process for preparation of stabilized Bi nanoparticles

    SciTech Connect

    Wang Yi; Zhao Jingzhe Zhao Xu; Tang Lanqin; Li Yunling; Wang Zichen

    2009-01-08

    Stabilized bismuth nanoparticles have been prepared by reducing bismuth chloride with hydrazine hydrate in the presence of sodium oleate under a facile water-based process. The obtained samples are investigated by X-ray diffraction, transmission electron microscopy (TEM) and differential thermal analysis and thermogravimetry (DTA/TG). The present results indicate that the bismuth nanoparticles are spherical, small diameter and in a high purity. In addition, measurement of water contact angle indicates that Bi samples are hydrophobic, which gives defense to samples from further oxidation, samples are steady in 6 months without obvious oxidation.

  2. Migration of Beryllium via Multiple Exposure Pathways among Work Processes in Four Different Facilities.

    PubMed

    Armstrong, Jenna L; Day, Gregory A; Park, Ji Young; Stefaniak, Aleksandr B; Stanton, Marcia L; Deubner, David C; Kent, Michael S; Schuler, Christine R; Virji, M Abbas

    2014-01-01

    Inhalation of beryllium is associated with the development of sensitization; however, dermal exposure may also be important. The primary aim of this study was to elucidate relationships among exposure pathways in four different manufacturing and finishing facilities. Secondary aims were to identify jobs with increased levels of beryllium in air, on skin, and on surfaces; identify potential discrepancies in exposure pathways, and determine if these are related to jobs with previously identified risk. Beryllium was measured in air, on cotton gloves, and on work surfaces. Summary statistics were calculated and correlations among all three measurement types were examined at the facility and job level. Exposure ranking strategies were used to identify jobs with higher exposures. The highest air, glove, and surface measurements were observed in beryllium metal production and beryllium oxide ceramics manufacturing jobs that involved hot processes and handling powders. Two finishing and distribution facilities that handle solid alloy products had lower exposures than the primary production facilities, and there were differences observed among jobs. For all facilities combined, strong correlations were found between air-surface (rp ≥ 0.77), glove-surface (rp ≥ 0.76), and air-glove measurements (rp ≥ 0.69). In jobs where higher risk of beryllium sensitization or disease has been reported, exposure levels for all three measurement types were higher than in jobs with lower risk, though they were not the highest. Some jobs with low air concentrations had higher levels of beryllium on glove and surface wipe samples, suggesting a need to further evaluate the causes of the discrepant levels. Although such correlations provide insight on where beryllium is located throughout the workplace, they cannot identify the direction of the pathways between air, surface, or skin. Ranking strategies helped to identify jobs with the highest combined air, glove, and/or surface exposures. All previously identified high-risk jobs had high air concentrations, dermal mass loading, or both, and none had low dermal and air. We have found that both pathways are relevant. [Supplementary materials are available for this article. Go to the publisher's online edition of Journal of Occupational and Environmental Hygiene for the following free supplemental resource: a file describing the forms of beryllium materials encountered during production and characteristics of the aerosols by process areas.]. PMID:25357184

  3. Radioactive Air Emmission Notice of Construction (NOC) for the Waste Receiving and Processing Facility (WRAP)

    SciTech Connect

    MENARD, N.M.

    2000-12-01

    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 modify pursuant to 40 Code of Federal Regulations (CFR) 61.07 for the Waste Receiving and Processing (WRAP) Facility. The rewrite of this NOC incorporates all the approved revisions (Sections 5.0, 6.0, 8.0, and 9.0), a revised potential to emit (PTE) based on the revised maximally exposed individual (MEI) (Sections 8.0, 10.0, 11.0, 12.0, 13.0, 14.0, and 15.0), the results of a study on fugitive emissions (Sections 6.0, 10.0, and 15.0), and reflects the current operating conditions at the WRAP Facility (Section 5.0). This NOC replaces DOE/RL-93-15 and DOE/RL-93-16 in their entirety. The primary function of the WRAP Facility is to examine, assay, characterize, treat, verify, and repackage radioactive material and mixed waste. There are two sources of emissions from the WRAP Facility: stack emissions and fugitive emissions. The stack emissions have an unabated total effective dose equivalent (TEDE) estimate to the hypothetical offsite MEI of 1.13 E+02 millirem per year. The abated TEDE for the stack emissions is estimated at 5.63 E-02 millirem per year to the MEI. The fugitive emissions have an unabated TEDE estimate to the hypothetical offsite MEI of 5.87 E-04. There is no abatement for the fugitive emissions.

  4. Installation of semiconductor crystal growth and processing facilities in the Building 166 addition at Lawrence Livermore National Laboratory

    NASA Astrophysics Data System (ADS)

    1990-08-01

    A new addition was constructed to Building 166 at Lawrence Livermore National Laboratory (LLNL). This addition is intended to contain facilities as described below. The Metalorganic Chemical Vapor Deposition (MOCVD) facility is a proposed facility for the growth of semiconductor crystals composed of various combinations of gallium, aluminum, indium, arsenic, phosphorous, antimony, silicon, and zinc. This facility will utilize hazardous metal hydride gases (arsine, silane, and disilane) and pyrophoric materials (metal alkyls). The MOCVD process has been intensively developed over the past 10 years and is being safely utilized in over 75 locations worldwide in both research and manufacturing applications. All equipment in the LLNL MOCVD facility is commercially available and is typical of that used in similar facilities in both industry and academia. The Semiconductor Device Fabrication (SDF) facility is a proposed facility for the fabrication of semiconductor devices from crystals grown in the MOCVD facility. General laboratory chemicals and silane gas will be utilized in this facility. The remaining space in the building addition will consist of an optics laboratory and general purpose work area. The only hazardous materials to be used in these areas are small quantities of common laboratory solvents. For the purposes of this Environmental Assessment, these areas will be considered to be part of the SDF.

  5. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ..., DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE SOUTH DAKOTA 941.827 Special performance standardscoal processing plants and support facilities not...

  6. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ..., DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE SOUTH DAKOTA 941.827 Special performance standardscoal processing plants and support facilities not...

  7. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ..., DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE SOUTH DAKOTA 941.827 Special performance standardscoal processing plants and support facilities not...

  8. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ..., DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE SOUTH DAKOTA 941.827 Special performance standardscoal processing plants and support facilities not...

  9. Advanced technologies for maintenance of electrical systems and equipment at the Savannah River Site Defense Waste Processing Facility

    SciTech Connect

    Husler, R.O. ); Weir, T.J. )

    1991-01-01

    An enhanced maintenance program is being established to characterize and monitor cables, components, and process response at the Savannah River Site, Defense Waste Processing Facility. This facility was designed and constructed to immobilize the radioactive waste currently stored in underground storage tanks and is expected to begin operation in 1993. The plant is initiating the program to baseline and monitor instrument and control (I C) and electrical equipment, remote process equipment, embedded instrument and control cables, and in-cell jumper cables used in the facility. This program is based on the electronic characterization and diagnostic (ECAD) system which was modified to include process response analysis and to meet rigid Department of Energy equipment requirements. The system consists of computer-automated, state-of-the-art electronics. The data that are gathered are stored in a computerized database for analysis, trending, and troubleshooting. It is anticipated that the data which are gathered and trended will aid in life extension for the facility.

  10. [The 'ideal therapy process': testing a new approach for assessing process quality in inpatient parent-child facilities].

    PubMed

    Musekamp, G; Lukasczik, M; Gerlich, C; Saupe-Heide, M; Lbmann, R; Vogel, H; Neuderth, S

    2014-12-01

    Instruments for external quality assurance in inpatient parent-child rehabilitation and prevention facilities were developed in 2 projects. For the assessment of process quality, we sought an alternative test to the peer review procedure which also places a stronger emphasis on patient perspectives. The aim was to define an "ideal process" as a standard, to develop quantifiable criteria, and to test a multimethod approach which involves different data levels. On the basis of different sources, the "ideal process" for parent-child rehabilitation and prevention and associated criteria were defined by involving an accompanying expert group during a consensus process. Criteria were assessed on different levels: on the rehabilitation/prevention centre level, a questionnaire of process-relevant structural features was used; on the patient level, a case-related routine documentation filled in by clinic staff and an incident-related patient questionnaire were applied. Data were collected in 37 centres (prevention: 19; rehabilitation: 11; 7 offering both types of programmes). Analysis of patient-related data is based on a sample of 1?513 prevention patients and 286 rehabilitation patients. The resulting "ideal process" consists of the stages "preparation", "arrival", "treatment planning", "treatment", "completion of treatment", and "organisation", each containing specific criteria. Exemplarily, the outcomes for the stages "treatment planning" and "treatment" are presented. There is variability both between features and between clinics. The majority of the patients report that the criteria are fulfilled while there are medium to high levels of fulfillment regarding the routine documentation. The criteria of the questionnaire of process-relevant structural features are mostly fulfilled according to the clinics. Agreement between the 3 data levels can be observed. On the basis of the defined "ideal process", the methods that were tested seem to be appropriate to illustrate process-relevant features from different perspectives. The exemplary measured process quality of the pilot clinics can be judged as predominantly good. Individual deficits of process quality and limitations of the chosen methods are discussed. PMID:24408310

  11. TRENTA Facility for Trade-Off Studies Between Combined Electrolysis Catalytic Exchange and Cryogenic Distillation Processes

    SciTech Connect

    Cristescu, I.; Cristescu, I.R.; Doerr, L.; Glugla, M.; Hellriegel, G.; Schaefer, P.; Welte, S.; Kveton, O.; Murdoch, D

    2005-07-15

    One of the most used methods for tritium recovery from different sources of tritiated water is based on the combination between Combined Electrolysis Catalytic Exchange (CECE) and Cryogenic Distillation (CD) processes. The development, i.e. configuration, design and performance testing of critical components, of a tritium recovery system based on the combination CECE-CD is essential for both JET and ITER. For JET, a Water Detritiation System (WDS) is not only needed to process tritiated water which has already been accumulated from operation, but also for the tritiated water which will be generated during decommissioning. For ITER, the WDS is one of the key systems to control the tritium content in the effluents streams, to recover as much tritium as possible and consequently to minimize the impact on the environment. A cryogenic distillation facility with the aim to investigate the trade-off between CECE-CD, to validate different components and mathematical modelling software is current under development at Tritium Laboratory Karlsruhe (TLK) as an extension of the existing CECE facility.

  12. Mercury Reduction and Removal from High Level Waste at the Defense Waste Processing Facility - 12511

    SciTech Connect

    Behrouzi, Aria; Zamecnik, Jack

    2012-07-01

    The Defense Waste Processing Facility processes legacy nuclear waste generated at the Savannah River Site during production of enriched uranium and plutonium required by the Cold War. The nuclear waste is first treated via a complex sequence of controlled chemical reactions and then vitrified into a borosilicate glass form and poured into stainless steel canisters. Converting the nuclear waste into borosilicate glass is a safe, effective way to reduce the volume of the waste and stabilize the radionuclides. One of the constituents in the nuclear waste is mercury, which is present because it served as a catalyst in the dissolution of uranium-aluminum alloy fuel rods. At high temperatures mercury is corrosive to off-gas equipment, this poses a major challenge to the overall vitrification process in separating mercury from the waste stream prior to feeding the high temperature melter. Mercury is currently removed during the chemical process via formic acid reduction followed by steam stripping, which allows elemental mercury to be evaporated with the water vapor generated during boiling. The vapors are then condensed and sent to a hold tank where mercury coalesces and is recovered in the tank's sump via gravity settling. Next, mercury is transferred from the tank sump to a purification cell where it is washed with water and nitric acid and removed from the facility. Throughout the chemical processing cell, compounds of mercury exist in the sludge, condensate, and off-gas; all of which present unique challenges. Mercury removal from sludge waste being fed to the DWPF melter is required to avoid exhausting it to the environment or any negative impacts to the Melter Off-Gas system. The mercury concentration must be reduced to a level of 0.8 wt% or less before being introduced to the melter. Even though this is being successfully accomplished, the material balances accounting for incoming and collected mercury are not equal. In addition, mercury has not been effectively purified and collected in the Mercury Purification Cell (MPC) since 2008. A significant cleaning campaign aims to bring the MPC back up to facility housekeeping standards. Two significant investigations are being undertaken to restore mercury collection. The SMECT mercury pump has been removed from the tank and will be functionally tested. Also, research is being conducted by the Savannah River National Laboratory to determine the effects of antifoam addition on the behavior of mercury. These path forward items will help us better understand what is occurring in the mercury collection system and ultimately lead to an improved DWPF production rate and mercury recovery rate. (authors)

  13. Status of the Development of In-Tank/At-Tank Separations Technologies for High-Level Waste Processing for the U.S. Department of Energy

    SciTech Connect

    Wilmarth, William R.; Machara, N.; Peterson, Reid A.; Bush, Sheryl R.

    2011-10-01

    Within the U.S. Department of Energys (DOE) Office of Technology Innovation and Development, the Office of Waste Processing manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226 storage tanks (grouped or collocated in tank farms). This waste may be considered to contain mixed and stratified high activity and low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are first-of-a-kind and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be developed from basic principles, or require significant re-engineering to adapt to DOEs specific applications. Of particular interest recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing. Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanfords Waste Treatment and Immobilization Plant (WTP) or Savannah Rivers Salt Waste Processing Facility (SWPF)); and (3) create a parallel treatment process to shorten the overall treatment duration.

  14. Obliterative bronchiolitis in workers in a coffee-processing facility - Texas, 2008-2012.

    PubMed

    2013-04-26

    Obliterative bronchiolitis, a rare, irreversible form of fixed obstructive lung disease, has been identified in workers exposed to flavoring chemicals while working in the microwave-popcorn and flavoring-manufacturing industries; the occupational risk to workers outside these industries is largely unknown. This report describes two cases of obliterative bronchiolitis identified in workers employed in a small coffee-processing facility. Both patients' illness was misdiagnosed before they received a diagnosis of work-related obliterative bronchiolitis, which had not been identified previously in the coffee-processing industry. These cases reinforce the need for exposure evaluation in all industries in which workers are exposed to flavoring chemicals. Additionally, a high index of suspicion is required when these potentially exposed workers have progressive shortness of breath. If obliterative bronchiolitis is suspected, immediate protection from further exposure is crucial to prevent further deterioration of lung function. PMID:23615673

  15. The low moisture eastern coal processing system at the UTSI-DOE Coal Fired Flow Facility

    SciTech Connect

    Evans, B.R.; Washington, E.S.; Sanders, M.E.

    1993-10-01

    A low moisture, eastern coal processing system was constructed at the Department of Energy`s Coal Fired Flow Facility (CFFF), located at the University of Tennessee Space Institute in Tullahoma, Tennessee, to provide a metered and regulated supply of seeded, pulverized coal to support magnetohydrodynamic (MHD) power generation research. The original system configuration is described as well as major modifications made in response to specific operational problems. Notable among these was the in-house development of the Moulder flow control valve which exhibited marked improvement in durability compared to previous valves used with pulverized coal. Coal processing system performance parameters are discussed. A summary of tests conducted and significant events are included.

  16. Idaho Chemical Processing Plant Liquid Effluent Treatment and Disposal Facility hot test report

    SciTech Connect

    Hastings, R.L.

    1993-09-01

    Prior to initial operation with radioactive feed or ``hot`` operation, the Liquid Effluent Treatment and Disposal (LET&D) Facility underwent extensive testing. This report provides a detailed description and analysis of this testing. Testing has determined that LET&D is capable of processing radioactive solutions between the design flowrates of 275 gph to 550 gph. Modifications made to prevent condensation on the off-gas HEPA filters, to the process vacuum control, bottoms cooler rupture disks, and feed control system operation were successful. Unfortunately, two mixers failed prior to ``hot`` testing due to manufacturer`s error which limited operation of the PEW Evaporator System and sampling was not able to prove that design removal efficiencies for Mercury, Cadmium, Plutonium, and Non-Volatile Radionuclides.

  17. Cancer incidence in municipalities near two former nuclear materials processing facilities in Pennsylvania--an update.

    PubMed

    Boice, John D; Bigbee, William L; Mumma, Michael T; Heath, Clark W; Blot, William J

    2009-02-01

    Previous studies of cancer incidence among persons living in municipalities within one mile of two nuclear materials processing and fabrication plants in Pennsylvania were extended for the years 1998-2004. It had been shown that mailing addresses for residents of rural areas often did not reflect the actual municipality of residence and, if not corrected, would bias study results. The previous studies had corrected for this bias. Accordingly for the extended study, we obtained mailing addresses from the Pennsylvania Department of Health (PDH) for 866 persons with cancer who presumably lived in one of eight minor civil divisions (MCDs) near or encompassing the former nuclear facilities, designated as Area 1 in previous studies conducted by the PDH. Street addresses were geocoded and local postmasters were asked to place rural delivery addresses, post office boxes and street addresses that could not be geocoded into the correct MCD of actual residence. Over 15% of the mailing addresses were found not to be within the boundaries of the Area 1 municipalities. After the mailing addresses of individuals with cancer were placed in their proper MCD of residence, the number of persons diagnosed with cancer (n = 708) and confirmed to have lived in Area 1 was as expected (728.4) based on cancer incidence rates in the general population of Pennsylvania (SIR 0.97; 95% CI 0.90-1.05). To further evaluate the patterns of cancer rates near these nuclear facilities and the influence of improved reporting and geocoding of addresses over time, analyses were conducted of publicly available cancer incidence data from 1990 through 2004. Based on mailing addresses, a steady decrease in the number of cancers reported in the Area 1 proximal MCDs was seen, in contrast to a steady rise in the number of cancers reported in seven adjacent but more distant MCDs from the nuclear facilities, designated as Area 2. These patterns were attributed to improvements over time in the geocoding of residential mailing addresses coupled with the gradual elimination and replacement of rural delivery addresses with street addresses. The incorrect placement of mailing addresses in residential Area 1 municipalities prior to about 2002 overestimated the number of cancers occurring among residents living in close proximity to the nuclear facilities and, correspondingly, underestimated the number among Area 2 residents. Summing Area 1 and Area 2 data showed that there was no change in cancer rates over time. These results are consistent with previous studies indicating that living in municipalities near the former Apollo-Parks nuclear facilities was not associated with an increase in cancer occurrence. PMID:19131733

  18. Facility design: introduction. [TRU facility

    SciTech Connect

    Unger, W.E.

    1980-08-11

    The design of shielded chemical processing facilities for handling plutonium is discussed. The TRU facility is considered in particular; its features for minimizing the escape of process materials are listed. 20 figures. (DLC)

  19. Studsvik Processing Facility - A proven solution for the conservation of a National Asset

    SciTech Connect

    Ping, M.; Hill, M.; Harrison, J.; Wise, D.

    2007-07-01

    Studsvik has completed over 7.5 years of operation at its Erwin, TN facility. During this time period Studsvik processed over 13.3 million pounds (4.96 million kg) of radioactive ion exchange bead resin, powdered filter media, granular activated carbon (GAC), and filter cartridges which comprised a cumulative total activity of 87,396 Curies (3.23E+09 MBq), with the highest radiation level for any incoming resin container being 400 R/hr (4.0 Sv/hr). The Studsvik Processing Facility (SPF-Erwin) has the capability to safely and efficiently receive and process a wide variety of solid and liquid Low Level Radioactive Waste (LLRW) streams including: Spent Filter Cartridges (Metal or Poly), Ion Exchange Resins (IER), powered filter media, GAC, organic solids, graphite, oils, solvents, and cleaning solutions. In 2005 Studsvik added advanced robotic technology to the SPF greatly increasing its capabilities to safely handle waste streams with radiation levels in excess of 400 R/hr (4.0 Sv/h), saving personnel exposure and maximizing ALARA. The most recent addition to Studsvik's capabilities is the cost and volume efficient processing of filter cartridges (both metal and poly). The SPF-Erwin employs the Thermal Organic Reduction (THOR{sup sm}) process, developed and patented by Studsvik, which utilizes pyrolysis/steam reforming technology. THOR{sup sm} reliably and safely processes these wide varieties of LLRWs in a unique, moderate temperature, pyrolysis/steam reforming, fluidized bed treatment system. The THOR{sup sm} technology is also suitable for processing hazardous, mixed, and dry active LLRW with appropriate licensing and waste feed modifications. Studsvik has proven to be an experienced and reliable source for the cost efficient disposition of LLRW for the nuclear industry. These processing concepts and capabilities have helped generators maximize the utilization of the limited available burial space - extending the Class-A, Class-B, and Class-C burial capabilities. This paper will provide an overview of this proven approach for both organic and inorganic LLRWs. A perfect example of the processors and generators working together to conserve a National Asset we have all come to know as the LLRW burial sites. (authors)

  20. VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY'S (DWPF) PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 7A QUALIFICATION SAMPLE

    SciTech Connect

    Click, D.; Edwards, T.; Jones, M.; Wiedenman, B.

    2011-03-14

    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.

  1. A Guide for Developing Standard Operating Job Procedures for the Sludge Thickening Process Wastewater Treatment Facility. SOJP No. 9.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the screening and grinding process of wastewater treatment facilities. The objective of this process is the removal of coarse materials from the raw waste stream for the protection of subsequent equipment and processes. The guide gives step-by-step instructions for safety inspection,

  2. A Guide for Developing Standard Operating Job Procedures for the Screening & Grinding Process Wastewater Treatment Facility. SOJP No. 1.

    ERIC Educational Resources Information Center

    Deal, Gerald A.; Montgomery, James A.

    This guide describes standard operating job procedures for the screening and grinding process of wastewater treatment facilities. The objective of this process is the removal of coarse materials from the raw waste stream for the protection of subsequent equipment and processes. The guide gives step-by-step instructions for safety inspection,

  3. Development of CFC-Free Cleaning Processes at the NASA White Sands Test Facility

    NASA Technical Reports Server (NTRS)

    Beeson, Harold; Kirsch, Mike; Hornung, Steven; Biesinger, Paul

    1995-01-01

    The NASA White Sands Test Facility (WSTF) is developing cleaning and verification processes to replace currently used chlorofluorocarbon-113- (CFC-113-) based processes. The processes being evaluated include both aqueous- and solvent-based techniques. The presentation will include the findings of investigations of aqueous cleaning and verification processes that are based on a draft of a proposed NASA Kennedy Space Center (KSC) cleaning procedure. Verification testing with known contaminants, such as hydraulic fluid and commonly used oils, established correlations between nonvolatile residue and CFC-113. Recoveries ranged from 35 to 60 percent of theoretical. WSTF is also investigating enhancements to aqueous sampling for organics and particulates. Although aqueous alternatives have been identified for several processes, a need still exists for nonaqueous solvent cleaning, such as the cleaning and cleanliness verification of gauges used for oxygen service. The cleaning effectiveness of tetrachloroethylene (PCE), trichloroethylene (TCE), ethanol, hydrochlorofluorocarbon-225 (HCFC-225), tert-butylmethylether, and n-Hexane was evaluated using aerospace gauges and precision instruments and then compared to the cleaning effectiveness of CFC-113. Solvents considered for use in oxygen systems were also tested for oxygen compatibility using high-pressure oxygen autoignition and liquid oxygen mechanical impact testing.

  4. An ImageJ plugin for ion beam imaging and data processing at AIFIRA facility

    NASA Astrophysics Data System (ADS)

    Devès, G.; Daudin, L.; Bessy, A.; Buga, F.; Ghanty, J.; Naar, A.; Sommar, V.; Michelet, C.; Seznec, H.; Barberet, P.

    2015-04-01

    Quantification and imaging of chemical elements at the cellular level requires the use of a combination of techniques such as micro-PIXE, micro-RBS, STIM, secondary electron imaging associated with optical and fluorescence microscopy techniques employed prior to irradiation. Such a numerous set of methods generates an important amount of data per experiment. Typically for each acquisition the following data has to be processed: chemical map for each element present with a concentration above the detection limit, density and backscattered maps, mean and local spectra corresponding to relevant region of interest such as whole cell, intracellular compartment, or nanoparticles. These operations are time consuming, repetitive and as such could be source of errors in data manipulation. In order to optimize data processing, we have developed a new tool for batch data processing and imaging. This tool has been developed as a plugin for ImageJ, a versatile software for image processing that is suitable for the treatment of basic IBA data operations. Because ImageJ is written in Java, the plugin can be used under Linux, Mas OS X and Windows in both 32-bits and 64-bits modes, which may interest developers working on open-access ion beam facilities like AIFIRA. The main features of this plugin are presented here: listfile processing, spectroscopic imaging, local information extraction, quantitative density maps and database management using OMERO.

  5. Radioactive air emissions notice of construction for the Waste Receiving And Processing facility

    SciTech Connect

    Not Available

    1993-02-01

    The mission of the Waste Receiving And Processing (WRAP) Module 1 facility (also referred to as WRAP 1) includes: examining, assaying, characterizing, treating, and repackaging solid radioactive and mixed waste to enable permanent disposal of the wastes in accordance with all applicable regulations. The solid wastes to be handled in the WRAP 1 facility include low-level waste (LLW), transuranic (TRU) waste, TRU mixed wastes, and low-level mixed wastes (LLMW). Airborne releases from the WRAP 1 facility will be primarily in particulate forms (99.999 percent of total unabated emissions). The release of two volatilized radionuclides, tritium and carbon-14 will contribute less than 0.001 percent of the total unabated emissions. Table 2-1 lists the radionuclides which are anticipated to be emitted from WRAP 1 exhaust stack. The Clean Air Assessment Package 1988 (CAP-88) computer code (WHC 1991) was used to calculate effective dose equivalent (EDE) from WRAP 1 to the maximally exposed offsite individual (MEI), and thus demonstrate compliance with WAC 246-247. Table 4-1 shows the dose factors derived from the CAP-88 modeling and the EDE for each radionuclide. The source term (i.e., emissions after abatement in curies per year) are multiplied by the dose factors to obtain the EDE. The total projected EDE from controlled airborne radiological emissions to the offsite MEI is 1.31E-03 mrem/year. The dose attributable to radiological emissions from WRAP 1 will, then, constitute 0.013 percent of the WAC 246-247 EDE regulatory limit of 10 mrem/year to the offsite MEI.

  6. A combined approach of simulation and analytic hierarchy process in assessing production facility layouts

    NASA Astrophysics Data System (ADS)

    Ramli, Razamin; Cheng, Kok-Min

    2014-07-01

    One of the important areas of concern in order to obtain a competitive level of productivity in a manufacturing system is the layout design and material transportation system (conveyor system). However, changes in customers' requirements have triggered the need to design other alternatives of the manufacturing layout for existing production floor. Hence, this paper discusses effective alternatives of the process layout specifically, the conveyor system layout. Subsequently, two alternative designs for the conveyor system were proposed with the aims to increase the production output and minimize space allocation. The first proposed layout design includes the installation of conveyor oven in the particular manufacturing room based on priority, and the second one is the one without the conveyor oven in the layout. Simulation technique was employed to design the new facility layout. Eventually, simulation experiments were conducted to understand the performance of each conveyor layout design based on operational characteristics, which include predicting the output of layouts. Utilizing the Analytic Hierarchy Process (AHP), the newly and improved layout designs were assessed before the final selection was done. As a comparison, the existing conveyor system layout was included in the assessment process. Relevant criteria involved in this layout design problem were identified as (i) usage of space of each design, (ii) operator's utilization rates, (iii) return of investment (ROI) of the layout, and (iv) output of the layout. In the final stage of AHP analysis, the overall priority of each alternative layout was obtained and thus, a selection for final use by the management was made based on the highest priority value. This efficient planning and designing of facility layout in a particular manufacturing setting is able to minimize material handling cost, minimize overall production time, minimize investment in equipment, and optimize utilization of space.

  7. Node 2 and Japanese Experimental Module (JEM) In Space Station Processing Facility

    NASA Technical Reports Server (NTRS)

    2003-01-01

    Lining the walls of the Space Station Processing Facility at the Kennedy Space Center (KSC) are the launch awaiting U.S. Node 2 (lower left). and the first pressurized module of the Japanese Experimental Module (JEM) (upper right), named 'Kibo' (Hope). Node 2, the 'utility hub' and second of three connectors between International Space Station (ISS) modules, was built in the Torino, Italy facility of Alenia Spazio, an International contractor based in Rome. Japan's major contribution to the station, the JEM, was built by the Space Development Agency of Japan (NASDA) at the Tsukuba Space Center near Tokyo and will expand research capabilities aboard the station. Both were part of an agreement between NASA and the European Space Agency (ESA). The Node 2 will be the next pressurized module installed on the Station. Once the Japanese and European laboratories are attached to it, the resulting roomier Station will expand from the equivalent space of a 3-bedroom house to a 5-bedroom house. The Marshall Space Center in Huntsville, Alabama manages the Node program for NASA.

  8. Letter Report. Defense Waste Processing Facility Pour Spout Heaters - Conceptual Designs and Modeling

    SciTech Connect

    SK Sundaram; JM Perez, Jr.

    2000-09-06

    The Tanks Focus Area (TFA) identified a major task to address performance limitations and deficiencies of the Defense Waste Processing Facility (DWPF) now in its sixth year of operation. Design, installation, testing, monitoring, operability, and a number of other characteristics were studied by research personnel collaboratively at a number of facilities: Savannah River Technology Center (SRTC), Clemson Environmental Technologies Laboratory (CETL), Pacific Northwest National Laboratory (PNNL), and the Idaho National Engineering and Environmental Laboratory (INEEL). Because the potential limiting feature to the DWPF was identified as the pour spout/riser heater, researches on alternative design concepts originally proposed in the past were revisited. In the original works, finite element modeling was performed to evaluate temperature distribution and stress of the design currently used at the DWPF. Studies were also made to define the requirements of the design and to consider the approaches for remote removal/replacement. Their heater type/location, their remotely replaceable thermocouples, and their capabilities for remote handling characterized the five alternative designs proposed. Review comments on the alternative designs indicated a relatively wide range of advantages and disadvantages of the designs. The present report provides an overview of the design criteria, modeling results, and alternative designs. Based on a review of the past design optimization activities and an assessment of recent experience, recommendations are proposed for future consideration and improvement.

  9. USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

    SciTech Connect

    WESTCOTT, J.L.; JOCHEN; PREVETTE

    2007-01-02

    Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State are being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary.

  10. USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

    SciTech Connect

    WESTCOTT, J.L.

    2006-11-15

    Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary.

  11. Basic Data Report -- Defense Waste Processing Facility Sludge Plant, Savannah River Plant 200-S Area

    SciTech Connect

    Amerine, D.B.

    1982-09-01

    This Basic Data Report for the Defense Waste Processing Facility (DWPF)--Sludge Plant was prepared to supplement the Technical Data Summary. Jointly, the two reports were intended to form the basis for the design and construction of the DWPF. To the extent that conflicting information may appear, the Basic Data Report takes precedence over the Technical Data Summary. It describes project objectives and design requirements. Pertinent data on the geology, hydrology, and climate of the site are included. Functions and requirements of the major structures are described to provide guidance in the design of the facilities. Revision 9 of the Basic Data Report was prepared to eliminate inconsistencies between the Technical Data Summary, Basic Data Report and Scopes of Work which were used to prepare the September, 1982 updated CAB. Concurrently, pertinent data (material balance, curie balance, etc.) have also been placed in the Basic Data Report. It is intended that these balances be used as a basis for the continuing design of the DWPF even though minor revisions may be made in these balances in future revisions to the Technical Data Summary.

  12. Final deactivation project report on the Integrated Process Demonstration Facility, Building 7602 Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-09-01

    The purpose of this report is to document the condition of the Integrated Process Demonstration Facility (Building 7602) at Oak Ridge National Laboratory (ORNL) after completion of deactivation activities by the High Ranking Facilities Deactivation Project (HRFDP). This report identifies the activities conducted to place the facility in a safe and environmentally sound condition prior to transfer to the U.S. Department of Energy (DOE) Environmental Restoration EM-40 Program. This report provides a history and description of the facility prior to commencing deactivation activities and documents the condition of the building after completion of all deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance (S&M) Plan, remaining hazardous and radioactive materials inventory, radiological controls, Safeguards and Security, and supporting documentation provided in the Office of Nuclear Material and Facility Stabilization Program (EM-60) Turnover package are discussed.

  13. Experience of Hot Cell Renovation Work in CPF (Chemical Processing Facility)

    SciTech Connect

    Toyonobu Nabemoto; Fujio Katahira; Tadatsugu Sakaya; Shinichi Aose; Takafumi Kitajima; Kouji Ogasawara; Kazunori Nomura; Shigehiko Miyachi; Yoshiaki Ichige; Tadahiro Shinozaki; Shinichi Ohuchi

    2008-01-15

    Renovation work for operation room A of the Chemical Processing Facility (CPF) was carried out. Cell renovation work involved disassembly, removal and installation of new equipment for the CA-3 cell of operation room A and the crane renovation work involved the repair of the in-cell crane for the CA-5 cell of operation room A. There were not many examples of renovation work performed on cells under high radiation environment and alpha contamination in Japan. Lessons learnt: With respect to the cell renovation work and crane repair work, a method that gave full consideration to safety was employed and the work was performed without accidents or disaster. Moreover, through improvement of the method, reduction of radioactive exposure of the workers was achieved and a melt reduction device was designed to deal with the radioactive waste material that was generated in the renovation work to achieve significant melt reduction of waste material.

  14. Ohio Senator John Glenn tours the SPACEHAB Payload Processing Facility in Cape Canaveral

    NASA Technical Reports Server (NTRS)

    1998-01-01

    Ohio Senator John Glenn, second from right, enjoys a tour of the SPACEHAB Payload Processing Facility in Cape Canaveral. Joining Senator Glenn are, left to right, Dr. Bernard Harris, SPACEHAB vice president, microgravity and life sciences; Dale Steffey, SPACEHAB vice president, operations; and Dr. Shelley Harrison, SPACEHAB chairman and chief executive officer. Senator Glenn arrived at KSC on Jan. 20 to tour KSC operational areas and to view the launch of STS-89 later this week. Glenn, who made history in 1962 as the first American to orbit the Earth, completing three orbits in a five-hour flight aboard Friendship 7, will fly his second space mission aboard Space Shuttle Discovery this October. Glenn is retiring from the Senate at the end of this year and will be a payload specialist aboard STS-95.

  15. Ohio Senator John Glenn tours the SPACEHAB Payload Processing Facility in Cape Canaveral

    NASA Technical Reports Server (NTRS)

    1998-01-01

    Ohio Senator John Glenn, second from left, enjoys a tour of the SPACEHAB Payload Processing Facility in Cape Canaveral. Joining Senator Glenn are, left to right, Dale Steffey, SPACEHAB vice president, operations; Dr. Shelley Harrison, SPACEHAB chairman and chief executive officer; and Dr. Bernard Harris, SPACEHAB vice president, microgravity and life sciences. Senator Glenn arrived at KSC on Jan. 20 to tour KSC operational areas and to view the launch of STS-89 later this week. Glenn, who made history in 1962 as the first American to orbit the Earth, completing three orbits in a five-hour flight aboard Friendship 7, will fly his second space mission aboard Space Shuttle Discovery this October. Glenn is retiring from the Senate at the end of this year and will be a payload specialist aboard STS-95.

  16. Ohio Senator John Glenn tours the SPACEHAB Payload Processing Facility in Cape Canaveral

    NASA Technical Reports Server (NTRS)

    1998-01-01

    Ohio Senator John Glenn, at left, enjoys a tour of the SPACEHAB Payload Processing Facility in Cape Canaveral. Joining Senator Glenn are, left to right, Dale Steffey, SPACEHAB vice president, operations; Dr. Shelley Harrison, SPACEHAB chairman and chief executive officer; and Dr. Bernard Harris, SPACEHAB vice president, microgravity and life sciences. Senator Glenn arrived at KSC on Jan. 20 to tour KSC operational areas and to view the launch of STS-89 later this week. Glenn, who made history in 1962 as the first American to orbit the Earth, completing three orbits in a five-hour flight aboard Friendship 7, will fly his second space mission aboard Space Shuttle Discovery this October. Glenn is retiring from the Senate at the end of this year and will be a payload specialist aboard STS-95.

  17. QA Objectives for Nondestructive Assay at the Waste Receiving & Processing (WRAP) Facility

    SciTech Connect

    CANTALOUB, M.G.

    2000-08-01

    The Waste Receiving and Processing (WRAP) facility, located on the Word Site in southeast Washington, is a key link in the certification of transuranic (TRU) waste for shipment to the Waste Isolation Pilot Plant (WIPP). Waste characterization is one of the vital functions performed at WRAP, and nondestructive assay (NDA) measurements of TRU waste containers is one of two required methods used for waste characterization. The Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE/WIPP-069 (WIPP-WAC) delineates the quality assurance objectives which have been established for NDA measurement systems. Sites must demonstrate that the quality assurance objectives can be achieved for each radioassay system over the applicable ranges of measurement. This report summarizes the validation of the WRAP NDA systems against the radioassay quality assurance objectives or QAOs. A brief description of the each test and significant conclusions are included. Variables that may have affected test outcomes and system response are also addressed.

  18. The Shuttle Radar Topography Mission is uncrated in the Multi- Payload Processing Facility

    NASA Technical Reports Server (NTRS)

    1999-01-01

    Inside the Multi-Payload Processing Facility, the lid covering the Shuttle Radar Topography Mission (SRTM) is lifted. The primary payload on mission STS-99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission scheduled for September 1999. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  19. The Shuttle Radar Topography Mission is uncrated in the Multi- Payload Processing Facility

    NASA Technical Reports Server (NTRS)

    1999-01-01

    The Shuttle Radar Topography Mission (SRTM) sits inside the Multi-Payload Processing Facility after the SRTM's cover was removed. The primary payload on mission STS-99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission scheduled for September 1999. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  20. The SRTM is moved into place in the Space Station Processing Facility

    NASA Technical Reports Server (NTRS)

    1999-01-01

    Inside the Space Station Processing Facility, the Shuttle Radar Topography Mission (SRTM) is maneuvered into place to prepare it for launch targeted for September 1999. The primary payload on mission STS-99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  1. The Shuttle Radar Topography Mission is uncrated in the Multi- Payload Processing Facility

    NASA Technical Reports Server (NTRS)

    1999-01-01

    Inside the Multi-Payload Processing Facility, the lid covering the Shuttle Radar Topography Mission (SRTM) is lifted from the crate. The primary payload on mission STS-99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission scheduled for September 1999. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  2. The Shuttle Radar Topography Mission is uncrated in the Multi- Payload Processing Facility

    NASA Technical Reports Server (NTRS)

    1999-01-01

    Inside the Multi-Payload Processing Facility, the Shuttle Radar Topography Mission (SRTM) is revealed after the lid of its container was removed. The primary payload on mission STS-99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission scheduled for September 1999. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  3. Toxicity Characteristic Leaching Procedure (TCLP) testing of Defense Waste Processing Facility (DWPF) projected glass compositions

    SciTech Connect

    Applewhite-Ramsey, A.

    1994-06-01

    Vitrification of Savannah River Site (SRS) high level radioactive waste is scheduled to begin in late 1995. The vitrification operation will take place at the SRS Defense waste Processing Facility (DWPF). The US Department of Energy has instituted specifications which provide technical criteria which must be met by the DWPF to ensure that the waste glass will be suitable for permanent disposal in a federal geologic repository. Included in these criteria is a specification requiring DWPF to determine whether its high level, radioactive waste glass should also be classified as characteristically hazardous waste. A study was performed, using the anticipated range of glass compositions which will be produced over the lifetime of the DWPF, which definitively proved that DWPF waste glass should not be classified as characteristic hazardous waste.

  4. Detailed results of ASTP experiment MA-011. [biological processing facility in space

    NASA Technical Reports Server (NTRS)

    Seaman, G. V. F.; Allen, R. E.; Barlow, G. H.; Bier, M.

    1976-01-01

    This experiment was developed in order to conduct engineering and operational tests of electrokinetic equipment in a micro-gravity environment. The experimental hardware in general functioned as planned and electrophoretic separations were obtained in space. The results indicated the development of satisfactory sample collection, return, and preservation techniques. The application of a near-zero zeta potential interior wall coating to the experimental columns, confirmation of biocompatibility of all appropriate hardware components, and use of a sterile operating environment provided a significant step forward in the development of a biological processing facility in space. A separation of a test of aldehyde-fixed rabbit, human, and horse red blood cells was obtained. Human kidney cells were separated into several components and viable cells returned to earth. The isotachophoretic separation of red cells was also demonstrated. Problems associated with the hardware led to a lack of success in the attempt to separate subpopulations of human lymphocytes.

  5. Performance based seismic qualification of reinforced concrete nuclear materials processing facilities

    SciTech Connect

    Mertz, G.E.; Loceff, F.; Houston, T.; Rauls, G.; Mulliken, J.

    1997-09-01

    A seismic qualification of a reinforced concrete nuclear materials processing facility using performance based acceptance criteria is presented. Performance goals are defined in terms of a minimum annual seismic failure frequency. Pushover analyses are used to determine the building`s ultimate capacity and relate the capacity to roof drift and joint rotation. Nonlinear dynamic analyses are used to quantify the building`s drift using a suite of ground motion intensities representing varying soil conditions and levels of seismic hazard. A correlation between joint rotation and building drift to damage state is developed from experimental data. The damage state and seismic hazard are convolved to determine annual seismic failure frequency. The results of this rigorous approach is compared to those using equivalent force methods and pushover techniques recommended by ATC-19 and FEMA-273.

  6. Facile fabrication processes for hydrogel-based microfluidic devices made of natural biopolymers

    PubMed Central

    Yajima, Yuya; Yamada, Masumi; Yamada, Emi; Iwase, Masaki; Seki, Minoru

    2014-01-01

    We present facile strategies for the fabrication of two types of microfluidic devices made of hydrogels using the natural biopolymers, alginate, and gelatin as substrates. The processes presented include the molding-based preparation of hydrogel plates and their chemical bonding. To prepare calcium-alginate hydrogel microdevices, we suppressed the volume shrinkage of the alginate solution during gelation using propylene glycol alginate in the precursor solution along with sodium alginate. In addition, a chemical bonding method was developed using a polyelectrolyte membrane of poly-L-lysine as the electrostatic glue. To prepare gelatin-based microdevices, we used microbial transglutaminase to bond hydrogel plates chemically and to cross-link and stabilize the hydrogel matrix. As an application, mammalian cells (fibroblasts and vascular endothelial cells) were cultivated on the microchannel surface to form three-dimensional capillary-embedding tissue models for biological research and tissue engineering. PMID:24803964

  7. Tracking implementation and (un)intended consequences: a process evaluation of an innovative peripheral health facility financing mechanism in Kenya.

    PubMed

    Waweru, Evelyn; Goodman, Catherine; Kedenge, Sarah; Tsofa, Benjamin; Molyneux, Sassy

    2016-03-01

    In many African countries, user fees have failed to achieve intended access and quality of care improvements. Subsequent user fee reduction or elimination policies have often been poorly planned, without alternative sources of income for facilities. We describe early implementation of an innovative national health financing intervention in Kenya; the health sector services fund (HSSF). In HSSF, central funds are credited directly into a facility's bank account quarterly, and facility funds are managed by health facility management committees (HFMCs) including community representatives. HSSF is therefore a finance mechanism with potential to increase access to funds for peripheral facilities, support user fee reduction and improve equity in access. We conducted a process evaluation of HSSF implementation based on a theory of change underpinning the intervention. Methods included interviews at national, district and facility levels, facility record reviews, a structured exit survey and a document review. We found impressive achievements: HSSF funds were reaching facilities; funds were being overseen and used in a way that strengthened transparency and community involvement; and health workers' motivation and patient satisfaction improved. Challenges or unintended outcomes included: complex and centralized accounting requirements undermining efficiency; interactions between HSSF and user fees leading to difficulties in accessing crucial user fee funds; and some relationship problems between key players. Although user fees charged had not increased, national reduction policies were still not being adhered to. Finance mechanisms can have a strong positive impact on peripheral facilities, and HFMCs can play a valuable role in managing facilities. Although fiduciary oversight is essential, mechanisms should allow for local decision-making and ensure that unmanageable paperwork is avoided. There are also limits to what can be achieved with relatively small funds in contexts of enormous need. Process evaluations tracking (un)intended consequences of interventions can contribute to regional financing and decentralization debates. PMID:25920355

  8. Analysis of airborne and waterborne particles around a taconite ore processing facility.

    PubMed

    Axten, Charles W; Foster, David

    2008-10-01

    Since the mid-1970s, samples of airborne and waterborne fibrous particulates have been collected in the area of the Northshore Taconite Ore Processing Facility by the Minnesota Department of Health (MDH), the Minnesota Pollution Control Agency (PCA), and the University of Minnesota. Indirect sample preparation has consistently been used although other aspects of the sampling methods and sites have varied and analytical procedures were altered over time as more accurate and precise microscopy methods were developed (i.e., phase contrast optical microscopy, transmission electron microscopy, transmission electron microscopy with energy dispersive spectroscopy). In the mid-1970s, levels of airborne fibrous particulate in the Silver Bay area averaged from 0.00030 to 0.03 f/ml. This level was significantly greater than levels of similar particulates in the St. Paul, MN area, although two of the Silver Bay sampling sites, considered individually, did not indicate levels of fibrous particulate markedly different than that seen in St. Paul. More recent sampling data (i.e., 1990-2001) indicate mean concentration of airborne fibrous particulates (amphibole-like fibrous particulates) of 0.0020 f/ml with a range of values from 0.0001 to 0.0140 f/ml. Such levels are not significantly different from those seen in other non-urban environments in the US and Europe. Concentrations of fibrous particulates in water samples were higher in the mid-1970 when iron ore tailings were being deposited in Lake Superior, but since the tailings have been deposited on land waterborne levels of fibrous particulate in the Beaver River have remained relatively constant averaging in the range of 7.5 MFL. This level is only slightly in excess of the current EPA drinking water standard for fibrous particulates. Review and consideration of this data is important in determining the potential health risks associated with airborne and waterborne fibrous particulates in the areas of the Northshore Taconite Ore Processing Facility. PMID:18221826

  9. Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

    SciTech Connect

    Moore, L.; Shanteau, C.

    1992-12-01

    This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county's future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

  10. Final report on the public involvement process phase 1, Monitored Retrievable Storage Facility Feasibility Study

    SciTech Connect

    Moore, L.; Shanteau, C.

    1992-12-01

    This report summarizes the pubic involvement component of Phase 1 of the Monitored Retrievable Storage Facility (NM) Feasibility Study in San Juan County, Utah. Part of this summary includes background information on the federal effort to locate a voluntary site for temporary storage of nuclear waste, how San Juan County came to be involved, and a profile of the county. The heart of the report, however, summarizes the activities within the public involvement process, and the issues raised in those various forums. The authors have made every effort to reflect accurately and thoroughly all the concerns and suggestions expressed to us during the five month process. We hope that this report itself is a successful model of partnership with the citizens of the county -- the same kind of partnership the county is seeking to develop with its constituents. Finally, this report offers some suggestions to both county officials and residents alike. These suggestions concern how decision-making about the county`s future can be done by a partnership of informed citizens and listening decision-makers. In the Appendix are materials relating to the public involvement process in San Juan County.

  11. Erosion/corrosion concerns in feed preparation systems at the Defense Waste Processing Facility

    SciTech Connect

    Gee, J.T.; Chandler, C.T.; Daugherty, W.L.; Imrich, K.J.; Jenkins, C.F.

    1997-12-31

    The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950`s to produce nuclear materials in support of the national defense effort. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF) to immobilize the high level radioactive waste resulting from these processes as a durable borosilicate glass. The DWPF, after having undergone extensive testing, has been approved for operations and is currently immobilizing radioactive waste. To ensure reliability of the DWPF remote canyon processing equipment, a materials evaluation program was performed prior to radioactive operations to determine to what extent erosion/corrosion would impact design life of equipment. The program consisted of performing pre-service baseline inspections on critical equipment and follow-up inspections after completion of DWPF cold chemical demonstration runs. Non-destructive examination (NDE) techniques were used to assess erosion/corrosion as well as evaluation of corrosion coupon racks. These results were used to arrive at predicted equipment life for selected feed preparation equipment. It was concluded with the exception of the coil and agitator for the slurry mix evaporator (SME), which are exposed to erosive glass frit particles, all of the equipment should meet its design life.

  12. A Guide for Developing Standard Operating Job Procedures for the Sludge Conditioning & Dewatering Process Wastewater Treatment Facility. SOJP No. 11.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the sludge conditioning and dewatering process of wastewater treatment facilities. In this process, sludge is treated with chemicals to make the sludge coagulate and give up its water more easily. The treated sludge is then dewatered using a vacuum filter. The guide gives step-by-step…

  13. A Guide for Developing Standard Operating Job Procedures for the Sludge Conditioning & Dewatering Process Wastewater Treatment Facility. SOJP No. 11.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the sludge conditioning and dewatering process of wastewater treatment facilities. In this process, sludge is treated with chemicals to make the sludge coagulate and give up its water more easily. The treated sludge is then dewatered using a vacuum filter. The guide gives step-by-step

  14. A Guide for Developing Standard Operating Job Procedures for the Digestion Process Wastewater Treatment Facility. SOJP No. 10.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the digestion process of wastewater treatment facilities. This process is for reducing the volume of sludge to be treated in subsequent units and to reduce the volatile content of sludge. The guide gives step-by-step instructions for pre-startup, startup, continuous operating, shutdown,

  15. 40 CFR 60.5400 - What equipment leak standards apply to affected facilities at an onshore natural gas processing...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... affected facilities at an onshore natural gas processing plant? 60.5400 Section 60.5400 Protection of... NEW STATIONARY SOURCES Standards of Performance for Crude Oil and Natural Gas Production, Transmission... natural gas processing plant? This section applies to the group of all equipment, except...

  16. 40 CFR 60.5400 - What equipment leak standards apply to affected facilities at an onshore natural gas processing...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... affected facilities at an onshore natural gas processing plant? 60.5400 Section 60.5400 Protection of... NEW STATIONARY SOURCES Standards of Performance for Crude Oil and Natural Gas Production, Transmission... natural gas processing plant? This section applies to the group of all equipment, except...

  17. 30 CFR 910.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 910.827 Section 910.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... § 910.827 Special performance standards—coal processing plants and support facilities not located at...

  18. 30 CFR 947.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 947.827 Section 947.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... § 947.827 Special performance standards—coal processing plants and support facilities not located at...

  19. 30 CFR 939.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 939.827 Section 939.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... ISLAND § 939.827 Special performance standards—coal processing plants and support facilities not...

  20. 30 CFR 912.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 912.827 Section 912.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... § 912.827 Special performance standards—coal processing plants and support facilities not located at...

  1. 30 CFR 937.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 937.827 Section 937.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... § 937.827 Special performance standards—coal processing plants and support facilities not located at...

  2. 30 CFR 933.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 933.827 Section 933.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... CAROLINA § 933.827 Special performance standards—coal processing plants and support facilities not...

  3. 30 CFR 922.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 922.827 Section 922.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... § 922.827 Special performance standards—coal processing plants and support facilities not located at...

  4. 30 CFR 941.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 941.827 Section 941.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... DAKOTA § 941.827 Special performance standards—coal processing plants and support facilities not...

  5. 30 CFR 921.827 - Special performance standards-coal processing plants and support facilities not located at or...

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Special performance standards-coal processing... mine. 921.827 Section 921.827 Mineral Resources OFFICE OF SURFACE MINING RECLAMATION AND ENFORCEMENT... MASSACHUSETTS § 921.827 Special performance standards—coal processing plants and support facilities not...

  6. A Guide for Developing Standard Operating Job Procedures for the Digestion Process Wastewater Treatment Facility. SOJP No. 10.

    ERIC Educational Resources Information Center

    Schwing, Carl M.

    This guide describes standard operating job procedures for the digestion process of wastewater treatment facilities. This process is for reducing the volume of sludge to be treated in subsequent units and to reduce the volatile content of sludge. The guide gives step-by-step instructions for pre-startup, startup, continuous operating, shutdown,…

  7. Tracking implementation and (un)intended consequences: a process evaluation of an innovative peripheral health facility financing mechanism in Kenya

    PubMed Central

    Waweru, Evelyn; Goodman, Catherine; Kedenge, Sarah; Tsofa, Benjamin; Molyneux, Sassy

    2016-01-01

    In many African countries, user fees have failed to achieve intended access and quality of care improvements. Subsequent user fee reduction or elimination policies have often been poorly planned, without alternative sources of income for facilities. We describe early implementation of an innovative national health financing intervention in Kenya; the health sector services fund (HSSF). In HSSF, central funds are credited directly into a facility’s bank account quarterly, and facility funds are managed by health facility management committees (HFMCs) including community representatives. HSSF is therefore a finance mechanism with potential to increase access to funds for peripheral facilities, support user fee reduction and improve equity in access. We conducted a process evaluation of HSSF implementation based on a theory of change underpinning the intervention. Methods included interviews at national, district and facility levels, facility record reviews, a structured exit survey and a document review. We found impressive achievements: HSSF funds were reaching facilities; funds were being overseen and used in a way that strengthened transparency and community involvement; and health workers’ motivation and patient satisfaction improved. Challenges or unintended outcomes included: complex and centralized accounting requirements undermining efficiency; interactions between HSSF and user fees leading to difficulties in accessing crucial user fee funds; and some relationship problems between key players. Although user fees charged had not increased, national reduction policies were still not being adhered to. Finance mechanisms can have a strong positive impact on peripheral facilities, and HFMCs can play a valuable role in managing facilities. Although fiduciary oversight is essential, mechanisms should allow for local decision-making and ensure that unmanageable paperwork is avoided. There are also limits to what can be achieved with relatively small funds in contexts of enormous need. Process evaluations tracking (un)intended consequences of interventions can contribute to regional financing and decentralization debates. PMID:25920355

  8. ANION ANALYSES BY ION CHROMATOGRAPHY FOR THE ALTERNATE REDUCTANT DEMONSTRATION FOR THE DEFENSE WASTE PROCESSING FACILITY

    SciTech Connect

    Best, D.

    2010-08-04

    The Process Science Analytical Laboratory (PSAL) at the Savannah River National Laboratory was requested by the Defense Waste Processing Facility (DWPF) to develop and demonstrate an Ion Chromatography (IC) method for the analysis of glycolate, in addition to eight other anions (fluoride, formate, chloride, nitrite, nitrate, sulfate, oxalate and phosphate) in Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) samples. The method will be used to analyze anions for samples generated from the Alternate Reductant Demonstrations to be performed for the DWPF at the Aiken County Technology Laboratory (ACTL). The method is specific to the characterization of anions in the simulant flowsheet work. Additional work will be needed for the analyses of anions in radiological samples by Analytical Development (AD) and DWPF. The documentation of the development and demonstration of the method fulfills the third requirement in the TTQAP, SRNL-RP-2010-00105, 'Task Technical and Quality Assurance Plan for Glycolic-Formic Acid Flowsheet Development, Definition and Demonstrations Tasks 1-3'.

  9. Advanced Distributed Measurements and Data Processing at the Vibro-Acoustic Test Facility, GRC Space Power Facility, Sandusky, Ohio - an Architecture and an Example

    NASA Technical Reports Server (NTRS)

    Hill, Gerald M.; Evans, Richard K.

    2009-01-01

    A large-scale, distributed, high-speed data acquisition system (HSDAS) is currently being installed at the Space Power Facility (SPF) at NASA Glenn Research Center s Plum Brook Station in Sandusky, OH. This installation is being done as part of a facility construction project to add Vibro-acoustic Test Capabilities (VTC) to the current thermal-vacuum testing capability of SPF in support of the Orion Project s requirement for Space Environments Testing (SET). The HSDAS architecture is a modular design, which utilizes fully-remotely managed components, enables the system to support multiple test locations with a wide-range of measurement types and a very large system channel count. The architecture of the system is presented along with details on system scalability and measurement verification. In addition, the ability of the system to automate many of its processes such as measurement verification and measurement system analysis is also discussed.

  10. VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 6 QUALIFICATION SAMPLE

    SciTech Connect

    Click, D.; Jones, M.; Edwards, T.

    2010-06-09

    For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) confirms 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.1 DWPF SRAT samples are typically dissolved using a room temperature HF-HNO3 acid dissolution (i.e., DWPF Cold Chem (CC) Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICPAES). In addition to the CC method confirmation, the DWPF lab's mercury (Hg) digestion method was also evaluated for applicability to SB6 (see DWPF procedure 'Mercury System Operating Manual', Manual: SW4-15.204. Section 6.1, Revision 5, Effective date: 12-04-03). 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 digestion of Sludge Batch 6 (SB6) SRAT Receipt and SB6 SRAT Product samples. For validation of the DWPF lab's Hg method, only SRAT receipt material was used and compared to AR digestion results. The SB6 SRAT Receipt and SB6 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB6 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 5 (SB5), to form the SB6 Blend composition. In addition to the 16 elements currently measured by the DWPF, this report includes Hg and thorium (Th) data (Th comprising {approx}2.5 - 3 Wt% of the total solids in SRAT Receipt and SRAT Product, respectively) and provides specific details of ICP-AES analysis of Th. Thorium was found to interfere with the U 367.007 nm emission line, and an inter-element correction (IEC) had to be applied to U data, which is also discussed. The results for any one particular element should not be used in any way to identify the form or speciation of a particular element without support from XRD analysis or used to estimate ratios of compounds in the sludge.

  11. L. monocytogenes in a cheese processing facility: Learning from contamination scenarios over three years of sampling.

    PubMed

    Rckerl, I; Muhterem-Uyar, M; Muri-Klinger, S; Wagner, K-H; Wagner, M; Stessl, B

    2014-10-17

    The aim of this study was to analyze the changing patterns of Listeria monocytogenes contamination in a cheese processing facility manufacturing a wide range of ready-to-eat products. Characterization of L. monocytogenes isolates included genotyping by pulsed-field gel electrophoresis (PFGE) and multi-locus sequence typing (MLST). Disinfectant-susceptibility tests and the assessment of L. monocytogenes survival in fresh cheese were also conducted. During the sampling period between 2010 and 2013, a total of 1284 environmental samples were investigated. Overall occurrence rates of Listeria spp. and L. monocytogenes were 21.9% and 19.5%, respectively. Identical L. monocytogenes genotypes were found in the food processing environment (FPE), raw materials and in products. Interventions after the sampling events changed contamination scenarios substantially. The high diversity of globally, widely distributed L. monocytogenes genotypes was reduced by identifying the major sources of contamination. Although susceptible to a broad range of disinfectants and cleaners, one dominant L. monocytogenes sequence type (ST) 5 could not be eradicated from drains and floors. Significantly, intense humidity and steam could be observed in all rooms and water residues were visible on floors due to increased cleaning strategies. This could explain the high L. monocytogenes contamination of the FPE (drains, shoes and floors) throughout the study (15.8%). The outcome of a challenge experiment in fresh cheese showed that L. monocytogenes could survive after 14days of storage at insufficient cooling temperatures (8 and 16C). All efforts to reduce L. monocytogenes environmental contamination eventually led to a transition from dynamic to stable contamination scenarios. Consequently, implementation of systematic environmental monitoring via in-house systems should either aim for total avoidance of FPE colonization, or emphasize a first reduction of L. monocytogenes to sites where contamination of the processed product is unlikely. Drying of surfaces after cleaning is highly recommended to facilitate the L. monocytogenes eradication. PMID:25136788

  12. Implementing comprehensive de-licensing process for the West Jefferson North Facility

    SciTech Connect

    Anderson, Keith

    2007-07-01

    Available in abstract form only. Full text of publication follows: Implementation of the comprehensive de-licensing process for the West Jefferson North (WJN) facility was documented through the Final Certification of Completion. The Final Certification of Completion summarizes the performance and results of the final status surveys of the affected and unaffected areas of the West Jefferson North (WJN) site as part of the completion of the Columbus Closure Project (CCP). Final status survey processes adhered to the requirements of the 'Radiological Characterization and Final Status Plan for Battelle Columbus Laboratories Decommissioning Project, West Jefferson Site' DD-97-02, Rev. 0 (hereinafter DD-97-02), as reflecting the requirements of draft NUREG 5849. Surveys were performed throughout the decommissioning and remediation activities performed at the WJN and documented in Final Status Survey Reports (FSSR). Throughout the project, the CCP activity engaged the oversight of the US Department of Energy (DOE), the Battelle Memorial Institute (BMI), and the Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE). The ESSAP of the ORISE fulfilled the Independent Verification Contractor (IVC) role for the CCP under contract to the Oak Ridge Office of the DOE. The US Nuclear Regulatory Commission (NRC) also performed independent review of the in-process final status surveys. The FSSR, in conjunction with the IVC Letter Reports and the NRC inspection reports, document that the endpoint criteria objectives of the NRC-approved Decommissioning Plan have been met for WJN site as covered by the CCP. (author)

  13. The high moisture western coal processing system at the UTSI-DOE Coal Fired Flow Facility. Topical report

    SciTech Connect

    Sanders, M.E.

    1996-02-01

    The original eastern coal processing system at the Department of Energy`s Coal Fired Flow Facility (CFFF), located at the University of Tennessee Space Institute in Tullahoma, Tennessee, was modified to pulverize and dry Montana Rosebud, a western coal. Significant modifications to the CFFF coal processing system were required and the equipment selection criteria are reviewed. Coal processing system performance parameters are discussed. A summary of tests conducted and significant events are included.

  14. Qualification of the Nippon Instrumentation for use in Measuring Mercury at the Defense Waste Processing Facility

    SciTech Connect

    Edwards, T.; Mahannah, R.

    2011-07-05

    The Nippon Mercury/RA-3000 system installed in 221-S M-14 has been qualified for use. The qualification was a side-by-side comparison of the Nippon Mercury/RA-3000 system with the currently used Bacharach Mercury Analyzer. The side-by-side testing included standards for instrument calibration verifications, spiked samples and unspiked samples. The standards were traceable back to the National Institute of Standards and Technology (NIST). The side-by-side work included the analysis of Sludge Receipt and Adjustment Tank (SRAT) Receipt, SRAT Product, and Slurry Mix Evaporator (SME) samples. With the qualification of the Nippon Mercury/RA-3000 system in M-14, the DWPF lab will be able to perform a head to head comparison of a second Nippon Mercury/RA-3000 system once the system is installed. The Defense Waste Processing Facility (DWPF) analyzes receipt and product samples from the Sludge Receipt and Adjustment Tank (SRAT) to determine the mercury (Hg) concentration in the sludge slurry. The SRAT receipt is typically sampled and analyzed for the first ten SRAT batches of a new sludge batch to obtain an average Hg concentration. This average Hg concentration is then used to determine the amount of steam stripping required during the concentration/reflux step of the SRAT cycle to achieve a less than 0.6 wt% Hg in the SRAT product solids. After processing is complete, the SRAT product is sampled and analyzed for mercury to ensure that the mercury concentration does not exceed the 0.45 wt% limit in the Slurry Mix Evaporator (SME). The DWPF Laboratory utilizes Bacharach Analyzers to support these Hg analyses at this facility. These analyzers are more than 10 years old, and they are no longer supported by the manufacturer. Due to these difficulties, the Bacharach Analyzers are to be replaced by new Nippon Mercury/RA-3000 systems. DWPF issued a Technical Task Request (TTR) for the Savannah River National Laboratory (SRNL) to assist in the qualification of the new systems. SRNL prepared a task technical and quality assurance (TT&QA) plan that outlined the activities that are necessary and sufficient to meet the objectives of the TTR. In addition, TT&QA plan also included a test plan that provided guidance to the DWPF Lab in collecting the data needed to qualify the new Nippon Mercury/RA-3000 systems.

  15. Microgravity and Materials Processing Facility study (MMPF): Requirements and Analyses of Commercial Operations (RACO) preliminary data release

    NASA Technical Reports Server (NTRS)

    1988-01-01

    This requirements and analyses of commercial operations (RACO) study data release reflects the current status of research activities of the Microgravity and Materials Processing Facility under Modification No. 21 to NASA/MSFC Contract NAS8-36122. Section 1 includes 65 commercial space processing projects suitable for deployment aboard the Space Station. Section 2 contains reports of the R:BASE (TM) electronic data base being used in the study, synopses of the experiments, and a summary of data on the experimental facilities. Section 3 is a discussion of video and data compression techniques used as well as a mission timeline analysis.

  16. Sources and potential application of waste heat utilization at a gas processing facility

    NASA Astrophysics Data System (ADS)

    Alshehhi, Alyas Ali

    Waste heat recovery (WHR) has the potential to significantly improve the efficiency of oil and gas plants, chemical and other processing facilities, and reduce their environmental impact. In this Thesis a comprehensive energy audit at Abu Dhabi Gas Industries Ltd. (GASCO) ASAB gas processing facilities is undertaken to identify sources of waste heat and evaluate their potential for on-site recovery. Two plants are considered, namely ASAB0 and ASAB1. Waste heat evaluation criteria include waste heat grade (i.e., temperature), rate, accessibility (i.e., proximity) to potential on-site waste heat recovery applications, and potential impact of recovery on installation performance and safety. The operating parameters of key waste heat source producing equipment are compiled, as well as characteristics of the waste heat streams. In addition, potential waste heat recovery applications and strategies are proposed, focusing on utilities, i.e., enhancement of process cooling/heating, electrical/mechanical power generation, and steam production. The sources of waste heat identified at ASAB facilities consist of gas turbine and gas generator exhaust gases, flared gases, excess propane cooling capacity, excess process steam, process gas air-cooler heat dissipation, furnace exhaust gases and steam turbine outlet steam. Of the above waste heat sources, exhaust gases from five gas turbines and one gas generator at ASAB0 plant, as well as from four gas turbines at ASAB1 plant, were found to meet the rate (i.e., > 1 MW), grade (i.e., > 180°C), accessibility (i.e., < 50 m from potential on-site WHR applications) and minimal impact criteria on the performance and safety of existing installations, for potential waste heat recovery. The total amount of waste heat meeting these criteria were estimated at 256 MW and 289 MW at ASAB0 and ASAB1 plants, respectively, both of which are substantial. Of the 289 MW waste generated at ASAB1, approximately 173 MW are recovered by waste heat recovery steam generators (WHRSGs), leaving 116 MW unutilized. The following strategies were developed to recover the above waste heat. At ASAB0, it is proposed that exhaust gases from all five gas turbines be used to power a WHRSG. The steam generated by the WHRSG would both i) drive an absorption refrigeration unit for gas turbine inlet air cooling, which would result in additional electric or mechanical power generation, and pre-cooling of process gas, which could reduce the need for or eliminate air coolers, as well as reduce propane chiller load, and ii) serve for heating of lean gas, which would reduce furnace load. At ASAB1, it is proposed that exhaust gases from all four gas turbines be used to generate steam in WHRSG that would drive an absorption refrigeration unit for either gas turbine inlet air cooling for additional electric or mechanical power generation, or pre-cooling of process gas to eliminate air-coolers and reduce propane chiller cooling load. Considering the smaller amount of waste heat available at ASAB1 (116 MW) relative to ASAB0 (237 MW), these above two recovery options could not be implemented simultaneously at ASAB0. To permit the detailed design and techno-economic feasibility evaluation of the proposed waste heat recovery strategies in a subsequent study, the cooling loads and associated electric power consumption of ASAB0 process gas air-coolers were estimated at 21 MW and 1.9 MW, respectively, and 67 MW and 2.2 MW, respectively for ASAB1 plant. In addition, the heating loads and fuel consumption of ASAB0 furnaces used for lean gas re-generation were estimated at 24 MW and 0.0653 MMSCMD, respectively. In modeling work undertaken in parallel with this study at the Petroleum Institute, the waste heat recovery strategies proposed here were found to be thermodynamically and economically feasible, and to lead to substantial energy and cost savings, hence environmental benefits.

  17. Qualification of a Carbon Analyzer to Support the Defense Waste Processing Facility

    SciTech Connect

    Edwards, T.; Feller, M.

    2011-07-05

    The I-O Model 1030 carbon analyzer has been qualified for use at the Defense Waste Processing Facility (DWPF). The qualification was a side-by-side comparison of the Model 1030 system with the currently used Model 1010 Analyzer. This recommendation is based on side-by-side comparisons of the new unit to the currently used Model 1010 analyzer that are presented in this report. The side-by-side testing included standards and process samples. The standards, which were used for instrument calibration verifications in the measurement of total inorganic carbon (TIC) and of total organic carbon (TOC), were traceable back to the National Institute of Standards and Technology. The process samples included TIC analyses of Sludge Receipt and Adjustment Tank samples and TOC analyses for Slurry Mix Evaporator (SME) samples. After the Model 1030 has been used for production reporting, DWPF should consider an investigation into the uncertainties associated with the TOC measurements to determine how far below the 18,916 ppm limit DWPF must control the average of the measurements for a set of SME samples to account for the uncertainties of the measurements from this new analyzer. Based upon the results presented in this report, it is recommended that the Model 1030 carbon analyzer is qualified for use. This recommendation is based on side-by-side comparisons of the new unit to the currently used Model 1010 analyzer that are presented in this report. The side-by-side testing included standards for instrument calibration verifications for TIC and TOC, and process samples. The standards were traceable back to NIST. The process samples included TIC analyses of SRAT Receipt samples and TOC analyses for SME samples. At some point in the future, after the Model 1030 has been used for production reporting, DWPF should consider an investigation into the uncertainties associated with the TOC measurements to determine how far below the 18,916 ppm limit DWPF must control the average of the measurements for a set of SME samples to account for the uncertainties of the measurements from this new analyzer.

  18. Conceptual design for the Waste Receiving and Processing facility Module 2A. Conceptual Design Report: Volume 1

    SciTech Connect

    Not Available

    1992-07-01

    This is a Conceptual Design Report (CDR) for the Waste Receiving and Processing (WRAP) Module 2A facility at Hanford Reservation. The mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities those contact handled (CH) low-level radioactive mixed wastes (LLMW) that: (1) are currently in retrievable storage at the Hanford Central Waste Complex (HCWC) awaiting a treatment capability to permit permanent disposal compliant with the Land Disposal Restrictions and; (2) are forecasted to be generated over the next 30 years. The primary sources of waste to be treated at WRAP Module 2A include the currently stored waste from the 183-H solar basin evaporators, secondary solids from the future Hanford site liquid effluent treatment facilities, thermal treatment facility ash, other WRAP modules, and other, miscellaneous waste from storage and onsite/offsite waste generators consisting of compactible and non-compactible solids, contaminated soils, and metals. This volume, Volume 1 provides a narrative of the project background, objective and justification. A description of the WRAP 2A mission, operations and project scope is also included. Significant project requirements such as security, health, safety, decontamination and decomissioning, maintenance, data processing, and quality are outlined. Environmental compliance issues and regulatory permits are identified, and a preliminary safety evaluation is provided.

  19. Product/Process (P/P) Models For The Defense Waste Processing Facility (DWPF): Model Ranges And Validation Ranges For Future Processing

    SciTech Connect

    Jantzen, C.; Edwards, T.

    2015-09-25

    Radioactive high level waste (HLW) at the Savannah River Site (SRS) has successfully been vitrified into borosilicate glass in the Defense Waste Processing Facility (DWPF) since 1996. Vitrification requires stringent product/process (P/P) constraints since the glass cannot be reworked once it is poured into ten foot tall by two foot diameter canisters. A unique “feed forward” statistical process control (SPC) was developed for this control rather than statistical quality control (SQC). In SPC, the feed composition to the DWPF melter is controlled prior to vitrification. In SQC, the glass product would be sampled after it is vitrified. Individual glass property-composition models form the basis for the “feed forward” SPC. The models transform constraints on the melt and glass properties into constraints on the feed composition going to the melter in order to guarantee, at the 95% confidence level, that the feed will be processable and that the durability of the resulting waste form will be acceptable to a geologic repository.

  20. DWPF (Defense Waste Processing Facility) canister impact testing and analyses for the Transportation Technology Center

    SciTech Connect

    Farnsworth, R.K.; Mishima, J.

    1988-12-01

    A legal weight truck cask design has been developed for the US Department of Energy by GA Technologies, Inc. The cask will be used to transport defense high-level waste canisters produced by the Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The development of the cask required the collection of impact data for the DWPF canisters. The Materials Characterization Center (MCC) performed this work under the guidance of the Transportation Technology Center (TTC) at Sandia National Laboratories. Two full-scale DWPF canisters filled with nonradioactive borosilicate glass were impacted under ''normal'' and ''hypothetical'' accident conditions. Two canisters, supplied by the DWPF, were tested. Each canister was vertically dropped on the bottom end from a height of either 0.3 m or 9.1 m (for normal or hypothetical accident conditions, respectively). The structural integrity of each canister was then examined using helium leak and dye penetrant testing. The canisters' diameters and heights, which had been previously measured, were then remeasured to determine how the canister dimensions had changed. Following structural integrity testing, the canisters were flaw leak tested. For transportation flaw leak testing, four holes were fabricated into the shell of canister A-27 (0.3 m drop height). The canister was then transported a total distance of 2069 miles. During transport, the waste form material that fell from each flaw was collected to determine the amount of size distribution of each flaw release. 2 refs., 8 figs., 12 tabs.

  1. CHARACTERIZATION OF A PRECIPITATE REACTOR FEED TANK (PRFT) SAMPLE FROM THE DEFENSE WASTE PROCESSING FACILITY (DWPF)

    SciTech Connect

    Crawford, C.; Bannochie, C.

    2014-05-12

    A sample of from the Defense Waste Processing Facility (DWPF) Precipitate Reactor Feed Tank (PRFT) was pulled and sent to the Savannah River National Laboratory (SRNL) in June of 2013. The PRFT in DWPF receives Actinide Removal Process (ARP)/ Monosodium Titanate (MST) material from the 512-S Facility via the 511-S Facility. This 2.2 L sample was to be used in small-scale DWPF chemical process cell testing in the Shielded Cells Facility of SRNL. A 1L sub-sample portion was characterized to determine the physical properties such as weight percent solids, density, particle size distribution and crystalline phase identification. Further chemical analysis of the PRFT filtrate and dissolved slurry included metals and anions as well as carbon and base analysis. This technical report describes the characterization and analysis of the PRFT sample from DWPF. At SRNL, the 2.2 L PRFT sample was composited from eleven separate samples received from DWPF. The visible solids were observed to be relatively quick settling which allowed for the rinsing of the original shipping vials with PRFT supernate on the same day as compositing. Most analyses were performed in triplicate except for particle size distribution (PSD), X-ray diffraction (XRD), Scanning Electron Microscopy (SEM) and thermogravimetric analysis (TGA). PRFT slurry samples were dissolved using a mixed HNO3/HF acid for subsequent Inductively Coupled Plasma Atomic Emission Spectroscopy (ICPAES) and Inductively Coupled Plasma Mass Spectroscopy (ICP-MS) analyses performed by SRNL Analytical Development (AD). Per the task request for this work, analysis of the PRFT slurry and filtrate for metals, anions, carbon and base were primarily performed to support the planned chemical process cell testing and to provide additional component concentrations in addition to the limited data available from DWPF. Analysis of the insoluble solids portion of the PRFT slurry was aimed at detailed characterization of these solids (TGA, PSD, XRD and SEM) in support of the Salt IPT chemistry team. The overall conclusions from analyses performed in this study are that the PRFT slurry consists of 0.61 Wt.% insoluble MST solids suspended in a 0.77 M [Na+] caustic solution containing various anions such as nitrate, nitrite, sulfate, carbonate and oxalate. The corresponding measured sulfur level in the PRFT slurry, a critical element for determining how much of the PRFT slurry gets blended into the SRAT, is 0.437 Wt.% TS. The PRFT slurry does not contain insoluble oxalates nor significant quantities of high activity sludge solids. The lack of sludge solids has been alluded to by the Salt IPT chemistry team in citing that the mixing pump has been removed from Tank 49H, the feed tank to ARP-MCU, thus allowing the sludge solids to settle out.  The PRFT aqueous slurry from DWPF was found to contain 5.96 Wt.% total dried solids. Of these total dried solids, relatively low levels of insoluble solids (0.61 Wt.%) were measured. The densities of both the filtrate and slurry were 1.05 g/mL.  Particle size distribution of the PRFT solids in filtered caustic simulant and XRD analysis of washed/dried PRFT solids indicate that the PRFT slurry contains a bimodal distribution of particles in the range of 1 and 6 μm and that the particles contain sodium titanium oxide hydroxide Na2Ti2O4(OH)2 crystalline material as determined by XRD. These data are in excellent agreement with similar data obtained from laboratory sampling of vendor supplied MST. Scanning Electron Microscopy (SEM) combined with Energy Dispersive X-ray Spectroscopy (EDS) analysis of washed/dried PRFT solids shows the particles to be like previous MST analyses consisting of irregular shaped micron-sized solids consisting primarily of Na and Ti.  Thermogravimetric analysis of the washed and unwashed PRFT solids shows that the washed solids are very similar to MST solids. The TGA mass loss signal for the unwashed solids shows similar features to TGA performed on cellulose nitrate filter paper indicating significant presence of the deteriorated filter in this unwashed sample. Neither the washed nor unwashed PRFT solids TGA traces showed any features that would indicate presence of sodium oxalate solids.  The PRFT Filtrate elemental analysis shows that Na, S and Al are major soluble species with trace levels of B, Cr, Cu, K, Li, Si, Tc, Th and U present. Nitrate, nitrite, sulfate, oxalate, carbonate and hydroxide are major soluble anion species. There is good agreement between the analyzed TOC and the total carbon calculated from the sum of oxalate and minor species formate.  Comparison of the amount and speciation of the carbon species between filtrate and slurry indicates no significant carbon-containing species, e.g., sodium oxalate, are present in the slurry solids.  Dissolution of the PRFT slurry and subsequent analysis shows that Na, Ti, Si and U are the major elements present on a Wt.% total dried solids basis with 30, 5.8 and 0.47 and 0.11 Wt.% total dried solids, respectively. The amount of Al in the dissolved PRFT slurry is less than that calculated from the PRFT filtrate alone which suggests that the mixed acid digestion used in this work is not optimized for Al recovery. The concentrations of Ca, Fe, Hg and U are all low (at or below 0.11 wt%) and there is no detectable Mn or Ni present which indicates no significant HLW sludge solids are present in the PRFT slurry sample.

  2. Bioassay testing of simulated effluent from the Defense Waste Processing Facility

    SciTech Connect

    Fliermans, C.B.

    1984-12-11

    Static acute bioassay tests were used to investigate the effect of the proposed effluent from the Defense Waste Processing Facility on juvenile bluegill sunfish, Lepomis macrochirus, and the lower food chain microorganisms present in Four Mile Creek. The simulated effluent contained NaNO/sub 3/ (25 mg/L), NaMnO (0.4 mg/L), NaCHO/sub 2/ (30 mg/L), Na/sub 2/C/sub 2/O/sub 4/ (20 mg/L) and WRICO ZC-830 (150 mg/L). The 96 hour acute toxicity testing for the bluegill sunfish indicated no toxicity for any of the tested concentrations more than 10 times the expected levels to be discharged into Four Mile Creek. These findings were consistent for all the pH values tested and regardless of the presence or absence of WRICO ZC-830. The bacterial studies indicated that the projected effluent would be toxic when the effluent reached concentrations twice that which has been projected or when the NaCHO/sub 2/ reaches 10X above the expected discharge levels. 1 ref., 28 tabs.

  3. Reconnaissance hydrogeologic investigation of the Defense Waste Processing Facility and Vicinity, Savannah River Plant, South Carolina

    SciTech Connect

    Dennehy, K.F.; Prowell, D.C.; McMahon, P.B.

    1989-01-01

    The purposes of this report are two-fold: (1) to define the hydrogeologic conditions in the vicinity of the defense waste processing facility (DWPF) and, (2) to evaluate the potential for movement of a concentrated salt-solution waste if released at or near the DWPF. These purposes were accomplished by assembling and evaluating existing hydrogeologic data; collecting additional geologic, hydrologic, and water-quality data; developing a local geologic framework; developing a conceptual model of the local ground-water flow system; and by performing laboratory experiments to determine the mobility of salt-solution waste in surface and near-surface sediments. Although the unconsolidated sediments are about 1000 ft thick in the study area, only the Tertiary age sediments, or upper 300 ft are discussed in this report. The top of the Ellenton Formation acts as the major confining unit between the overlying aquifers in Tertiary sediments and the underlying aquifers in Cretaceous sediments; therefore, the Ellenton Formation is the vertical limit of our hydrogeologic investigation. The majority of the hydrologic data for this study come from monitoring wells at the saltstone disposal site (SDS) in Z Area (fig. 3). No recent water-level data were collected in S Area owing to the removal of S Area monitoring wells prior to construction at the DWPF. 46 refs., 26 figs., 7 tabs.

  4. The Role of Educators in Educational Facilities Planning: A Case Study of the Planning Process.

    ERIC Educational Resources Information Center

    Neylon, Terrance Bernard

    This case study explores the role of educators in educational facilities planning and construction and discusses the different agendas and perspectives people bring to the development of educational facility specifications. It describes how cooperation and input among stakeholders resulted in a Massachusetts community college was built in 18…

  5. CONTAMINATED PROCESS EQUIPMENT REMOVAL FOR THE D&D OF THE 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINISHING PLANT (PFP)

    SciTech Connect

    HOPKINS, A.M.; MINETTE, M.J.; KLOS, D.B.

    2007-01-25

    This paper describes the unique challenges encountered and subsequent resolutions to accomplish the deactivation and decontamination of a plutonium ash contaminated building. The 232-Z Contaminated Waste Recovery Process Facility at the Plutonium Finishing Plant was used to recover plutonium from process wastes such as rags, gloves, containers and other items by incinerating the items and dissolving the resulting ash. The incineration process resulted in a light-weight plutonium ash residue that was highly mobile in air. This light-weight ash coated the incinerator's process equipment, which included gloveboxes, blowers, filters, furnaces, ducts, and filter boxes. Significant airborne contamination (over 1 million derived air concentration hours [DAC]) was found in the scrubber cell of the facility. Over 1300 grams of plutonium held up in the process equipment and attached to the walls had to be removed, packaged and disposed. This ash had to be removed before demolition of the building could take place.

  6. GIS analysis of the siting criteria for the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility

    SciTech Connect

    Hoskinson, R.L.

    1994-01-01

    This report summarizes a study conducted using the Arc/Info{reg_sign} geographic information system (GIS) to analyze the criteria used for site selection for the Mixed and Low-Level Waste Treatment Facility (MLLWTF) and the Idaho Waste Processing Facility (IWPF). The purpose of the analyses was to determine, based on predefined criteria, the areas on the INEL that best satisfied the criteria. The coverages used in this study were produced by importing the AutoCAD files that produced the maps for a pre site selection draft report into the GIS. The files were then converted to Arc/Info{reg_sign} GIS format. The initial analysis was made by considering all of the criteria as having equal importance in determining the areas of the INEL that would best satisfy the requirements. Another analysis emphasized four of the criteria as ``must`` criteria which had to be satisfied. Additional analyses considered other criteria that were considered for, but not included in the predefined criteria. This GIS analysis of the siting criteria for the IWPF and MLLWTF provides a logical, repeatable, and defensible approach to the determination of candidate locations for the facilities. The results of the analyses support the location of the Candidate Locations.

  7. Uranium Exposures in a Community near a Uranium Processing Facility: Relationship with Hypertension and Hematologic Markers

    PubMed Central

    Wagner, Sara E.; Burch, James B.; Bottai, Matteo; Pinney, Susan M.; Puett, Robin; Porter, Dwayne; Vena, John E.; Hbert, James R.

    2010-01-01

    Background Environmental uranium exposure originating as a byproduct of uranium processing can impact human health. The Fernald Feed Materials Production Center functioned as a uranium processing facility from 1951 to 1989, and potential health effects among residents living near this plant were investigated via the Fernald Medical Monitoring Program (FMMP). Methods Data from 8,216 adult FMMP participants were used to test the hypothesis that elevated uranium exposure was associated with indicators of hypertension or changes in hematologic parameters at entry into the program. A cumulative uranium exposure estimate, developed by FMMP investigators, was used to classify exposure. Systolic and diastolic blood pressure and physician diagnoses were used to assess hypertension; and red blood cells, platelets, and white blood cell differential counts were used to characterize hematology. The relationship between uranium exposure and hypertension or hematologic parameters was evaluated using generalized linear models and quantile regression for continuous outcomes, and logistic regression or ordinal logistic regression for categorical outcomes, after adjustment for potential confounding factors. Results Of 8,216 adult FMMP participants 4,187 (51%) had low cumulative uranium exposure, 1,273 (15%) had moderate exposure, and 2,756 (34%) were in the high (>0.50 Sievert) cumulative lifetime uranium exposure category. Participants with elevated uranium exposure had decreased white blood cell and lymphocyte counts and increased eosinophil counts. Female participants with higher uranium exposures had elevated systolic blood pressure compared to women with lower exposures. However, no exposure-related changes were observed in diastolic blood pressure or hypertension diagnoses among female or male participants. Conclusions Results from this investigation suggest that residents in the vicinity of the Fernald plant with elevated exposure to uranium primarily via inhalation exhibited decreases in white blood cell counts, and small, though statistically significant, gender-specific alterations in systolic blood pressure at entry into the FMMP. PMID:20889151

  8. Hypertension and hematologic parameters in a community near a uranium processing facility

    SciTech Connect

    Wagner, Sara E.; Burch, James B.; South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC; WJB Dorn Veteran's Affairs Medical Center, Columbia, SC ; Bottai, Matteo; Pinney, Susan M.; Puett, Robin; South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC; Arnold School of Public Health, Department of Environmental Health Sciences, University of South Carolina, Columbia, SC ; Porter, Dwayne; Vena, John E.; Hebert, James R.; South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC

    2010-11-15

    Background: Environmental uranium exposure originating as a byproduct of uranium processing can impact human health. The Fernald Feed Materials Production Center functioned as a uranium processing facility from 1951 to 1989, and potential health effects among residents living near this plant were investigated via the Fernald Medical Monitoring Program (FMMP). Methods: Data from 8216 adult FMMP participants were used to test the hypothesis that elevated uranium exposure was associated with indicators of hypertension or changes in hematologic parameters at entry into the program. A cumulative uranium exposure estimate, developed by FMMP investigators, was used to classify exposure. Systolic and diastolic blood pressure and physician diagnoses were used to assess hypertension; and red blood cells, platelets, and white blood cell differential counts were used to characterize hematology. The relationship between uranium exposure and hypertension or hematologic parameters was evaluated using generalized linear models and quantile regression for continuous outcomes, and logistic regression or ordinal logistic regression for categorical outcomes, after adjustment for potential confounding factors. Results: Of 8216 adult FMMP participants 4187 (51%) had low cumulative uranium exposure, 1273 (15%) had moderate exposure, and 2756 (34%) were in the high (>0.50 Sievert) cumulative lifetime uranium exposure category. Participants with elevated uranium exposure had decreased white blood cell and lymphocyte counts and increased eosinophil counts. Female participants with higher uranium exposures had elevated systolic blood pressure compared to women with lower exposures. However, no exposure-related changes were observed in diastolic blood pressure or hypertension diagnoses among female or male participants. Conclusions: Results from this investigation suggest that residents in the vicinity of the Fernald plant with elevated exposure to uranium primarily via inhalation exhibited decreases in white blood cell counts, and small, though statistically significant, gender-specific alterations in systolic blood pressure at entry into the FMMP.

  9. STATUS OF THE DEVELOPMENT OF IN-TANK/AT-TANK SEPARATIONS TECHNOLOGIES FOR FOR HIGH-LEVEL WASTE PROCESSING FOR THE U.S. DEPARTMENT OF ENERGY

    SciTech Connect

    Aaron, G.; Wilmarth, B.

    2011-09-19

    Within the U.S. Department of Energy's (DOE) Office of Technology Innovation and Development, the Office of Waste Processing manages a research and development program related to the treatment and disposition of radioactive waste. At the Savannah River (South Carolina) and Hanford (Washington) Sites, approximately 90 million gallons of waste are distributed among 226 storage tanks (grouped or collocated in 'tank farms'). This waste may be considered to contain mixed and stratified high activity and low activity constituent waste liquids, salts and sludges that are collectively managed as high level waste (HLW). A large majority of these wastes and associated facilities are unique to the DOE, meaning many of the programs to treat these materials are 'first-of-a-kind' and unprecedented in scope and complexity. As a result, the technologies required to disposition these wastes must be developed from basic principles, or require significant re-engineering to adapt to DOE's specific applications. Of particular interest recently, the development of In-tank or At-Tank separation processes have the potential to treat waste with high returns on financial investment. The primary objective associated with In-Tank or At-Tank separation processes is to accelerate waste processing. Insertion of the technologies will (1) maximize available tank space to efficiently support permanent waste disposition including vitrification; (2) treat problematic waste prior to transfer to the primary processing facilities at either site (i.e., Hanford's Waste Treatment and Immobilization Plant (WTP) or Savannah River's Salt Waste Processing Facility (SWPF)); and (3) create a parallel treatment process to shorten the overall treatment duration. This paper will review the status of several of the R&D projects being developed by the U.S. DOE including insertion of the ion exchange (IX) technologies, such as Small Column Ion Exchange (SCIX) at Savannah River. This has the potential to align the salt and sludge processing life cycle, thereby reducing the Defense Waste Processing Facility (DWPF) mission by 7 years. Additionally at the Hanford site, problematic waste streams, such as high boehmite and phosphate wastes, could be treated prior to receipt by WTP and thus dramatically improve the capacity of the facility to process HLW. Treatment of boehmite by continuous sludge leaching (CSL) before receipt by WTP will dramatically reduce the process cycle time for the WTP pretreatment facility, while treatment of phosphate will significantly reduce the number of HLW borosilicate glass canisters produced at the WTP. These and other promising technologies will be discussed.

  10. Process Testing to Support the Conceptual Design of a Plutonium Vitrification Facility

    SciTech Connect

    Zamecnik, J.R.; Jones, T.M.; Miller, D.H.; Herman, D.T.; Marra, J.C.

    2007-07-01

    In the aftermath of the Cold War, the United States Department of Energy (DOE) has identified up to 50 metric tonnes of excess plutonium that needs to be dispositioned. The bulk of the material is slated to be blended with uranium and fabricated into a Mixed Oxide (MOX) fuel for subsequent burning in commercial nuclear reactors. Excess plutonium-containing materials that are not suitable for fabrication into MOX fuel will need to be dispositioned via other means. A lanthanide borosilicate (LaBS) glass was identified as a preferred form for the disposition of the impure plutonium-containing feeds. The LaBS glass formulation uses a lanthanide borosilicate frit rather than the alkali borosilicate frit used to vitrify high level waste. The LaBS glass has been shown to be able to accommodate high quantities of fissile material (greater than 10 wt % elemental plutonium) and tolerate the impurities expected in the plutonium feed streams. A conceptual design effort is now underway at the Savannah River Site (SRS) to design a vitrification facility to immobilize the excess Pu feeds that are not slated for disposition via MOX fuel. The conceptual design phase is planned to complete in FY07. A test program was initiated at the Savannah River National Laboratory (SRNL) to provide input data to the conceptual design effort. A major component of this test effort involves vitrification process testing. A cylindrical induction melter (CIM) was developed for the vitrification of actinide feed streams. Due to the high temperatures required to incorporate high plutonium oxide contents into the glass by dissolution and melting, the melter vessel is constructed out of Pt/Rh alloy and can be operated at temperatures up to 1600 deg. C. Additionally, the melter design is compact to facilitate installation in a glovebox (the size of the conceptual facility melter is approximately 6'' in diameter by 18'' tall). The CIM has proven to be a viable means to process the LaBS glass at processing temperatures of 1400-1500 deg. C. In this paper, the offgas sampling tests conducted in the CIM to capture and analyze the particulate and vapors emitted from lanthanide borosilicate (LaBS) Frit X with HfO{sub 2} as a surrogate for PuO{sub 2} and added impurities are discussed. The tests with impurities added showed that alkali salts such as NaCl and KCl were substantially emitted into the offgas system as the salt particulate, HCl, or Cl{sub 2}. Retention of Na and K in the glass were about 80 and 55%, respectively. Chloride retention was about 35%; chloride remaining in the glass was 0.29-0.37 wt%. Overall, about 58-72% of the impurities added were volatilized. Virtually all of the particulate species were collected on the nominal 0.3 {mu}m filter. The particulate was found to be as small as 0.2 {mu}m and have an approximate median size of 0.5 {mu}m. The particulate salt was also found to stick together by forming bridges between particles. (authors)

  11. Advanced technologies for maintenance of electrical systems and equipment at the Savannah River Site Defense Waste Processing Facility

    SciTech Connect

    Husler, R.O.; Weir, T.J.

    1991-12-31

    An enhanced maintenance program is being established to characterize and monitor cables, components, and process response at the Savannah River Site, Defense Waste Processing Facility. This facility was designed and constructed to immobilize the radioactive waste currently stored in underground storage tanks and is expected to begin operation in 1993. The plant is initiating the program to baseline and monitor instrument and control (I&C) and electrical equipment, remote process equipment, embedded instrument and control cables, and in-cell jumper cables used in the facility. This program is based on the electronic characterization and diagnostic (ECAD) system which was modified to include process response analysis and to meet rigid Department of Energy equipment requirements. The system consists of computer-automated, state-of-the-art electronics. The data that are gathered are stored in a computerized database for analysis, trending, and troubleshooting. It is anticipated that the data which are gathered and trended will aid in life extension for the facility.

  12. 40 CFR 80.513 - What provisions apply to transmix processing facilities and pipelines that produce diesel fuel...

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... processing facilities and pipelines that produce diesel fuel from pipeline interface? 80.513 Section 80.513... FUELS AND FUEL ADDITIVES Motor Vehicle Diesel Fuel; Nonroad, Locomotive, and Marine Diesel Fuel; and ECA... pipelines that produce diesel fuel from pipeline interface? For purposes of this section, transmix means...

  13. 40 CFR 80.513 - What provisions apply to transmix processing facilities and pipelines that produce diesel fuel...

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... processing facilities and pipelines that produce diesel fuel from pipeline interface? 80.513 Section 80.513... FUELS AND FUEL ADDITIVES Motor Vehicle Diesel Fuel; Nonroad, Locomotive, and Marine Diesel Fuel; and ECA... pipelines that produce diesel fuel from pipeline interface? For purposes of this section, transmix means...

  14. Development of a portable hyperspectral imaging system for monitoring the efficacy of sanitation procedures in food processing facilities

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Cleaning and sanitation in food processing facilities is a critical step in reducing the risk of transfer of pathogenic organisms to food consumed by the public. Current methods to check the effectiveness of sanitation procedures rely on visual observation and sub-sampling tests such as ATP biolumin...

  15. 17 CFR 37.10 - Process for a swap execution facility to make a swap available to trade.

    Code of Federal Regulations, 2014 CFR

    2014-04-01

    ... COMMODITY FUTURES TRADING COMMISSION SWAP EXECUTION FACILITIES General Provisions 37.10 Process for a swap... offers that swap for trading on its trading system or platform. (b) Factors to consider. To make a swap... and sellers; (2) The frequency or size of transactions; (3) The trading volume; (4) The number...

  16. Screening study for waste biomass to ethanol production facility using the Amoco process in New York State. Final report

    SciTech Connect

    1995-08-01

    This report evaluates the economic feasibility of locating biomass-to-ethanol waste conversion facilities in New York State. Part 1 of the study evaluates 74 potential sites in New York City and identifies two preferred sites on Staten, the Proctor Gamble and the Arthur Kill sites, for further consideration. Part 2 evaluates upstate New York and determines that four regions surrounding the urban centers of Albany, Buffalo, Rochester, and Syracuse provide suitable areas from which to select specific sites for further consideration. A separate Appendix provides supplemental material supporting the evaluations. A conceptual design and economic viability evaluation were developed for a minimum-size facility capable of processing 500 tons per day (tpd) of biomass consisting of wood or paper, or a combination of the two for upstate regions. The facility would use Amoco`s biomass conversion technology and produce 49,000 gallons per day of ethanol and approximately 300 tpd of lignin solid by-product. For New York City, a 1,000-tpd processing facility was also evaluated to examine effects of economies of scale. The reports evaluate the feasibility of building a biomass conversion facility in terms of city and state economic, environmental, and community factors. Given the data obtained to date, including changing costs for feedstock and ethanol, the project is marginally attractive. A facility should be as large as possible and located in a New York State Economic Development Zone to take advantage of economic incentives. The facility should have on-site oxidation capabilities, which will make it more financially viable given the high cost of energy. 26 figs., 121 tabs.

  17. Mechanical design and fabrication of a prototype facility for processing NaK using a chlorine reaction method

    SciTech Connect

    Dafoe, R.; Keller, D.; Stoll, F.

    1990-01-01

    A prototype facility has been built at the Idaho National Engineering Laboratory (INEL) to dispose of 180 gal(0.68 m{sup 3}) of radioactively contaminated NaK (sodium-potassium) that have been stored on site for 35 years. The NaK was used as primary coolant for the Experimental Breeder Reactor I (EBR-I) at the INEL and was contaminated during a meltdown of the Mark II core in November 1955. The NaK then was transferred to four containers for temporary storage. The facility process will react the NaK with elemental chlorine using a batch process to produce chemically stable sodium chloride and potassium chloride salts. The first use of the facility will be on a prototype level to verify the method. If results are favorable, the facility will be modified to eventually dispose of the EBR-I NaK. The design and intended operation of the prototype facility are described. 2 figs.

  18. A Microsoft Project-Based Planning, Tracking, and Management Tool for the National Transonic Facility's Model Changeover Process

    NASA Technical Reports Server (NTRS)

    Vairo, Daniel M.

    1998-01-01

    The removal and installation of sting-mounted wind tunnel models in the National Transonic Facility (NTF) is a multi-task process having a large impact on the annual throughput of the facility. Approximately ten model removal and installation cycles occur annually at the NTF with each cycle requiring slightly over five days to complete. The various tasks of the model changeover process were modeled in Microsoft Project as a template to provide a planning, tracking, and management tool. The template can also be used as a tool to evaluate improvements to this process. This document describes the development of the template and provides step-by-step instructions on its use and as a planning and tracking tool. A secondary role of this document is to provide an overview of the model changeover process and briefly describe the tasks associated with it.

  19. The Earthscope USArray Array Network Facility (ANF): Evolution of Data Acquisition, Processing, and Storage Systems

    NASA Astrophysics Data System (ADS)

    Davis, G. A.; Battistuz, B.; Foley, S.; Vernon, F. L.; Eakins, J. A.

    2009-12-01

    Since April 2004 the Earthscope USArray Transportable Array (TA) network has grown to over 400 broadband seismic stations that stream multi-channel data in near real-time to the Array Network Facility in San Diego. In total, over 1.7 terabytes per year of 24-bit, 40 samples-per-second seismic and state of health data is recorded from the stations. The ANF provides analysts access to real-time and archived data, as well as state-of-health data, metadata, and interactive tools for station engineers and the public via a website. Additional processing and recovery of missing data from on-site recorders (balers) at the stations is performed before the final data is transmitted to the IRIS Data Management Center (DMC). Assembly of the final data set requires additional storage and processing capabilities to combine the real-time data with baler data. The infrastructure supporting these diverse computational and storage needs currently consists of twelve virtualized Sun Solaris Zones executing on nine physical server systems. The servers are protected against failure by redundant power, storage, and networking connections. Storage needs are provided by a hybrid iSCSI and Fiber Channel Storage Area Network (SAN) with access to over 40 terabytes of RAID 5 and 6 storage. Processing tasks are assigned to systems based on parallelization and floating-point calculation needs. On-site buffering at the data-loggers provide protection in case of short-term network or hardware problems, while backup acquisition systems at the San Diego Supercomputer Center and the DMC protect against catastrophic failure of the primary site. Configuration management and monitoring of these systems is accomplished with open-source (Cfengine, Nagios, Solaris Community Software) and commercial tools (Intermapper). In the evolution from a single server to multiple virtualized server instances, Sun Cluster software was evaluated and found to be unstable in our environment. Shared filesystem architectures using PxFS and QFS were found to be incompatible with our software architecture, so sharing of data between systems is accomplished via traditional NFS. Linux was found to be limited in terms of deployment flexibility and consistency between versions. Despite the experimentation with various technologies, our current virtualized architecture is stable to the point of an average daily real time data return rate of 92.34% over the entire lifetime of the project to date.

  20. Automatic methods of the processing of data from track detectors on the basis of the PAVICOM facility

    NASA Astrophysics Data System (ADS)

    Aleksandrov, A. B.; Goncharova, L. A.; Davydov, D. A.; Publichenko, P. A.; Roganova, T. M.; Polukhina, N. G.; Feinberg, E. L.

    2007-02-01

    New automatic methods essentially simplify and increase the rate of the processing of data from track detectors. This provides a possibility of processing large data arrays and considerably improves their statistical significance. This fact predetermines the development of new experiments which plan to use large-volume targets, large-area emulsion, and solid-state track detectors [1]. In this regard, the problem of training qualified physicists who are capable of operating modern automatic equipment is very important. Annually, about ten Moscow students master the new methods, working at the Lebedev Physical Institute at the PAVICOM facility [2 4]. Most students specializing in high-energy physics are only given an idea of archaic manual methods of the processing of data from track detectors. In 2005, on the basis of the PAVICOM facility and the physicstraining course of Moscow State University, a new training work was prepared. This work is devoted to the determination of the energy of neutrons passing through a nuclear emulsion. It provides the possibility of acquiring basic practical skills of the processing of data from track detectors using automatic equipment and can be included in the educational process of students of any physical faculty. Those who have mastered the methods of automatic data processing in a simple and pictorial example of track detectors will be able to apply their knowledge in various fields of science and technique. Formulation of training works for pregraduate and graduate students is a new additional aspect of application of the PAVICOM facility described earlier in [4].

  1. The Shock Compression Laboratory at Harvard: A New Facility for Planetary Impact Processes

    NASA Technical Reports Server (NTRS)

    Stewart, S. T.

    2004-01-01

    The Shock Compression Laboratory in the Department of Earth and Planetary Sciences at Harvard is a new facility for the study of impact and collisional phenomena. The following describes the experimental capabilities of the laboratory.

  2. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site

    SciTech Connect

    Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

    1993-02-01

    The Defense Waste Processing Facility (DWPF) was built on the Savannah River Site (SRS) during the mid-1980's. The Savannah River Ecology Laboratory (SREL) has completed 12 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Research conducted by the SREL has focused primarily on four questions related to these wetlands: (1) Prior to construction, what fauna and flora were present at the DWPF site and at similar, yet undisturbed, alternative sites (2) By comparing the Carolina bay at the DWPF site (Sun Bay) with an undisturbed control Carolina bay (Rainbow Bay), what effect is construction having on the organisms that inhabited the DWPF site (3) By comparing control streams with streams on the periphery of the DWPF site, what effect is construction having on the peripheral streams (4) How effective have efforts been to lessen the impacts of construction, both with respect to erosion control measures and the construction of refuge ponds'' as alternative breeding sites for amphibians that formerly bred at Sun Bay Through the long-term census-taking of biota at the DWPF site and Rainbow Bay, SREL has begun to evaluate the impact of construction on the biota and the effectiveness of mitigation efforts. Similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive Orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10CFR1022).

  3. Molecular and Genomic Characterization of Vibrio mimicus Isolated from a Frozen Shrimp Processing Facility in Mexico.

    PubMed

    Guardiola-Avila, Iliana; Acedo-Felix, Evelia; Sifuentes-Romero, Itzel; Yepiz-Plascencia, Gloria; Gomez-Gil, Bruno; Noriega-Orozco, Lorena

    2016-01-01

    Vibrio mimicus is a gram-negative bacterium responsible for diseases in humans. Three strains of V. mimicus identified as V. mimicus 87, V. mimicus 92 and V. mimicus 93 were isolated from a shrimp processing facility in Guaymas, Sonora, Mexico. The strains were analyzed using several molecular techniques and according to the cluster analysis they were different, their similarities ranged between 51.3% and 71.6%. ERIC-PCR and RAPD (vmh390R) were the most discriminatory molecular techniques for the differentiation of these strains. The complete genomes of two strains (V. mimicus 87, renamed as CAIM 1882, and V. mimicus 92, renamed as CAIM 1883) were sequenced. The sizes of the genomes were 3.9 Mb in both strains, with 2.8 Mb in ChI and 1.1 Mb in ChII. A 12.7% difference was found in the proteome content (BLAST matrix). Several virulence genes were detected (e.g. capsular polysaccharide, an accessory colonization factor and genes involved in quorum-sensing) which were classified in 16 categories. Variations in the gene content between these genomes were observed, mainly in proteins and virulence genes (e.g., hemagglutinin, mobile elements and membrane proteins). According to these results, both strains were different, even when they came from the same source, giving an insight of the diversity of V. mimicus. The identification of various virulence genes, including a not previously reported V. mimicus gene (acfD) in ChI in all sequenced strains, supports the pathogenic potential of this species. Further analysis will help to fully understand their potential virulence, environmental impact and evolution. PMID:26730584

  4. Molecular and Genomic Characterization of Vibrio mimicus Isolated from a Frozen Shrimp Processing Facility in Mexico

    PubMed Central

    Guardiola-Avila, Iliana; Acedo-Felix, Evelia; Sifuentes-Romero, Itzel; Yepiz-Plascencia, Gloria; Gomez-Gil, Bruno; Noriega-Orozco, Lorena

    2016-01-01

    Vibrio mimicus is a gram-negative bacterium responsible for diseases in humans. Three strains of V. mimicus identified as V. mimicus 87, V. mimicus 92 and V. mimicus 93 were isolated from a shrimp processing facility in Guaymas, Sonora, Mexico. The strains were analyzed using several molecular techniques and according to the cluster analysis they were different, their similarities ranged between 51.3% and 71.6%. ERIC-PCR and RAPD (vmh390R) were the most discriminatory molecular techniques for the differentiation of these strains. The complete genomes of two strains (V. mimicus 87, renamed as CAIM 1882, and V. mimicus 92, renamed as CAIM 1883) were sequenced. The sizes of the genomes were 3.9 Mb in both strains, with 2.8 Mb in ChI and 1.1 Mb in ChII. A 12.7% difference was found in the proteome content (BLAST matrix). Several virulence genes were detected (e.g. capsular polysaccharide, an accessory colonization factor and genes involved in quorum-sensing) which were classified in 16 categories. Variations in the gene content between these genomes were observed, mainly in proteins and virulence genes (e.g., hemagglutinin, mobile elements and membrane proteins). According to these results, both strains were different, even when they came from the same source, giving an insight of the diversity of V. mimicus. The identification of various virulence genes, including a not previously reported V. mimicus gene (acfD) in ChI in all sequenced strains, supports the pathogenic potential of this species. Further analysis will help to fully understand their potential virulence, environmental impact and evolution. PMID:26730584

  5. Airborne concentrations of chrysotile asbestos in serpentine quarries and stone processing facilities in Valmalenco, Italy.

    PubMed

    Cattaneo, Andrea; Somigliana, Anna; Gemmi, Mauro; Bernabeo, Ferruccio; Savoca, Domenico; Cavallo, Domenico M; Bertazzi, Pier A

    2012-07-01

    Asbestos may be naturally present in rocks and soils. In some cases, there is the possibility of releasing asbestos fibres into the atmosphere from the rock or soil, subsequently exposing workers and the general population, which can lead to an increased risk of developing asbestos-related diseases. In the present study, air contaminated with asbestos fibres released from serpentinites was investigated in occupational settings (quarries and processing factories) and in the environment close to working facilities and at urban sites. The only naturally occurrence of asbestos found in Valmalenco area was chrysotile; amphibole fibres were never detected. An experimental cut-off diameter of 0.25 μm was established for distinguishing between Valmalenco chrysotile and antigorite single fibres using selected area electron diffraction analyses. Air contamination from chrysotile fibres in the examined occupational settings was site-dependent as the degree of asbestos contamination of Valmalenco serpentinites is highly variable from place to place. Block cutting of massive serpentinites with multiple blades or discs and drilling at the quarry sites that had the highest levels of asbestos contamination generated the highest exposures to (i.e. over the occupational exposure limits) asbestos. Conversely, working activities on foliated serpentinites produced airborne chrysotile concentrations comparable with ambient levels. Environmental chrysotile concentrations were always below the Italian limit for life environments (0.002 f ml(-1)), except for one sample collected at a quarry property boundary. The present exposure assessment study should encourage the development of an effective and concordant policy for proper use of asbestos-bearing rocks and soils as well as for the protection of public health. PMID:22213048

  6. Elimination Of Catalytic Hydrogen Generation In Defense Waste Processing Facility Slurries

    SciTech Connect

    Koopman, D. C.

    2013-01-22

    Based on lab-scale simulations of Defense Waste Processing Facility (DWPF) slurry chemistry, the addition of sodium nitrite and sodium hydroxide to waste slurries at concentrations sufficient to take the aqueous phase into the alkaline region (pH > 7) with approximately 500 mg nitrite ion/kg slurry (assuming <25 wt% total solids, or equivalently 2,000 mg nitrite/kg total solids) is sufficient to effectively deactivate the noble metal catalysts at temperatures between room temperature and boiling. This is a potential strategy for eliminating catalytic hydrogen generation from the list of concerns for sludge carried over into the DWPF Slurry Mix Evaporator Condensate Tank (SMECT) or Recycle Collection Tank (RCT). These conclusions are drawn in large part from the various phases of the DWPF catalytic hydrogen generation program conducted between 2005 and 2009. The findings could apply to various situations, including a solids carry-over from either the Sludge Receipt and Adjustment Tank (SRAT) or Slurry Mix Evaporator (SME) into the SMECT with subsequent transfer to the RCT, as well as a spill of formic acid into the sump system and transfer into an RCT that already contains sludge solids. There are other potential mitigating factors for the SMECT and RCT, since these vessels are typically operated at temperatures close to the minimum temperatures that catalytic hydrogen has been observed to occur in either the SRAT or SME (pure slurry case), and these vessels are also likely to be considerably more dilute in both noble metals and formate ion (the two essential components to catalytic hydrogen generation) than the two primary process vessels. Rhodium certainly, and ruthenium likely, are present as metal-ligand complexes that are favored under certain concentrations of the surrounding species. Therefore, in the SMECT or RCT, where a small volume of SRAT or SME material would be significantly diluted, conditions would be less optimal for forming or sustaining the catalytic ligand species. Such conditions are likely to adversely impact the ability of the transferred mass to produce hydrogen at the same rate (per unit mass SRAT or SME slurry) as in the SRAT or SME vessels.

  7. Remote crane control techniques and closed circuit television for the US Deparment of Energy, Defense Waste Processing Facility

    SciTech Connect

    DaSilva, D.A.

    1988-01-01

    The Defense Waste Processing Facility (DWPF) located at the Savannah River Plant (SRP), South Carolina is a nuclear waste facility being built to vitrify and containerize high level radioactive waste product. DWPF has a unique requirement for an unmanned crane system to install and replace equipment in the high humidity, high radiation and harsh chemical environment of permanently inaccessible processing cells. A radio control system is provided to control a 117 ton capacity bridge crane that is equipped with various power tools for remote handling of crane replaceable and maintained equipment. High resolution black and white Closed Circuit Television (CCTV) assemblies mounted on the crane and on the walls of the various processing cells are provided for viewing the equipment during normal operations and maintenance.

  8. Renovation of CPF (Chemical Processing Facility) for Development of Advanced Fast Reactor Fuel Cycle System

    SciTech Connect

    Shinichi Aose; Takafumi Kitajima; Kouji Ogasawara; Kazunori Nomura; Shigehiko Miyachi; Yoshiaki Ichige; Tadahiro Shinozaki; Shinichi Ohuchi

    2008-01-15

    CPF (Chemical Processing Facility) was constructed at Nuclear Fuel Cycle Engineering Laboratories of JAEA (Japan Atomic Energy Agency) in 1980 as a basic research field where spent fuel pins from fast reactor (FR) and high level liquid waste can be dealt with. The renovation consists of remodeling of the CA-3 cell and the laboratory A, installation of globe boxes, hoods and analytical equipments to the laboratory C and the analytical laboratory. Also maintenance equipments in the CA-5 cell which had been out of order were repaired. The CA-3 cell is the main cell in which important equipments such as a dissolver, a clarifier and extractors are installed for carrying out the hot test using the irradiated FR fuel. Since the CPF had specialized originally in the research function for the Purex process, it was desired to execute the research and development of such new, various reprocessing processes. Formerly, equipments were arranged in wide space and connected with not only each other but also with utility supply system mainly by fixed stainless steel pipes. It caused shortage of operation space in flexibility for basic experimental study. Old equipments in the CA-3 cell including vessels and pipes were removed after successful decontamination, and new equipments were installed conformably to the new design. For the purpose of easy installation and rearranging the experimental equipments, equipments are basically connected by flexible pipes. Since dissolver is able to be easily replaced, various dissolution experiments is conducted. Insoluble residue generated by dissolution of spent fuel is clarified by centrifugal. This small apparatus is effective to space-saving. Mini mixer settlers or centrifugal contactors are put on to the prescribed limited space in front of the backside wall. Fresh reagents such as solvent, scrubbing and stripping solution are continuously fed from the laboratory A to the extractor by the reagent supply system with semi-automatic observation system. The in-cell crane in CA-5 was renovated to increase driving efficiency. At the renovation for the in-cell crane, full scale mockup test and 3D simulation test had been executed in advance. After the renovation, hot tests in the CPF had been resumed from JFY 2002. New equipments such as dissolver, extractor, electrolytic device, etc. were installed in CA-3 conformably to the new design laid out in order to ensure the function and space. Glove boxes in the analysis laboratory were renewed in order to let it have flexibility from the viewpoint of conducting basic experiments (ex. U crystallization). Glove boxes and hoods were newly installed in the laboratory A for basic research and analysis, especially on MA chemistries. One laboratory (the laboratory C) was established to research about dry reprocessing. The renovation of the CPF has been executed in order to contribute to the development on the advanced fast reactor fuel cycle system, which will give us many sort of technical subject and experimental theme to be solved in the 2. Generation of the CPF.

  9. Qualification of the First ICS-3000 ION Chromatograph for use at the Defense Waste Processing Facility

    SciTech Connect

    Edwards, T; Mahannah, R.

    2011-07-05

    The ICS-3000 Ion Chromatography (IC) system installed in 221-S M-13 has been qualified for use. The qualification was a head to head comparison of the ICS-3000 with the currently used DX-500 IC system. The crosscheck work included standards for instrument calibration and calibration verifications and standards for individual anion analysis, where the standards were traceable back to the National Institute of Standards and Technology (NIST). In addition the crosscheck work included the analysis of simulated Sludge Receipt Adjustment Tank (SRAT) Receipt, SRAT Product, and Slurry Mix Evaporator (SME) samples, along with radioactive Sludge Batch 5 material from the SRAT and SME tanks. Based upon the successful qualification of the ICS-3000 in M-13, it is recommended that this task proceed in developing the data to qualify, by a head to head comparison of the two ICS-3000 instruments, a second ICS-3000 to be installed in M-14. The Defense Waste Processing Facility (DWPF) requires the analysis of specific anions at various stages of its processing of high level waste (HLW). The anions of interest to the DWPF are fluoride, formate, chloride, nitrite, nitrate, sulfate, oxalate, and phosphate. The anion analysis is used to evaluate process chemistry including formic acid/nitric acid additions to establish optimum conditions for mercury stripping, reduction-oxidation (REDOX) chemistry for the melter, nitrite destruction, organic acid constituents, etc. The DWPF Laboratory (Lab) has been using Dionex DX-500 ion chromatography (IC) systems since 1998. The vendor informed DWPF in 2006 that the instruments would no longer be supported by service contracts after 2008. DWPF purchased three new ICS-3000 systems in September of 2006. The ICS-3000 instruments are (a) designed to be more stable using an eluent generator to make eluent, (b) require virtually no daily chemical handling by the analysts, (c) require less line breaks in the hood, and (d) generally require less maintenance due to the pump configuration only using water versus the current system where the pump uses various hydroxide concentrations. The ICS-3000 instruments also allow the DWPF to maintain current service contracts, which support routine preventive maintenance and emergency support for larger problems such as component failure. One of the three new systems was set up in the DWPF Lab trailers in January of 2007 to be used for the development of methods and procedures. This system will continue to be used for training, new method development and potential improvements to current methods. The qualification of the other two ICS-3000 instruments is to be a phased effort. This effort is to be supported by the Applied Computational Engineering and Statistical (ACES) group of the Savannah River National Laboratory (SRNL) as authorized by the Technical Task Request (TTR) and as directed by the corresponding Task Technical and Quality Assurance (TT&QA) plan. The installation of the first 'rad' system into the M-13 Lab module required modifications to both the Lab module and to the radiohood. The installation was completed in July 2008. The testing of this system was conducted as directed by the TT&QA plan. The purpose of this technical report is to provide a review of the data generated by these tests that will lead to the recommendation for the qualification of the M-13 ICS-3000 instrument. With the successful qualification of this first ICS-3000, plans will be developed for the installation of the second 'rad' system in the M-14 Lab module later in fiscal year 2009. When the second 'rad' ICS-3000 system is installed, the DX-500 systems will be removed and retired from service.

  10. QUALIFICATION OF THE SECOND ICS-3000 ION CHROMATOGRAPH FOR USE AT THE DEFENSE WASTE PROCESSING FACILITY

    SciTech Connect

    Edwards, T.; Mahannah, R.

    2009-12-03

    The ICS-3000 Ion Chromatography (IC) system installed in 221-S M-14 has been qualified for use. The qualification testing was a head to head comparison of the second ICS-3000 with the initial ICS-3000 system that was installed in 221-S M-13. The crosscheck work included standards for instrument calibration and calibration verifications and standards for individual anion analysis, where the standards were traceable back to the National Institute of Standards and Technology (NIST). In addition the crosscheck work included the analysis of simulated Sludge Receipt and Adjustment Tank (SRAT) Receipt, SRAT Product, and Slurry Mix Evaporator (SME) samples, along with radioactive Sludge Batch 5 material from the SRAT and SME tanks. The Defense Waste Processing Facility (DWPF) requires the analysis of specific anions at various stages of its processing of high level waste (HLW). The anions of interest to the DWPF are fluoride, formate, chloride, nitrite, nitrate, sulfate, oxalate, and phosphate. The anion analysis is used to evaluate process chemistry including formic acid/nitric acid additions to establish optimum conditions for mercury stripping, reduction-oxidation (REDOX) chemistry for the melter, nitrite destruction, etc. The DWPF Laboratory (Lab) has recently replaced the Dionex DX-500 ion chromatography (IC) systems that had been used since 1998 by the first of two new ICS-3000 systems. The replacement effort was necessary due to the vendor of the DX-500 systems no longer supporting service contracts after 2008. DWPF purchased three new ICS-3000 systems in September of 2006. The ICS-3000 instruments are (a) designed to be more stable using an eluent generator to make eluent, (b) require virtually no daily chemical handling by the analysts, (c) require less line breaks in the hood, and (d) generally require less maintenance due to the pump configuration only using water versus the current system where the pump uses various hydroxide concentrations. The ICS-3000 instruments also allow the DWPF to maintain current service contracts, which support routine preventive maintenance and emergency support for larger problems such as component failure. One of the three new systems was set up in the DWPF Lab trailers in January of 2007 to be used for the development of methods and procedures. This system will continue to be used for training, new method development and potential improvements to current methods. The qualification of the other two ICS-3000 instruments was a phased effort. This effort was supported by the Applied Computational Engineering and Statistical (ACES) group of the Savannah River National Laboratory (SRNL) as authorized by the Technical Task Request (TTR) [1] and as directed by the corresponding Task Technical and Quality Assurance (TT&QA) plan [2]. The installation of the first 'rad' system into the M-13 Lab module required modifications to both the Lab module and to the radiohood. The installation was completed in July 2008. The testing of this system was conducted as directed by the TT&QA plan [2], and the instrument was qualified for use at the DWPF Lab as documented in [3]. As part of that evaluation, a recommendation was made that the second ICS-3000 be installed in the M-14 module and that qualification testing of that system be conducted. The purpose of this technical report is to provide a review of the data generated by these tests that will lead to the recommendation for the qualification of the M-14 ICS-3000 instrument.

  11. DEFENSE WASTE PROCESSING FACILITY ANALYTICAL METHOD VERIFICATION FOR THE SLUDGE BATCH 5 QUALIFICATION SAMPLE

    SciTech Connect

    Click, D; Tommy Edwards, T; Henry Ajo, H

    2008-07-25

    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-HNO3 acid dissolution (i.e., DWPF Cold Chem Method, see 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 digestion of Sludge Batch 5 (SB5) SRAT Receipt and SB5 SRAT Product samples. The SB5 SRAT Receipt and SB5 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB5 Batch composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 4 (SB4), to form the SB5 Blend composition. The results for any one particular element should not be used in any way to identify the form or speciation of a particular element in the sludge or used to estimate ratios of compounds in the sludge. A statistical comparison of the data validates the use of the DWPF CC method for SB5 Batch composition. However, the difficulty that was encountered in using the CC method for SB4 brings into question the adequacy of CC for the SB5 Blend. Also, it should be noted that visible solids remained in the final diluted solutions of all samples digested by this method at SRNL (8 samples total), which is typical for the DWPF CC method but not seen in the other methods. Recommendations to the DWPF for application to SB5 based on studies to date: (1) A dissolution study should be performed on the WAPS sample by SRNL which consists of the final composition of the sludge (the SB5 Blend); (2) Given the heel of SB4 in Tank 40, the DWPF lab should monitor the aluminum concentration in the first 10 SRAT Receipt batches of SB5 using both CC and sodium peroxide/hydroxide fusion to evaluate the adequacy of aluminum recovery by the CC method for this sludge batch; and (3) SRNL and the DWPF lab should investigate if comparisons between the elemental concentrations of the SME product glass (adjusted for frit addition) obtained by the mixed acid and peroxide fusion digestion and the SRAT Receipt and SRAT Product elemental concentrations obtained via the DWPF CC method provide insight into the adequacy of the CC method for analysis of the SRAT Product. The DWPF lab would need to calcine the SRAT product at 1050 C for the best comparison. If a consistent difference in elemental concentrations is revealed, another type of digestion (i.e. sodium peroxide/hydroxide fusion) should be used to determine the concentration of the element in question. Particular emphasis should be placed on monitoring the aluminum concentration in SB5.

  12. EVALUATION OF A TURBIDITY METER FOR USE AT THE DEFENSE WASTE PROCESSING FACILITY

    SciTech Connect

    Mahannah, R.; Edwards, T.

    2013-06-04

    Savannah River Remediation’s (SRR’s) Defense Waste Processing Facility (DWPF) Laboratory currently tests for sludge carry-over into the Recycle Collection Tank (RCT) by evaluating the iron concentration in the Slurry Mix Evaporator Condensate Tank (SMECT) and relating this iron concentration to the amount of sludge solids present. A new method was proposed for detecting the amount of sludge in the SMECT that involves the use of an Optek turbidity sensor. Waste Services Laboratory (WSL) personnel conducted testing on two of these units following a test plan developed by Waste Solidification Engineering (WSE). Both Optek units (SN64217 and SN65164) use sensor model AF16-N and signal converter model series C4000. The sensor body of each unit was modified to hold a standard DWPF 12 cc sample vial, also known as a “peanut” vial. The purpose of this testing was to evaluate the use of this model of turbidity sensor, or meter, to provide a measurement of the sludge solids present in the SMECT based upon samples from that tank. During discussions of the results from this study by WSE, WSL, and Savannah River National Laboratory (SRNL) personnel, an upper limit on the acceptable level of solids in SMECT samples was set at 0.14 weight percent (wt%). A “go/no-go” decision criterion was to be developed for the critical turbidity response, which is expressed in concentration units (CUs), for each Optek unit based upon the 0.14 wt% solids value. An acceptable or a “go” decision for the SMECT should reflect the situation that there is an identified risk (e.g. 5%) for a CU response from the Optek unit to be less than the critical CU value when the solids content of the SMECT is actually 0.14 wt% or greater, while a “no-go” determination (i.e., an Optek CU response above the critical CU value, a conservative decision relative to risk) would lead to additional evaluations of the SMECT to better quantify the possible solids content of the tank. Subsequent to the issuance of the initial version of this report but under the scope of the original request for technical assistance, WSE asked for this report to be revised to include the “go/no-go” CU value corresponding to 0.28 wt% solids. It was this request that led to the preparation of Revision 1 of the report. The results for the 0.28 wt% solids value were developed following the same approach as that utilized for the 0.14 wt% solids value. A sludge simulant was used to develop standards for testing both Optek units and to determine the viability of a “go/no-go” CU response for each of the units. Statistical methods were used by SRNL to develop the critical CU value for the “go/no-go” decision for these standards for each Optek unit. Since only one sludge simulant was available for this testing, the sensitivity of these results to other simulants and to actual sludge material is not known. However, limited testing with samples from the actual DWPF process (both SRAT product samples and SMECT samples) demonstrated that the use of the “go/no-go” criteria developed from the sludge simulant testing was conservative for these samples taken from the sludge batch, Sludge Batch 7b, being processed at the time of this testing. While both of the Optek units performed very reliably during this testing, there were statistically significant differences (although small on a practical scale) between the two units. Thus, testing should be conducted on any new unit of this Optek model to qualify it before it is used to support the DWPF operation.

  13. Evaluation Of A Turbidity Meter For Use At The Defense Waste Processing Facility

    SciTech Connect

    Mahannah, R. N.; Edwards, T. B.

    2013-01-15

    Savannah River Remediation's (SRR's) Defense Waste Processing Facility (DWPF) Laboratory currently tests for sludge carry-over into the Recycle Collection Tank (RCT) by evaluating the iron concentration in the Slurry Mix Evaporator Condensate Tank (SMECT) and relating this iron concentration to the amount of sludge solids present. A new method was proposed for detecting the amount of sludge in the SMECT that involves the use of an Optek turbidity sensor. Waste Services Laboratory (WSL) personnel conducted testing on two of these units following a test plan developed by Waste Solidification Engineering (WSE). Both Optek units (SN64217 and SN65164) use sensor model AF16-N and signal converter model series C4000. The sensor body of each unit was modified to hold a standard DWPF 12 cc sample vial, also known as a ''peanut'' vial. The purpose of this testing was to evaluate the use of this model of turbidity sensor, or meter, to provide a measurement of the sludge solids present in the SMECT based upon samples from that tank. During discussions of the results from this study by WSE, WSL, and Savannah River National Laboratory (SRNL) personnel, an upper limit on the acceptable level of solids in SMECT samples was set at 0.14 wt%. A ''go/no-go'' decision criterion was to be developed for the critical turbidity response, which is expressed in concentration units (CUs), for each Optek unit based upon the 0.14 wt% solids value. An acceptable or a ''go'' decision for the SMECT should reflect the situation that there is an identified risk (e.g. 5%) for a CU response from the Optek unit to be less than the critical CU value when the solids content of the SMECT is actually 0.14 wt% or greater, while a ''no-go'' determination (i.e., an Optek CU response above the critical CU value, a conservative decision relative to risk) would lead to additional evaluations of the SMECT to better quantify the possible solids content of the tank. A sludge simulant was used to develop standards for testing both Optek units and to determine the viability of a ''go/no-go'' CU response for each of the units. Statistical methods were used by SRNL to develop the critical CU value for the ''go/no-go'' decision for these standards for each Optek unit. Since only one sludge simulant was available for this testing, the sensitivity of these results to other simulants and to actual sludge material is not known. However, limited testing with samples from the actual DWPF process (both SRAT product samples and SMECT samples) demonstrated that the use of the ''go/no-go'' criteria developed from the sludge simulant testing was conservative for these samples taken from Sludge Batch 7b (SB7b), the sludge batch currently being processed. While both of the Optek units performed very reliably during this testing, there were statistically significant differences (although small on a practical scale) between the two units. Thus, testing should be conducted on any new unit of this Optek model to qualify it before it is used to support the DWPF operation.

  14. Chemical hazards database and detection system for Microgravity and Materials Processing Facility (MMPF)

    NASA Technical Reports Server (NTRS)

    Steele, Jimmy; Smith, Robert E.

    1991-01-01

    The ability to identify contaminants associated with experiments and facilities is directly related to the safety of the Space Station. A means of identifying these contaminants has been developed through this contracting effort. The delivered system provides a listing of the materials and/or chemicals associated with each facility, information as to the contaminant's physical state, a list of the quantity and/or volume of each suspected contaminant, a database of the toxicological hazards associated with each contaminant, a recommended means of rapid identification of the contaminants under operational conditions, a method of identifying possible failure modes and effects analysis associated with each facility, and a fault tree-type analysis that will provide a means of identifying potential hazardous conditions related to future planned missions.

  15. SHORT CIRCUIT COORDINATION STUDY & ARC FLASH EVALUATION FOR LIQUID PROCESSING & CAPSULE STORAGE 310 FACILITY

    SciTech Connect

    TOWNE, C.M.

    2003-12-26

    The objective of this study is to provide a design basis document for the electrical distribution system for the 310 Facility in the 300 Area. The study must assure that electrical equipment is rated to withstand the available fault current under abnormal (short circuit) conditions. Under-rated equipment would result in property damage, prolonged facility outages, and possible personal injury. Also to be considered, is the coordination of protective devices. This assures that the protection device nearest a fault will open and isolate the problem area from the remainder of facility systems. The study must specify what settings are required on adjustable protective devices to achieve optimum coordination. Lastly, the study must calculate Arc Blast energies at all parts of the system so that proper Personal Protective Equipment (PPE) can be specified for energized work.

  16. Processing capabilties for the elimination of contaminated metal scrapyards at DOE/ORO-managed sites. [Metal smelting facility

    SciTech Connect

    Mack, J.E.; Williams, L.C.

    1982-01-01

    Capabilities exist for reducing all the contaminated nickel, aluminum, and copper scrap to ingot form by smelting. Processing these metals at existing facilities could be completed in about 5 or 6 years. However, these metals represent only about 20% of the total metal inventories currently on hand at the DOE/ORO-managed sites. No provisions have been made for the ferrous scrap. Most of the ferrous scrap is unclassified and does not require secured storage. Also, the potential resale value of the ferrous scrap at about $100 per ton is very low in comparison. Consequently, this scrap has been allowed to accumulate. With several modifications and equipment additions, the induction melter at PGDP could begin processing ferrous scrap after its commitment to nickel and aluminum. The PGDP smelter is a retrofit installation, and annual throughput capabilities are limited. Processing of the existing ferrous scrap inventories would not be completed until the FY 1995-2000 time frame. An alternative proposal has been the installation of induction melters at the other two enrichment facilities. Conceptual design of a generic metal smelting facility is under way. The design study includes capital and operating costs for scrap preparation through ingot storage at an annual throughput of 10,000 tons per year. Facility design includes an induction melter with the capability of melting both ferrous and nonferrous metals. After three years of operation with scrapyard feed, the smelter would have excess capacity to support on-site decontamination and decomissioning projects or upgrading programs. The metal smelting facility has been proposed for FY 1984 line item funding with start-up operations in FY 1986.

  17. Wetland and Sensitive Species Survey Report for Y-12: Proposed Uranium Processing Facility (UPF)

    SciTech Connect

    Giffen, N.; Peterson, M.; Reasor, S.; Pounds, L.; Byrd, G.; Wiest, M. C.; Hill, C. C.

    2009-11-01

    This report summarizes the results of an environmental survey conducted at sites associated with the proposed Uranium Processing Facility (UPF) at the Y-12 National Security Complex in September-October 2009. The survey was conducted in order to evaluate potential impacts of the overall project. This project includes the construction of a haul road, concrete batch plant, wet soil storage area and dry soil storage area. The environmental surveys were conducted by natural resource experts at ORNL who routinely assess the significance of various project activities on the Oak Ridge Reservation (ORR). Natural resource staff assistance on this project included the collection of environmental information that can aid in project location decisions that minimize impacts to sensitive resource such as significant wildlife populations, rare plants and wetlands. Natural resources work was conducted in various habitats, corresponding to the proposed areas of impact. Thc credentials/qualifications of the researchers are contained in Appendix A. The proposed haul road traverses a number of different habitats including a power-line right-of-way. wetlands, streams, forest and mowed areas. It extends from what is known as the New Salvage Yard on the west to the Polaris Parking Lot on the east. This haul road is meant to connect the proposed concrete batch plant to the UPF building site. The proposed site of the concrete batch plant itself is a highly disturbed fenced area. This area of the project is shown in Fig. 1. The proposed Wet Soils Disposal Area is located on the north side of Bear Creek Road at the former Control Burn Study Area. This is a second growth arce containing thick vegetation, and extensive dead and down woody material. This area of the project is shown in Fig. 2. Thc dry soils storage area is proposed for what is currently known as the West Borrow Area. This site is located on the west side of Reeves Road south of Bear Creek Road. The site is an early successional field. This area of the project is shown in Fig. 2.

  18. Inorganic analyses of volatilized and condensed species within prototypic Defense Waste Processing Facility (DWPF) canistered waste

    SciTech Connect

    Jantzen, C.M.

    1992-06-30

    The high-level radioactive waste currently stored in carbon steel tanks at the Savannah River Site (SRS) will be immobilized in a borosilicate glass in the Defense Waste Processing Facility (DWPF). The canistered waste will be sent to a geologic repository for final disposal. The Waste Acceptance Preliminary Specifications (WAPS) require the identification of any inorganic phases that may be present in the canister that may lead to internal corrosion of the canister or that could potentially adversely affect normal canister handling. During vitrification, volatilization of mixed (Na, K, Cs)Cl, (Na, K, Cs){sub 2}SO{sub 4}, (Na, K, Cs)BF{sub 4}, (Na, K){sub 2}B{sub 4}O{sub 7} and (Na,K)CrO{sub 4} species from glass melt condensed in the melter off-gas and in the cyclone separator in the canister pour spout vacuum line. A full-scale DWPF prototypic canister filled during Campaign 10 of the SRS Scale Glass Melter was sectioned and examined. Mixed (NaK)CI, (NaK){sub 2}SO{sub 4}, (NaK) borates, and a (Na,K) fluoride phase (either NaF or Na{sub 2}BF{sub 4}) were identified on the interior canister walls, neck, and shoulder above the melt pour surface. Similar deposits were found on the glass melt surface and on glass fracture surfaces. Chromates were not found. Spinel crystals were found associated with the glass pour surface. Reference amounts of the halides and sulfates were found retained in the glass and the glass chemistry, including the distribution of the halides and sulfates, was homogeneous. In all cases where rust was observed, heavy metals (Zn, Ti, Sn) from the cutting blade/fluid were present indicating that the rust was a reaction product of the cutting fluid with glass and heat sensitized canister or with carbon-steel contamination on canister interior. Only minimal water vapor is present so that internal corrosion of the canister, will not occur.

  19. An analysis of workplace exposures to benzene over four decades at a petrochemical processing and manufacturing facility (1962-1999).

    PubMed

    Sahmel, J; Devlin, K; Burns, A; Ferracini, T; Ground, M; Paustenbach, D

    2013-01-01

    Benzene, a known carcinogen, can be generated as a by-product during the use of petroleum-based raw materials in chemical manufacturing. The aim of this study was to analyze a large data set of benzene air concentration measurements collected over nearly 40 years during routine employee exposure monitoring at a petrochemical manufacturing facility. The facility used ethane, propane, and natural gas as raw materials in the production of common commercial materials such as polyethylene, polypropylene, waxes, adhesives, alcohols, and aldehydes. In total, 3607 benzene air samples were collected at the facility from 1962 to 1999. Of these, in total 2359 long-term (>1 h) personal exposure samples for benzene were collected during routine operations at the facility between 1974 and 1999. These samples were analyzed by division, department, and job title to establish employee benzene exposures in different areas of the facility over time. Sampling data were also analyzed by key events over time, including changes in the occupational exposure limits (OELs) for benzene and key equipment process changes at the facility. Although mean benzene concentrations varied according to operation, in nearly all cases measured benzene quantities were below the OEL in place at the time for benzene (10 ppm for 1974-1986 and 1 ppm for 1987-1999). Decreases in mean benzene air concentrations were also found when data were evaluated according to 7- to 10-yr periods following key equipment process changes. Further, an evaluation of mortality rates for a retrospective employee cohort (n = 3938) demonstrated that the average personal benzene exposures at this facility (0.89 ppm for the period 1974-1986 and 0.125 ppm for the period 1987-1999) did not result in increased standardized mortality ratio (SMRs) for diseases or malignancies of the lymphatic system. The robust nature of this data set provides comprehensive exposure information that may be useful for assessing human benzene exposures at similar facilities. The data also provide a basis for comparable measured exposure levels and the potential for adverse health effects. These data may also prove beneficial for comparing relative exposure potential for production versus nonproduction operations and the relationship between area and personal breathing zone samples. PMID:23980839

  20. Improving the Quality of Services in Residential Treatment Facilities: A Strength-Based Consultative Review Process

    ERIC Educational Resources Information Center

    Pavkov, Thomas W.; Lourie, Ira S.; Hug, Richard W.; Negash, Sesen

    2010-01-01

    This descriptive case study reports on the positive impact of a consultative review methodology used to conduct quality assurance reviews as part of the Residential Treatment Center Evaluation Project. The study details improvement in the quality of services provided to youth in unmonitored residential treatment facilities. Improvements were…

  1. 78 FR 69539 - Removal of Attestation Process for Facilities Using H-1A Registered Nurses

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-20

    ...This final rule rescinds the regulations found which provided rules governing health care facilities using nonimmigrant foreign workers as registered nurses under the H-1A visa program. These subparts became obsolete after the authorizing statute and all extensions expired. Accordingly, the Department of Labor (the Department) is taking this action to remove regulations that no longer have......

  2. BIOLOGY AND POPULATION DYNAMICS OF THE TOP THREE PESTS IN FOOD PROCESSING FACILITIES

    Technology Transfer Automated Retrieval System (TEKTRAN)

    In this seminar presentation, an overview of the biology of three important stored-product pests (Indianmeal moth, red flour beetle, and warehouse beetle) will be presented. The factors that determine the relative importance of a particular pest species, such as type of facility, location, commodit...

  3. A Guide for Planning Facilities for Occupational Preparation Programs in Data Processing. Interim Report. Research 25.

    ERIC Educational Resources Information Center

    McIntosh, William A.

    This guide lists a series of pivotal questions about the educational program to be offered, and the answers to these questions bear directly on the numbers and kinds of instructional areas needed in the contemplated facilities. Much of the material is presented in a checklist format which allows for consideration of alternatives in facility…

  4. DESIGN CONSIDERATIONS FOR THE CONSTRUCTION AND OPERATION OF ETHANOL MANUFACTURING FACILITIES. PART II: PROCESS ENGINEERING CONSIDERATIONS

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Ethanol manufacturing facilities represent an important segment of our agricultural production system. The ethanol industry is currently experiencing a rapid expansion throughout the country, and is poised to substantially contribute to our countrys growing need for energy, especially as non-renew...

  5. Improving the Quality of Services in Residential Treatment Facilities: A Strength-Based Consultative Review Process

    ERIC Educational Resources Information Center

    Pavkov, Thomas W.; Lourie, Ira S.; Hug, Richard W.; Negash, Sesen

    2010-01-01

    This descriptive case study reports on the positive impact of a consultative review methodology used to conduct quality assurance reviews as part of the Residential Treatment Center Evaluation Project. The study details improvement in the quality of services provided to youth in unmonitored residential treatment facilities. Improvements were

  6. Design-Build Process for the Research Support Facility (RSF) (Book)

    SciTech Connect

    Not Available

    2012-06-01

    An in-depth look at how the U.S. DOE and NREL used a performance-based design-build contract to build the Research Support Facility (RSF); one of the most energy efficient office buildings in the world.

  7. Defense Waste Processing Facility: Report of task force on options to mitigate the effect of nitrite on DWPF operations

    SciTech Connect

    Randall, D.; Marek, J.C.

    1992-03-01

    The possibility of accumulating ammonium nitrate (an explosive) as well as organic compounds in the DWPF Chemical Processing Cell Vent System was recently discovered. A task force was therefore organized to examine ways to avoid this potential hazard. Of thirty-two processing/engineering options screened, the task force recommended five options, deemed to have the highest technical certainty, for detailed development and evaluation: Radiolysis of nitrite in the tetraphenylborate precipitate slurry feed in a new corrosion-resistant facility. Construction of a Late Washing Facility for precipitate washing before transfer to the DWPF; Just-in-Time'' precipitation; Startup Workaround by radiolysis of nitrite in the existing corrosion-resistant Pump Pit tanks; Ammonia venting and organics separation in the DWPF; and, Estimated costs and schedules are included in this report.

  8. Novel two-to-three hard hadronic processes and possible studies of generalized parton distributions at hadron facilities

    NASA Astrophysics Data System (ADS)

    Kumano, S.; Strikman, M.; Sudoh, K.

    2009-10-01

    We consider a novel class of hard branching hadronic processes a+b?c+d+e, where hadrons c and d have large and nearly opposite transverse momenta and large invariant energy, which is a finite fraction of the total invariant energy. We use color transparency logic to argue that these processes can be used to study quark generalized parton distributions (GPDs) for baryons and mesons in hadron collisions, hence complementing and adding to the studies of GPDs in the exclusive deep inelastic scattering processes. We propose that a number of GPDs can be investigated in hadron facilities such as Japan Proton Accelerator Research Complex facility and Gesellschaft fr Schwerionenforschung -Facility for Antiproton and Ion Research project. In this work, the GPDs for the nucleon and for the N?? transition are studied in the reaction N+N?N+?+B, where N, ?, and B are a nucleon, a pion, and a baryon (nucleon or ?), respectively, with a large momentum transfer between B (or ?) and the incident nucleon. In particular, the Efremov-Radyushkin-Brodsky-Lepage region of the GPDs can be measured in such exclusive reactions. We estimate the cross section of the processes N+N?N+?+B by using current models for relevant GPDs and information about large angle ?N reactions. We find that it will be feasible to measure these cross sections at the high-energy hadron facilities and to get novel information about the nucleon structure, for example, contributions of quark orbital angular momenta to the nucleon spin. The studies of N?? transition GPDs could be valuable also for investigating electromagnetic properties of the transition.

  9. REMOTE IN-CELL SAMPLING IMPROVEMENTS PROGRAM AT THESAVANNAH RIVER SITE (SRS) DEFENSE WASTE PROCESSING FACILITY (DWPF)

    SciTech Connect

    Marzolf, A

    2007-11-26

    Remote Systems Engineering (RSE) of the Savannah River National Lab (SRNL) in combination with the Defense Waste Processing Facility(DWPF) Engineering and Operations has evaluated the existing equipment and processes used in the facility sample cells for 'pulling' samples from the radioactive waste stream and performing equipment in-cell repairs/replacements. RSE has designed and tested equipment for improving remote in-cell sampling evolutions and reducing the time required for in-cell maintenance of existing equipment. The equipment within the present process tank sampling system has been in constant use since the facility start-up over 17 years ago. At present, the method for taking samples within the sample cells produces excessive maintenance and downtime due to frequent failures relative to the sampling station equipment and manipulator. Location and orientation of many sampling stations within the sample cells is not conducive to manipulator operation. The overextension of manipulators required to perform many in-cell operations is a major cause of manipulator failures. To improve sampling operations and reduce downtime due to equipment maintenance, a Portable Sampling Station (PSS), wireless in-cell cameras, and new commercially available sampling technology has been designed, developed and/or adapted and tested. The uniqueness of the design(s), the results of the scoping tests, and the benefits relative to in-cell operation and reduction of waste are presented.

  10. SUMMARY OF FY11 SULFATE RETENTION STUDIES FOR DEFENSE WASTE PROCESSING FACILITY GLASS

    SciTech Connect

    Fox, K.; Edwards, T.

    2012-05-08

    This report describes the results of studies related to the incorporation of sulfate in high level waste (HLW) borosilicate glass produced at the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF). A group of simulated HLW glasses produced for earlier sulfate retention studies was selected for full chemical composition measurements to determine whether there is any clear link between composition and sulfate retention over the compositional region evaluated. In addition, the viscosity of several glasses was measured to support future efforts in modeling sulfate solubility as a function of predicted viscosity. The intent of these studies was to develop a better understanding of sulfate retention in borosilicate HLW glass to allow for higher loadings of sulfate containing waste. Based on the results of these and other studies, the ability to improve sulfate solubility in DWPF borosilicate glasses lies in reducing the connectivity of the glass network structure. This can be achieved, as an example, by increasing the concentration of alkali species in the glass. However, this must be balanced with other effects of reduced network connectivity, such as reduced viscosity, potentially lower chemical durability, and in the case of higher sodium and aluminum concentrations, the propensity for nepheline crystallization. Future DWPF processing is likely to target higher waste loadings and higher sludge sodium concentrations, meaning that alkali concentrations in the glass will already be relatively high. It is therefore unlikely that there will be the ability to target significantly higher total alkali concentrations in the glass solely to support increased sulfate solubility without the increased alkali concentration causing failure of other Product Composition Control System (PCCS) constraints, such as low viscosity and durability. No individual components were found to provide a significant improvement in sulfate retention (i.e., an increase of the magnitude necessary to have a dramatic impact on blending, washing, or waste loading strategies for DWPF) for the glasses studied here. In general, the concentrations of those species that significantly improve sulfate solubility in a borosilicate glass must be added in relatively large concentrations (e.g., 13 to 38 wt % or more of the frit) in order to have a substantial impact. For DWPF, these concentrations would constitute too large of a portion of the frit to be practical. Therefore, it is unlikely that specific additives may be introduced into the DWPF glass via the frit to significantly improve sulfate solubility. The results presented here continue to show that sulfate solubility or retention is a function of individual glass compositions, rather than a property of a broad glass composition region. It would therefore be inappropriate to set a single sulfate concentration limit for a range of DWPF glass compositions. Sulfate concentration limits should continue to be identified and implemented for each sludge batch. The current PCCS limit is 0.4 wt % SO{sub 4}{sup 2-} in glass, although frit development efforts have led to an increased limit of 0.6 wt % for recent sludge batches. Slightly higher limits (perhaps 0.7-0.8 wt %) may be possible for future sludge batches. An opportunity for allowing a higher sulfate concentration limit at DWPF may lay lie in improving the laboratory experiments used to set this limit. That is, there are several differences between the crucible-scale testing currently used to define a limit for DWPF operation and the actual conditions within the DWPF melter. In particular, no allowance is currently made for sulfur partitioning (volatility versus retention) during melter processing as the sulfate limit is set for a specific sludge batch. A better understanding of the partitioning of sulfur in a bubbled melter operating with a cold cap as well as the impacts of sulfur on the off-gas system may allow a higher sulfate concentration limit to be established for the melter feed. This approach would have to be taken carefully to ensure that a sulfur salt layer is not formed on top of the melt pool while allowing higher sulfur based feeds to be processed through DWPF.

  11. Integration of the CERCLA and RCRA processes at an industrial facility using Texas risk reduction standards

    SciTech Connect

    Crossley, D.B.; Rogers, W.J.

    1995-12-31

    Industrial facilities in Texas that use, store and/or treat hazardous materials operate pursuant to the conditions of a Resource Conservation and Recovery Act (RCRA) permit and must also ensure compliance with provisions of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) if nominated to the National Priorities List of contaminated sites. While the CERCLA and RCRA programs have differing approaches, their objective is similar, i.e., mitigation of releases or threatened releases of toxic substances that may adversely impact human health or the environment. Recognizing the similarities in regulatory intent, a regulated facility may use Texas-promulgated risk reduction standards to establish risk-based contaminant specific cleanup levels for corrective actions pursuant to RCRA authority. Simultaneously, the facility will be evaluated for risk to human and ecological endpoints pursuant to CERCLA. A Baseline Risk Assessment (BRA) must be conducted to establish site-wide objectives that will be applied to individual solid waste management units ensuring compliance with all substantive requirements of CERCLA. The authors conclude that the parallel, integrated approach to these regulatory requirements will accelerate characterization/remediation of potential waste disposal sites, thereby reducing Environmental Restoration program expenditures.

  12. Ecological survey for the siting of the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility

    SciTech Connect

    Hoskinson, R.L.

    1994-05-01

    This report summarizes the results of field ecological surveys conducted by the Center for Integrated Environmental Technologies (CIET) on the Idaho National Engineering Laboratory (INEL) at four candidate locations for the siting of the Mixed and Low-Level Waste Treatment Facility (MLLWTF) and the Idaho Waste Processing Facility (IWPF). The purpose of these surveys was to comply with all Federal laws and Executive Orders to identify and evaluate any potential environmental impacts because of the project. The boundaries of the candidate location were marked with blaze-orange lath survey marker stakes by the project management. Global Positioning System (GPS) measurements of the marker stakes were made, and input to the Arc/Info{reg_sign} geographic information system (GIS). Field surveys were conducted to assess any potential impact to any important species, important habitats, and to any environmental study areas. The GIS location data was overlayed onto the INEL vegetation map and an analysis of vegetation classes on the locations was done. Results of the field surveys indicate use of Candidate Location {number_sign}1 by pygmy rabbits (Sylvilagus idahoensis) and expected use by them of Candidate Locations {number_sign}3 and {number_sign}9. Pygmy rabbits are categorized as a C2 species by the US Fish and Wildlife Service (USFWS). Two other C2 species, the ferruginous hawk (Buteo regalis) and the loggerhead shrike (Lanius ludovicianus) would also be expected to frequent the candidate locations. Candidate Location {number_sign}5 at the north end of the INEL is in the winter range of a large number of pronghorn antelope (Antilocapra americana).

  13. Integrated knowledge-based system for the process/product design and fault diagnosis of plastics recycling facilities

    SciTech Connect

    DiRaddo, R.W.; Pecora, L.; Lim, B.; Salloum, G.

    1995-11-01

    Plastics constitute approximately 8% by weight of a typical municipal solid waste stream. The reprocessing of plastic materials, subsequent to consumer use, is a complex problem requiring several processing stages, such as size reduction, sorting and separation, washing and drying, and finally reforming into a final part. The design of a plastics recycling facility is a difficult task that depends on the desired final product and the feedstock being considered. Once a plant becomes operational, processing problems will always be present, due primarily to the varying composition of the input stream. It is also important to address environmental safety, process and quality control issues. Also, optimal product design is critical with regard to final product performance and appropriate market application. With this in mind, an expert system technology has been developed in order to assist users in the process/product design and fault diagnosis of plastics recycling facilities. The technology can also be employed for optimal value-added product design. A modular approach is undertaken, so that the integration of the individual process units can be optimized to handle various waste stream compositions and desired final product specifications. An expert system is employed, with a built-in search routine, and the ability to incorporate new information. Sources for the information include several knowledge support specialists.

  14. Mines and mineral processing facilities in the vicinity of the March 11, 2011, earthquake in northern Honshu, Japan

    USGS Publications Warehouse

    Menzie, W. David; Baker, Michael S.; Bleiwas, Donald I.; Kuo, Chin

    2011-01-01

    U.S. Geological Survey data indicate that the area affected by the March 11, 2011, magnitude 9.0 earthquake and associated tsunami is home to nine cement plants, eight iodine plants, four iron and steel plants, four limestone mines, three copper refineries, two gold refineries, two lead refineries, two zinc refineries, one titanium dioxide plant, and one titanium sponge processing facility. These facilities have the capacity to produce the following percentages of the world's nonfuel mineral production: 25 percent of iodine, 10 percent of titanium sponge (metal), 3 percent of refined zinc, 2.5 percent of refined copper, and 1.4 percent of steel. In addition, the nine cement plants contribute about one-third of Japan's cement annual production. The iodine is a byproduct from production of natural gas at the Miniami Kanto gas field, east of Tokyo in Chiba Prefecture. Japan is the world's second leading (after Chile) producer of iodine, which is processed in seven nearby facilities.

  15. Risk-Based Disposal Plan for PCB Paint in the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Canal

    SciTech Connect

    R. A. Montgomery

    2008-05-01

    This Toxic Substances Control Act Risk-Based Polychlorinated Biphenyl Disposal plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex, Idaho National Laboratory Site, to address painted surfaces in the empty canal under 40 CFR 761.62(c) for paint, and under 40 CFR 761.61(c) for PCBs that may have penetrated into the concrete. The canal walls and floor will be painted with two coats of contrasting non-PCB paint and labeled as PCB. The canal is covered with open decking; the access grate is locked shut and signed to indicate PCB contamination in the canal. Access to the canal will require facility manager permission. Protective equipment for personnel and equipment entering the canal will be required. Waste from the canal, generated during ultimate Decontamination and Decommissioning, shall be managed and disposed as PCB Bulk Product Waste.

  16. Process-specific emission characteristics of volatile organic compounds (VOCs) from petrochemical facilities in the Yangtze River Delta, China.

    PubMed

    Mo, Ziwei; Shao, Min; Lu, Sihua; Qu, Hang; Zhou, Mengyi; Sun, Jin; Gou, Bin

    2015-11-15

    Process-specific emission characteristics of volatile organic compounds (VOCs) from petrochemical facilities were investigated in the Yangtze River Delta, China. Source samples were collected from various process units in the petrochemical, basic chemical, and chlorinated chemical plants, and were measured using gas chromatography-mass spectrometry/flame ionization detection. The results showed that propane (19.9%), propene (11.7%), ethane (9.5%) and i-butane (9.2%) were the most abundant species in the petrochemical plant, with propene at much higher levels than in petrochemical profiles measured in other regions. Styrene (15.3%), toluene (10.3%) and 1,3-butadiene (7.5%) were the major species in the basic chemical industry, while halocarbons, especially dichloromethane (15.2%) and chloromethane (7.5%), were substantial in the chlorinated chemical plant. Composite profiles were calculated using a weight-average approach based on the VOC emission strength of various process units. Emission profiles for an entire petrochemical-related industry were found to be process-oriented and should be established considering the differences in VOC emissions from various manufacturing facilities. The VOC source reactivity and carcinogenic risk potential of each process unit were also calculated in this study, suggesting that process operations mainly producing alkenes should be targeted for possible controls with respect to reducing the ozone formation potential, while process units emitting 1,3-butadiene should be under priority control in terms of toxicity. This provides a basis for further measurements of process-specific VOC emissions from the entire petrochemical industry. Meanwhile, more representative samples should be collected to reduce the large uncertainties. PMID:26179779

  17. RADIOLOGICAL CONTROLS FOR PLUTONIUM CONTAMINATED PROCESS EQUIPMENT REMOVAL FROM 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINSHING PLANT (PFP)

    SciTech Connect

    MINETTE, M.J.

    2007-05-30

    The 232-Z facility at Hanford's Plutonium Finishing Plant operated as a plutonium scrap incinerator for 11 years. Its mission was to recover residual plutonium through incinerating and/or leaching contaminated wastes and scrap material. Equipment failures, as well as spills, resulted in the release of radionuclides and other contamination to the building, along with small amounts to external soil. Based on the potential threat posed by the residual plutonium, the U.S. Department of Energy (DOE) issued an Action Memorandum to demolish Building 232-2, Comprehensive Environmental Response Compensation, and Liability Act (CERC1.A) Non-Time Critical Removal Action Memorandum for Removal of the 232-2 Waste Recovery Process Facility at the Plutonium Finishing Plant (04-AMCP-0486).

  18. Using the ABLE facility to observe urbanization effects on planetary boundary layer processes

    SciTech Connect

    Coulter, R.L.; Klazura, J.; Lesht, B.M.; Shannon, J.D.; Sisterson, D.L.; Wesely, M.L.

    1998-12-31

    The Argonne Boundary Layer Experiments (ABLE) facility, located in south central Kansas, east of Wichita, is devoted primarily to investigations of and within the planetary boundary layer (PBL), including the dynamics of the mixed layer during both day and night; effects of varying land use and landform; the interactive role of precipitation, runoff, and soil moisture; storm development; and energy budgets on scales of 10 to 100 km. With an expected lifetime of 10--15 years, the facility is well situated to observe the effects of gradual urbanization on PBL dynamics and structure as the Wichita urban area expands to the east and several small municipalities located within the study area expand. Combining the continuous measurements of ABLE with (1) ancillary continuous measurements of, for example, the Atmospheric Radiation Measurement (ARM) program and the Global Energy Water Cycle Experiment (GEWEX) programs and with (2) shorter, more intensive studies within ABLE, such as the Cooperative Atmosphere Surface Exchange Studies (CASES) Program, allows hypothesized features of urbanization, including heat island effects, precipitation enhancement, and modification of the surface energy budget partitioning, to be studied.

  19. Development of the Next-Generation Caustic-Side Solvent Extraction (NG-CSSX) Process for Cesium Removal from High-Level Tank Waste

    SciTech Connect

    Moyer, Bruce A; Bonnesen, Peter V; Delmau, Laetitia Helene; Sloop Jr, Frederick {Fred} V; Williams, Neil J; Birdwell Jr, Joseph F; Lee, Denise L; Leonard, Ralph; Fink, Samuel D; Peters, Thomas B.; Geeting, Mark W

    2011-01-01

    This paper describes the chemical performance of the Next-Generation Caustic-Side Solvent Extraction (NG-CSSX) process in its current state of development for removal of cesium from the alkaline high-level tank wastes at the Savannah River Site (SRS) in the US Department of Energy (USDOE) complex. Overall, motivation for seeking a major enhancement in performance for the currently deployed CSSX process stems from needs for accelerating the cleanup schedule and reducing the cost of salt-waste disposition. The primary target of the NG-CSSX development campaign in the past year has been to formulate a solvent system and to design a corresponding flowsheet that boosts the performance of the SRS Modular CSSX Unit (MCU) from a current minimum decontamination factor of 12 to 40,000. The chemical approach entails use of a more soluble calixarene-crown ether, called MaxCalix, allowing the attainment of much higher cesium distribution ratios (DCs) on extraction. Concurrently decreasing the Cs-7SB modifier concentration is anticipated to promote better hydraulics. A new stripping chemistry has been devised using a vitrification-friendly aqueous boric acid strip solution and a guanidine suppressor in the solvent, resulting in sharply decreased DCs on stripping. Results are reported herein on solvent phase behavior and batch Cs distribution for waste simulants and real waste together with a preliminary flowsheet applicable for implementation in the MCU. The new solvent will enable MCU to process a much wider range of salt feeds and thereby extend its service lifetime beyond its design life of three years. Other potential benefits of NG-CSSX include increased throughput of the SRS Salt Waste Processing Facility (SWPF), currently under construction, and an alternative modular near-tank application at Hanford.

  20. Salt Processing at the Savannah River Site: Results of Technology Down-Selection and Research and Development to Support New Salt Waste Processing Facility

    SciTech Connect

    Lang, K.; Gerdes, K.; Picha, K.; Spader, W.; McCullough, J.; Reynolds, J.; Morin, J. P.; Harmon, H. D.

    2002-02-26

    The Department of Energy's (DOE) Savannah River Site (SRS) high-level waste (HLW) program is responsible for storage, treatment, and immobilization of HLW for disposal. The Salt Processing Project (SPP) is the salt waste (water-soluble) treatment portion of this effort. The overall SPP encompasses the selection, design, construction, and operation of technologies to prepare the salt-waste feed material for immobilization at the site's Saltstone Production Facility (SPF) and vitrification facility (Defense Waste Processing Facility [DWPF]). Major constituents that must be removed from the salt waste and sent as feed to DWPF include cesium (Cs), strontium (Sr), and actinides. In April 2000, the DOE Deputy Secretary for Project Completion (EM-40) established the SRS Salt Processing Project Technical Working Group (TWG) to manage technology development of treatment alternatives for SRS high-level salt wastes. The separation alternatives investigated included three candidate Cs-removal processes selected, as well as actinide and Sr removal that are also required as a part of each process. The candidate Cs-removal processes are: crystalline Silicotitanate Non-Elutable Ion Exchange (CST); caustic Side Solvent Extraction (CSSX); and small Tank Tetraphenylborate Precipitation (STTP). The Tanks Focus Area was asked to assist DOE by managing the SPP research and development (R&D), revising roadmaps, and developing down-selection criteria. The down-selection decision process focused its analysis on three levels: (a) identification of goals that the selected technology should achieve, (b) selection criteria that are a measure of performance of the goal, and (c) criteria scoring and weighting for each technology alternative. After identifying the goals and criteria, the TWG analyzed R&D results and engineering data and scored the technology alternatives versus the criteria. Based their analysis and scoring, the TWG recommended CSSX as the preferred alternative. This recommendation was formalized in July 2001 when DOE published the Savannah River Site Salt Processing Alternatives Final Supplemental Environmental Impact Statement (SEIS) and was finalized in the DOE Record of Decision issued in October 2001.

  1. The application of Sunna dosimeter film for process control at industrial gamma- and electron beam irradiation facilities

    SciTech Connect

    Kovacs, Andras; Baranyai, M.; Fuochi, P. G.; Lavalle, M.; Corda, U.; Miller, Steven D.; Murphy, Mark K.; O'Doherty, J.

    2004-09-30

    The Sunna dosimeter was introduced for dose determination in the dose range of 50300kGy by measuring optically stimulated luminescence. The usefulness of the dosimeter film has already been shown in food irradiation for routine process control. The aim of the present study was to check the performance of the Sunna dosimeter film for process control in radiation sterilization under industrial processing conditions, i.e. at high activity gamma irradiators and at high energy electron beam facilities. To ensure similar irradiation conditions during calibration and routine irradiation in-plant calibration was performed by irradiating the Sunna dosimeters together with ethanolmonochlorobenzene transfer standard and alanine reference standard dosimeters. The Sunna dosimeters were then irradiated together with the routine dosimeter of the actual plant during regular production runs and the absorbed doses measured by the different dosimeters agreed within 2%(1?).

  2. Single-crystalline twinned ZnO nanoleaf structure via a facile hydrothermal process.

    PubMed

    Qiu, Jijun; Lil, Xiaomin; Gao, Xiangdong; Gan, Xiaoyan; He, Weizhen; Kim, Hyung-Kook; Hwang, Yoon-Hwae

    2011-03-01

    A single-crystalline twinned ZnO nanostructure with a 2-dimensional leaf-like morphology (nanoleaves) was synthesized using a facile hydrothermal strategy. The ZnO nanoleaves had 2-fold symmetric branches, which were identified by the existence of an inversion domain boundary (IDB) along the [2110] growth direction of the ribbon-like stems with both side surfaces of the stems terminated with a chemically active Zn-(0001) plane. A proposed growth mechanism suggested that the formation of IDB and the leaf-like shape are related to the dissolution of seed particles on the substrate surfaces and an OH- shielding effect in solution, respectively. Optical measurements revealed visible emission, suggesting the possession of defects in the as-grown and annealed ZnO nanoleaves. In addition, various ZnO nanostructures were synthesized by simply controlling the fabrication conditions. PMID:21449366

  3. Aerobic biodegradation of sludge with high hydrocarbon content generated by a Mexican natural gas processing facility.

    PubMed

    Roldn-Carrillo, T; Castorena-Corts, G; Zapata-Peasco, I; Reyes-Avila, J; Olgun-Lora, P

    2012-03-01

    The biodegradation of oil sludge from Mexican sour gas and petrochemical facilities contaminated with a high content of hydrocarbons, 334.7 7.0 g kg(-1) dry matter (dm), was evaluated. Studies in microcosm systems were carried out in order to determine the capacity of the native microbiota in the sludge to reduce hydrocarbon levels under aerobic conditions. Different carbon/nitrogen/phosphorous (C/N/P) nutrient ratios were tested. The systems were incubated at 30 C and shaken at 100 rpm. Hydrocarbon removals from 32 to 51% were achieved in the assays after 30 days of incubation. The best assay had C/N/P ratio of 100/1.74/0.5. The results of the Microtox() and Ames tests indicated that the original sludge was highly toxic and mutagenic, whereas the best assay gave a final product that did not show toxicity or mutagenicity. PMID:21600691

  4. HWMA/RCRA Closure Plan for the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System

    SciTech Connect

    K. Winterholler

    2007-01-31

    This Hazardous Waste Management Act/Resource Conservation and Recovery Act closure plan was developed for the Test Reactor Area Fluorinel Dissolution Process Mockup and Gamma Facilities Waste System, located in Building TRA-641 at the Reactor Technology Complex (RTC), Idaho National Laboratory Site, to meet a further milestone established under the Voluntary Consent Order SITE-TANK-005 Action Plan for Tank System TRA-009. The tank system to be closed is identified as VCO-SITE-TANK-005 Tank System TRA-009. This closure plan presents the closure performance standards and methods for achieving those standards.

  5. 75 FR 71733 - Requirements for Measurement Facilities Used for the Royalty Valuation of Processed Natural Gas

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-24

    ... with established standards governing gas and liquid hydrocarbon production measurement. We have... measurement of Federal production at gas processing plants when royalty is reported and paid on processed gas..., sampling, or recording devices associated with the measurement of inlet production, residue gas, fuel...

  6. Process Flow Chart for Immobilizing of Radioactive High Concentration Sodium Hydroxide Product from the Sodium Processing Facility at the BN-350 Nuclear power plant in Aktau, Kazakhstan

    SciTech Connect

    Burkitbayev, M.; Omarova, K.; Tolebayev, T.; Galkin, A.; Bachilova, N.; Blynskiy, A.; Maev, V.; Wells, D.; Herrick, A.; Michelbacher, J.

    2008-07-01

    This paper describes the results of a joint research investigations carried out by the group of Kazakhstan, British and American specialists in development of a new material for immobilization of radioactive 35% sodium hydroxide solutions from the sodium coolant processing facility of the BN-350 nuclear power plant. The resulting solid matrix product, termed geo-cement stone, is capable of isolating long lived radionuclides from the environment. The physico-mechanical properties of geo-cement stone have been investigated and the flow chart for its production verified in a full scale experiments. (author)

  7. RESEARCH AND DEVELOPMENT OF AN INTEGRAL SEPARATOR FOR A CENTRIFUGAL GAS PROCESSING FACILITY

    SciTech Connect

    LANCE HAYS

    2007-02-27

    A COMPACT GAS PROCESSING DEVICE WAS INVESTIGATED TO INCREASE GAS PRODUCTION FROM REMOTE, PREVIOUSLY UN-ECONOMIC RESOURCES. THE UNIT WAS TESTED ON AIR AND WATER AND WITH NATURAL GAS AND LIQUID. RESULTS ARE REPORTED WITH RECOMMENDATIONS FOR FUTURE WORK.

  8. Characterisation and treatment of VOCs in process water from upgrading facilities for compressed biogas (CBG).

    PubMed

    Nilsson Påledal, S; Arrhenius, K; Moestedt, J; Engelbrektsson, J; Stensen, K

    2016-02-01

    Compression and upgrading of biogas to vehicle fuel generates process water, which to varying degrees contains volatile organic compounds (VOCs) originating from the biogas. The compostion of this process water has not yet been studied and scientifically published and there is currently an uncertainty regarding content of VOCs and how the process water should be managed to minimise the impact on health and the environment. The aim of the study was to give an overview about general levels of VOCs in the process water. Characterisation of process water from amine and water scrubbers at plants digesting waste, sewage sludge or agricultural residues showed that both the average concentration and composition of particular VOCs varied depending on the substrate used at the biogas plant, but the divergence was high and the differences for total concentrations from the different substrate groups were only significant for samples from plants using waste compared to residues from agriculture. The characterisation also showed that the content of VOCs varied greatly between different sampling points for same main substrate and between sampling occasions at the same sampling point, indicating that site-specific conditions are important for the results which also indicates that a number of analyses at different times are required in order to make an more exact characterisation with low uncertainty. Inhibition of VOCs in the anaerobic digestion (AD) process was studied in biomethane potential tests, but no inhibition was observed during addition of synthetic process water at concentrations of 11.6 mg and 238 mg VOC/L. PMID:26694791

  9. Radioactive Carbon Isotope Monitoring System Based on Cavity Ring-down Laser Spectroscopy for Decommissioning Process of Nuclear Facilities

    NASA Astrophysics Data System (ADS)

    Tomita, Hideki; Watanabe, Kenichi; Takiguchi, Yu; Kawarabayashi, Jun; Iguchi, Tetsuo

    In decommissioning process of nuclear facilities, large amount of radioactive isotopes are discharged as waste. Radioactive carbon isotope (14C) is one of the key nuclides to determine the upper limit of concentration in the waste disposal. In particular, 14C on the graphite reactor decommissioning should be separated from stable carbon isotopes (12C and 13C) and monitored for the public health and safety. We propose an isotope analysis system based on cavity ring-down laser spectroscopy (CRDS) to monitor the carbon isotopes (12C, 13C and 14C) in the isotope separation process for the graphite reactor decommissioning. This system is compact and suitable for a continuous monitoring, because the concentration of molecules including the carbon isotope is derived from its photo absorbance with ultra high sensitive laser absorption spectroscopy. Here are presented the necessary conditions of CRDS system for 14C isotope analysis through the preliminary experimental results of 13C isotope analysis with a prototype system.

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

    SciTech Connect

    Jacobs, R.A.; Elder, H.H.

    1998-03-01

    The DWPF at the Department of Energy`s (DOE) Savannah River Site (SRS) began radioactive operations in December of 1995. The High Level Waste Tank Farm at SRS contains approximately thirty three million gallons of salt, supernate, and insoluble sludge wastes accumulated during more than three decades of weapons manufacture. In the DWPF, the radioactive components from this waste will ultimately be processed into a stable, borosilicate glass for long-term storage in a geological repository.The feeds to the DWPF are pretreated in a number of steps. Insoluble sludges, primarily aluminum, iron and other transition metals, are combined from several tanks, treated by caustic dissolution of aluminum and washed to remove soluble salts; these materials are removed to increase waste loading in the glass produced by the DWPF.The water soluble radioactive species in the salt and supernate, primarily cesium and actinides, are precipitated by sodium tetraphenylborate (NaTPB) or adsorbed onto sodium titanate. The resulting solids are also washed to remove excessive soluble salts before feeding to the DWPF. The soluble species removed by washing are disposed of as low level radioactive waste in a concrete form known as Saltstone. The presentation includes a brief overview of the High Level Waste system, pretreatment, and disposition of the various streams.The washed tetraphenylborate precipitates of cesium and potassium are hydrolyzed by copper catalyzed formic acid hydrolysis in the Salt Processing Cell (SPC) to yield soluble formates, boric acid, benzene and minor organic byproducts.The benzene and most of the organic byproducts are then steam stripped. The resulting aqueous hydrolysis product, including the still insoluble actinides adsorbed onto sodium titanate, is combined in the Chemical Processing Cell (CPC) with the insoluble sludge which has been treated with nitric acid and formic acid to remove mercury and to adjust the glass redox. Borosilicate glass frit is added and after assuring the melter feed meets glass quality and processing requirements, the slurry is fed to the melter producing glass which is poured into stainless steel canisters. The canisters are sealed, blasted to remove surface contamination, and welded prior to temporary storage in the Glass Waste Storage Building (GWSB). An overview of the DWPF process and its chemistry is included.The composition of the feeds is of primary importance to the DWPF. Critical factors determined by the feeds are related to safety, process design and operability, and glass quality.The Safety Analysis Report (SAR) source term, process shielding, potential for criticality, and generation of flammable gases are safety factors related to feed composition. Canister heat generation, NO{sub x} emissions, and corrosive species are process design parameters determined by feed composition. Nitrite in the washed precipitate, glass insolubles, glass liquidus (temperature of complete melting) and glass melt viscosity are operability parameters determined by composition. And glass durability is the critical quality parameter which requires knowledge and control of the feed compositions. The basis for each of these composition related factors is presented and the system for specifying feed acceptance criteria is described.The composition, and thus the durability, of the glass is determined by the mixing ratios of sludge insolubles, aqueous hydrolysis product, and frit. The frit is a purchased raw material; naturally, its composition is essentially fixed. Also, the glass components in the aqueous hydrolysis product are essentially invariant because the cesium plus potassium to boron ratio is unity, essentially all of the water is evaporated, and the sodium titanate concentration is carefully controlled in the precipitation process.Therefore, the sludge composition is the primary source of feed variability. The combination of process and tank farm history, strategic tank samples, system waste removal plans, and process modeling which project sludge batch composition and evaluate process related pa

  11. Design of generic coal conversion facilities: Process release---Refining and upgrading

    SciTech Connect

    Not Available

    1991-09-01

    The refinery and upgrade process development unit (PDU) is designed to upgrade liquid hydrocarbon products from the direct and indirect liquefaction PDU's to transportation fuels. The refinery will comprise of the following reactor systems: (a) Hydrotreating (b) Hydrocracking (c) Reforming. The three reactor systems will share common feed preparation, product separation and fractionation sections. The refinery is being designed to operate independently of the other PDU's. The use of common feed and product handling systems will permit operation of one process reactor system at a time in the refinery. In addition, the hydrotreater and hydrocracker will be operable in series. The process is designed to utilize intermediate storage and maximize the use of equipment.

  12. Design of generic coal conversion facilities: Process release---Refining and upgrading

    SciTech Connect

    Not Available

    1991-09-01

    The refinery and upgrade process development unit (PDU) is designed to upgrade liquid hydrocarbon products from the direct and indirect liquefaction PDU`s to transportation fuels. The refinery will comprise of the following reactor systems: (a) Hydrotreating (b) Hydrocracking (c) Reforming. The three reactor systems will share common feed preparation, product separation and fractionation sections. The refinery is being designed to operate independently of the other PDU`s. The use of common feed and product handling systems will permit operation of one process reactor system at a time in the refinery. In addition, the hydrotreater and hydrocracker will be operable in series. The process is designed to utilize intermediate storage and maximize the use of equipment.

  13. Extrinsic and intrinsic complexities of the Los Alamos Plutonium Processing Facility

    SciTech Connect

    Bearse, R.C.; Longmire, V.L.; Roberts, N.J.

    1985-01-01

    Analysis of the data obtained in one year of plutonium accounting at Los Alamos reveals significant complexity. Much of this complexity arises from the complexity of the processes themselves. Additional complexity is induced by errors in the data entry process. It is important to note that there is no evidence that this complexity is adversely affecting the accounting in the plant. We have been analyzing transaction data from fiscal year 1983 processing. This study involved 62,595 transactions. The data have been analyzed using the relational database program INGRES on a VAX 11/780 computer. This software allows easy manipulation of the original data and subsets drawn from it. We have been attempting for several years to understand the global features of the TA-55 accounting data. This project has underscored several of the system's complexities. Examples that will be reported here include audit trails, lot-name multiplicity, etc.

  14. Technology Readiness Assessment of Department of Energy Waste Processing Facilities: Lessons Learned, Next Steps

    SciTech Connect

    Alexander, D.; Gerdes, K.; Holton, L.; Krahn, S.; Sutter, H.

    2008-07-01

    In an effort to improve its oversight of major waste treatment construction projects DOE has piloted a Technical Readiness Assessment/Technology Maturation Plan (TRA/TMP) process based on similar processes employed by the United States Department of Defense (DoD) and the National Aeronautics and Space Administration (NASA. DOE has carried out TRAs for the Hanford Waste Treatment and Immobilization Plant (WTP), for supplemental treatment technologies that may be employed to process Hanford low activity waste (LAW), for the removal of Hanford K-Basin waste, and for treatment technologies for Savannah River Site's tank 48. This paper describes the TRA/TMP methodology and discusses the findings and lessons learned during its application. The paper also discusses the next steps in the technical assessment of DOE environmental projects. (authors)

  15. A facile process for soak-and-peel delamination of CVD graphene from substrates using water.

    PubMed

    Gupta, Priti; Dongare, Pratiksha D; Grover, Sameer; Dubey, Sudipta; Mamgain, Hitesh; Bhattacharya, Arnab; Deshmukh, Mandar M

    2014-01-01

    We demonstrate a simple technique to transfer chemical vapour deposited (CVD) graphene from copper and platinum substrates using a soak-and-peel delamination technique utilizing only hot deionized water. The lack of chemical etchants results in cleaner CVD graphene films minimizing unintentional doping, as confirmed by Raman and electrical measurements. The process allows the reuse of substrates and hence can enable the use of oriented substrates for growth of higher quality graphene, and is an inherently inexpensive and scalable process for large-area production. PMID:24457558

  16. A facile process for soak-and-peel delamination of CVD graphene from substrates using water

    PubMed Central

    Gupta, Priti; Dongare, Pratiksha D.; Grover, Sameer; Dubey, Sudipta; Mamgain, Hitesh; Bhattacharya, Arnab; Deshmukh, Mandar M.

    2014-01-01

    We demonstrate a simple technique to transfer chemical vapour deposited (CVD) graphene from copper and platinum substrates using a soak-and-peel delamination technique utilizing only hot deionized water. The lack of chemical etchants results in cleaner CVD graphene films minimizing unintentional doping, as confirmed by Raman and electrical measurements. The process allows the reuse of substrates and hence can enable the use of oriented substrates for growth of higher quality graphene, and is an inherently inexpensive and scalable process for large-area production. PMID:24457558

  17. Low frequency of infertility among workers in a borate processing facility.

    PubMed

    Sayli, Bekir Sitki

    2003-01-01

    In order to rule out the possibility of omitting some individuals in the study at field visits described in previous articles, either because of the reluctance of the subject or because of his appointment elsewhere, fertility and infertility states of borate workers of the Borax and Acid Plants in Bandirma, Balikesir are given. Balikesir is one of the four provinces with large borate deposits of Turkey, and Bandirma is 1 of its 19 districts. This county is relatively far away from borate deposits, and drinking water piped out through the springs has a boron amount between 0.10 and 0.82 ppm B. That the participants are occupationally exposed to the mineral in essence is therefore conceivable. At the first phase of the investigation, 191 workers were interviewed, as detailed previously. Among these, there were six infertiles of the primary type with a rate 3.1%. Boron-unrelated infertile couples among sibs were found to be 2.6-3.6%, and 3.2% for three generation marriages-none being higher than those revealed in different sets of controls. In the second stage of work, computerized files of all workers of the facility and all employees of the general management sharing the same location were checked without an interview. Twenty-four subjects (3.4%) out of 712 workers were childless versus 2.7% among 108 employees, and 2.2% among 91 workers of a distantly located sulfuric acid plant of the same complex. The differences were not significant, and these recent findings support the conclusion already reached almost unambiguously that boron exposure at the present levels does not interfere with human reproduction. PMID:12835486

  18. Treating wastewater from a pharmaceutical formulation facility by biological process and ozone.

    PubMed

    Lester, Yaal; Mamane, Hadas; Zucker, Ines; Avisar, Dror

    2013-09-01

    Wastewater from a pharmaceutical formulation facility (TevaKS, Israel) was treated with a biological activated-sludge system followed by ozonation. The goal was to reduce the concentrations of the drugs carbamazepine (CBZ) and venlafaxine (VLX) before discharging the wastewater to the municipal wastewater treatment plant (WWTP). Both drugs were detected at extremely high concentrations in TevaKS raw wastewater ([VLX]=11.72 2.2mg/L, [CBZ]=0.84 0.19 mg/L), and resisted the biological treatment. Ozone efficiently degraded CBZ: at an O3 dose-to-dissolved organic carbon ratio of 0.55 (O3/DOC), the concentration of CBZ was reduced by >99%. A lower removal rate was observed for VLX, which was decreased by ? 98% at the higher O3/DOC ratio of 0.87. Decreasing the pH of the biologically treated effluent from 7 to 5 significantly increased the ozone degradation rate of CBZ, while decreasing the degradation rate of VLX. Ozone treatment did not alter the concentration of the effluent's DOC and filtered chemical oxygen demand (CODf). However, a significant increase was recorded (following ozonation) in the effluent's biological oxygen demand (BOD5) and the BOD5/CODf ratio. This implies an increase in the effluent's biodegradability, which is highly desirable if ozonation is followed by a domestic biological treatment. Different organic byproducts were formed following ozone reaction with the target pharmaceuticals and with the effluent organic matter; however, these byproducts are expected to be removed during biological treatment in the municipal WWTP. PMID:23764586

  19. Distribution and identification of culturable airborne microorganisms in a Swiss milk processing facility.

    PubMed

    Brandl, Helmut; Fricker-Feer, Claudia; Ziegler, Dominik; Mandal, Jyotshna; Stephan, Roger; Lehner, Angelika

    2014-01-01

    Airborne communities (mainly bacteria) were sampled and characterized (concentration levels and diversity) at 1 outdoor and 6 indoor sites within a Swiss dairy production facility. Air samples were collected on 2 sampling dates in different seasons, one in February and one in July 2012 using impaction bioaerosol samplers. After cultivation, isolates were identified by mass spectrometry (matrix-assisted laser desorption/ionization-time-of-flight) and molecular (sequencing of 16S rRNA and rpoB genes) methods. In general, total airborne particle loads and total bacterial counts were higher in winter than in summer, but remained constant within each indoor sampling site at both sampling times (February and July). Bacterial numbers were generally very low (<100 cfu/m(3) of air) during the different steps of milk powder production. Elevated bacterial concentrations (with mean values of 391 ± 142 and 179 ± 33 cfu/m(3) of air during winter and summer sampling, respectively; n=15) occurred mainly in the "logistics area," where products in closed tins are packed in secondary packaging material and prepared for shipping. However, total bacterial counts at the outdoor site varied, with a 5- to 6-fold higher concentration observed in winter compared with summer. Twenty-five gram-positive and gram-negative genera were identified as part of the airborne microflora, with Bacillus and Staphylococcus being the most frequent genera identified. Overall, the culturable microflora community showed a composition typical and representative for the specific location. Bacterial counts were highly correlated with total airborne particles in the size range 1 to 5 µm, indicating that a simple surveillance system based upon counting of airborne particles could be implemented. The data generated in this study could be used to evaluate the effectiveness of the dairy plant's sanitation program and to identify potential sources of airborne contamination, resulting in increased food safety. PMID:24210492

  20. APPLICATIONS OF MULTICOMPONENT ASSEMBLY PROCESSES TO THE FACILE SYNTHESES OF DIVERSELY FUNCTIONALIZED NITROGEN HETEROCYCLES

    PubMed Central

    Donald, James R.; Granger, Brett A.; Hardy, Simon; Sahn, James J.; Martin, Stephen F.

    2012-01-01

    Several multicomponent assembly processes have been developed for the synthesis of intermediates that may be elaborated by a variety of cyclizations to generate a diverse array of highly functionalized heterocycles from readily-available starting materials. The overall approach enables the efficient preparation of libraries of small molecules derived from fused, privileged scaffolds. PMID:22451742

  1. Engineering process and cost model for a conventional corn wet milling facility

    Technology Transfer Automated Retrieval System (TEKTRAN)

    Conventional wet milling of corn is a process designed for the recovery and purification of starch and several coproducts (germ, gluten, fiber and steep liquor). The total starch produced by the wet milling industry in the USA in 2004 equaled 21.5 billion kilograms, including modified starches and ...

  2. ASSESSMENT OF THE BACTERIOLOGICAL QUALITY OF COMPOST FROM A YARD WASTE PROCESSING FACILITY

    EPA Science Inventory

    Citizen concern over possible pathogenic microorganism contamination in compost and in a runoff collection pond prompted a U.S. Environmental Protection Agency (EPA) investigation. ne out of eight samples collected from the distribution pile at a yard waste compost processing fac...

  3. Standard practice for dosimetry in electron and bremsstrahlung irradiation facilities for food processing. ASTM standard

    SciTech Connect

    1998-06-01

    This practice is under the jurisdiction of ASTM Committee E-10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.01 on Dosimetry for Radiation Processing. Current edition approved Jan. 10, 1998. Published June 1998. Originally published as E 1431-91. Last previous edition E 1431-91.

  4. ASSESSMENT OF THE BACTERIOLOGICAL QUALITY OF COMPOST FROM A YARD WASTE PROCESSING FACILITY

    EPA Science Inventory

    Citizen concern over possible pathogenic microorganism contamination in compost and in a runoff collection pond prompted a U.S. Environmental Protection Agency (EPA) investigation. One out of eight samples collected from the distribution pile at a yard waste compost processing f...

  5. 40 CFR 80.513 - What provisions apply to transmix processing facilities?

    Code of Federal Regulations, 2011 CFR

    2011-07-01

    ... applies to the volume of diesel fuel produced by such a transmix processor using these processes, and does... May 31, 2010, motor vehicle diesel fuel produced by a transmix processor is subject to the 500 ppm... May 31, 2010, NRLM diesel fuel produced by a transmix processor is exempt from the standards of ...

  6. Facile fabrication of superhydrophobic surfaces on wood substrates via a one-step hydrothermal process

    NASA Astrophysics Data System (ADS)

    Liu, Ming; Qing, Yan; Wu, Yiqiang; Liang, Jin; Luo, Sha

    2015-03-01

    Superhydrophobic nanocomposite surfaces were successfully fabricated on wood substrates via a one-step hydrothermal process. The morphology of the nanocomposite surfaces was characterized using scanning electron microscopy (SEM), and the elemental composition was determined via energy-dispersive X-ray spectrometry (EDS), X-ray diffraction (XRD) analysis, and Fourier transform infrared (FTIR) spectroscopy. The results indicated that the crystallization of the anatase phase of TiO2 was prevented because of the presence of vinyltriethoxysilane [VTES, CH2CHSi(OC2H5)3] during the hydrothermal process. In addition, the nanocomposite contained Ti/Si particles with diameters ranging from 50 to 100 nm that thoroughly covered the wood substrate. Furthermore, the roughness coupled with the presence of low surface free energy groups led to superhydrophobicity; the static water contact angle (WCA) was as high as 153, and the sliding angle was very low.

  7. The LHEA PDP 11/70 graphics processing facility users guide

    NASA Technical Reports Server (NTRS)

    1978-01-01

    A compilation of all necessary and useful information needed to allow the inexperienced user to program on the PDP 11/70. Information regarding the use of editing and file manipulation utilities as well as operational procedures are included. The inexperienced user is taken through the process of creating, editing, compiling, task building and debugging his/her FORTRAN program. Also, documentation on additional software is included.

  8. Goldratt's thinking process applied to the budget constraints of a Texas MHMR facility.

    PubMed

    Taylor, Lloyd J; Churchwell, Lana

    2004-01-01

    Managers for years have known that the best way to run a business is to constantly be looking for ways to improve the way to do business. The barrier has been the ability to identify and solve the right problems. Eliyahu Goldratt (1992c), in his book The Goal, uses a love story format to illustrate his "Theory of Constraints." In Goldratt's (1994) next book, It's Not Luck, he further illustrates this powerful technique called "The Thinking Process" which is based on the Socratic method, using the "if ... then" reasoning process, The first step is to identify UDEs or undesirable effects within the organization and then use these UDEs to create a Current Reality Tree (CRT) which helps to identify the core problem. Next, use an Evaporating Cloud to come up with ideas and a way to break the constraint. Finally, use the injections in the Evaporating Cloud to create a Future Reality Tree, further validating the idea and making sure it does not create any negative effects. In this article, the "Thinking Process" will be used to identify and solve problems related to the General Medical Department of an MHMR State Hospital. PMID:15704641

  9. Risk-Based Decision Process for Accelerated Closure of a Nuclear Weapons Facility

    SciTech Connect

    Butler, L.; Norland, R. L.; DiSalvo, R.; Anderson, M.

    2003-02-25

    Nearly 40 years of nuclear weapons production at the Rocky Flats Environmental Technology Site (RFETS or Site) resulted in contamination of soil and underground systems and structures with hazardous substances, including plutonium, uranium and hazardous waste constituents. The Site was placed on the National Priority List in 1989. There are more than 370 Individual Hazardous Substance Sites (IHSSs) at RFETS. Accelerated cleanup and closure of RFETS is being achieved through implementation and refinement of a regulatory framework that fosters programmatic and technical innovations: (1) extensive use of ''accelerated actions'' to remediate IHSSs, (2) development of a risk-based screening process that triggers and helps define the scope of accelerated actions consistent with the final remedial action objectives for the Site, (3) use of field instrumentation for real time data collection, (4) a data management system that renders near real time field data assessment, and (5) a regulatory agency consultative process to facilitate timely decisions. This paper presents the process and interim results for these aspects of the accelerated closure program applied to Environmental Restoration activities at the Site.

  10. A facile method to determine pore size distribution in porous scaffold by using image processing.

    PubMed

    Lo Re, G; Lopresti, F; Petrucci, G; Scaffaro, R

    2015-09-01

    Image processing permits scientists to investigate morphological properties of three-dimensional structures starting from their bi-dimensional gray-scale representation. In many cases porous structure with complex architecture has to be designed in order to attempt specific properties such in the case of scaffold for tissue engineering. Traditional morphological characterization, like scanning electron microscopy, should be coupled with quantitative information such as pore size distribution (PSD) in order to get a deeper understanding of the influence of the porous structure on tissue regeneration processes and on other related applications, it is remarkable to study a quantitative analysis of porosity and of pores dimension. In this work it was developed as a software able to accomplish the segmentation of images containing pores of any geometry in a semi-automatic way with the aim to measure the PSD. Case study constituted by PLA porous scaffolds with different pore size was adopted. Results indicate that image processing methods well fit the pore size features of PLA scaffolds, overcoming the limits of the more invasive porosimetry techniques. PMID:26026425

  11. CHALLENGES OF PRESERVING HISTORIC RESOURCES DURING THE D & D OF HIGHLY CONTAMINATED HISTORICALLY SIGNIFICANT PLUTONIUM PROCESS FACILITIES

    SciTech Connect

    HOPKINS, A.M.

    2006-03-17

    The Manhattan Project was initiated to develop nuclear weapons for use in World War II. The Hanford Engineer Works (HEW) was established in eastern Washington State as a production complex for the Manhattan Project. A major product of the HEW was plutonium. The buildings and process equipment used in the early phases of nuclear weapons development are historically significant because of the new and unique work that was performed. When environmental cleanup became Hanford's central mission in 1991, the Department of Energy (DOE) prepared for the deactivation and decommissioning of many of the old process facilities. In many cases, the process facilities were so contaminated, they faced demolition. The National Historic Preservation Act (NHPA) requires federal agencies to evaluate the historic significance of properties under their jurisdiction for eligibility for inclusion in the National Register of Historic Places before altering or demolishing them so that mitigation through documentation of the properties can occur. Specifically, federal agencies are required to evaluate their proposed actions against the effect the actions may have on districts, sites, buildings or structures that ere included or eligible for inclusion in the National Register. In an agreement between the DOE'S Richland Operations Office (RL), the Washington State Historic Preservation Office (SHPO) and the Advisory Council on Historic Preservation (ACHP), the agencies concurred that the Hanford Site Historic District is eligible for listing on the National Register of Historic Places and that a Sitewide Treatment Plan would streamline compliance with the NHPA while allowing RL to manage the cleanup of the Hanford Site. Currently, many of the old processing buildings at the Plutonium Finishing Plant (PFP) are undergoing deactivation and decommissioning. RL and Fluor Hanford project managers at the PFP are committed to preserving historical artifacts of the plutonium production process. They must also ensure the safety of workers and the full decontamination of buildings or artifacts if they are to be preserved. This paper discusses the real time challenges of working safely, decontaminating process equipment, preserving historical structures and artifacts and documenting their history at PFP.

  12. The Challenges of Preserving Historic Resources During the Deactivation and Decommissioning of Highly Contaminated Historically Significant Plutonium Process Facilities

    SciTech Connect

    Hopkins, A.; Minette, M.; Sorenson, D.; Heineman, R.; Gerber, M.; Charboneau, S.; Bond, F.

    2006-07-01

    The Manhattan Project was initiated to develop nuclear weapons for use in World War II. The Hanford Engineer Works (HEW) was established in eastern Washington State as a production complex for the Manhattan Project. A major product of the HEW was plutonium. The buildings and process equipment used in the early phases of nuclear weapons development are historically significant because of the new and unique work that was performed. When environmental cleanup became Hanford's central mission in 1991, the Department of Energy (DOE) prepared for the deactivation and decommissioning of many of the old process facilities. In many cases, the process facilities were so contaminated, they faced demolition. The National Historic Preservation Act (NHPA) requires federal agencies to evaluate the historic significance of properties under their jurisdiction for eligibility for inclusion in the National Register of Historic Places before altering or demolishing them so that mitigation through documentation of the properties can occur. Specifically, federal agencies are required to evaluate their proposed actions against the effect the actions may have on districts, sites, buildings or structures that are included or eligible for inclusion in the National Register. In an agreement between the DOE's Richland Operations Office (RL), the Washington State Historic Preservation Office (SHPO) and the Advisory Council on Historic Preservation (ACHP), the agencies concurred that the Hanford Site Historic District is eligible for listing on the National Register of Historic Places and that a Site-wide Treatment Plan would streamline compliance with the NHPA while allowing RL to manage the cleanup of the Hanford Site. Currently, many of the old processing buildings at the Plutonium Finishing Plant (PFP) are undergoing deactivation and decommissioning. RL and Fluor Hanford project managers at the PFP are committed to preserving historical artifacts of the plutonium production process. They must also ensure the safety of workers and the full decontamination of buildings or artifacts if they are to be preserved. This paper discusses the real time challenges of working safely, decontaminating process equipment, preserving historical structures and artifacts and documenting their history at PFP. (authors)

  13. Design, development and qualification of a microbiological challenge facility to assess the effectiveness of BFS aseptic processing.

    PubMed

    Leo, F; Poisson, P; Sinclair, C S; Tallentire, A

    2005-01-01

    A programme of work has been initiated to further the understanding of the impact of the environment surrounding a Blow/Fill/Seal (BFS) machine upon the microbiological quality of processed product. A dedicated facility (Challenge Room) has been constructed and qualified to provide for the production and containment of dispersions of micro organisms in air of a room housing an operating BFS machine of a given style and configuration. The facility achieves homogeneous distribution of generated dispersions throughout the Challenge Room air, including that within and close to the critical area in which aseptic BFS operations occur. Generated microbial dispersions can be maintained in the room over extended time periods (up to 600 min) at a desired concentration within the range 10(1) to 10(7) cfu m(-3). They can also be produced employing different cell types, including bacterial endospores, Gram-positive and Gram-negative vegetative cells and yeast cells. Effective containment of dispersions is achieved while 'cards of product' (vials in sets) are conveyed from the Challenge Room to an adjacent Packing and Storage Area. Decontamination of the room and the housed BFS machine is accomplished through exposure to chlorine dioxide gas at a concentration of 1.0 mg dm(-3) for 120 min at room temperature (approximately 23 degrees C). PMID:15796134

  14. Ubiquitous image processing: a novel image-enhancement facility for consumers

    NASA Astrophysics Data System (ADS)

    Shaw, Rodney; Johnson, Paul

    2006-01-01

    Image-enhancement technology has been developed from first principles whereby an unskilled user may enhance and optimize the image quality of any digital photograph to personal choice within a matter of seconds. The novel methodology, which by virtue of its simple user-interface, real-time computation, and lack of any appreciable user learning-curve, naturally lends itself to many practical imaging applications in addition to that of a stand-alone application, including digital cameras, printers and photo-kiosks, or provision as an image-processing web-service. The basic imaging philosophy and principles leading to the development of this enhancement technology are discussed.

  15. 150t/d PP project of NEDOL process and design of reactor, catalyst facilities

    SciTech Connect

    Miyamori, Hideharu; Kobayashi, Masatoshi

    1995-12-31

    The development of coal liquefaction technology in Japan is being undertaken as one of the New Sunshine Program of Ministry of International Trade and Industry (MITI). Nippon Coal Oil Co., Ltd. (NCOL) has been commissioned by NEDO (New Energy and Industrial Technology Development Organization, which is playing a central role in this program) to design, construct and conduct operation researches on the 150t/d bituminous coal liquefaction pilot plant of NEDOL process. The pilot plant design and some technical topics such as design of reactor and liquefaction catalyst are presented in this report.

  16. Supercritical water oxidation technology for DWPF. [Defense Waste Processing Facility (DWPF)

    SciTech Connect

    Carter, J.T.; Gentilucci, J.A.

    1992-02-07

    At the request of Mr. H.L. Brandt and others in the Savannah River Field Office High Level Waste Division office, DWPF, and SRL personnel have reviewed two potential applications for supercritical water oxidation technology in DWPF. The first application would replace the current hydrolysis process by destroying the organic fractions of the precipitated cesium / potassium tetraphenylborate slurry. The second application pertains to liquid benzene destruction. After a thorough evaluation the first application is not recommended. The second is ready to be tested if needed.

  17. Historic AVHRR Processing in the Eumetsat Climate Monitoring Satellite Application Facility (cmsaf) (Invited)

    NASA Astrophysics Data System (ADS)

    Karlsson, K.

    2010-12-01

    The EUMETSAT CMSAF project (www.cmsaf.eu) compiles climatological datasets from various satellite sources with emphasis on the use of EUMETSAT-operated satellites. However, since climate monitoring primarily has a global scope, also datasets merging data from various satellites and satellite operators are prepared. One such dataset is the CMSAF historic GAC (Global Area Coverage) dataset which is based on AVHRR data from the full historic series of NOAA-satellites and the European METOP satellite in mid-morning orbit launched in October 2006. The CMSAF GAC dataset consists of three groups of products: Macroscopical cloud products (cloud amount, cloud type and cloud top), cloud physical products (cloud phase, cloud optical thickness and cloud liquid water path) and surface radiation products (including surface albedo). Results will be presented and discussed for all product groups, including some preliminary inter-comparisons with other datasets (e.g., PATMOS-X, MODIS and CloudSat/CALIPSO datasets). A background will also be given describing the basic methodology behind the derivation of all products. This will include a short historical review of AVHRR cloud processing and resulting AVHRR applications at SMHI. Historic GAC processing is one of five pilot projects selected by the SCOPE-CM (Sustained Co-Ordinated Processing of Environmental Satellite data for Climate Monitoring) project organised by the WMO Space programme. The pilot project is carried out jointly between CMSAF and NOAA with the purpose of finding an optimal GAC processing approach. The initial activity is to inter-compare results of the CMSAF GAC dataset and the NOAA PATMOS-X dataset for the case when both datasets have been derived using the same inter-calibrated AVHRR radiance dataset. The aim is to get further knowledge of e.g. most useful multispectral methods and the impact of ancillary datasets (for example from meteorological reanalysis datasets from NCEP and ECMWF). The CMSAF project is currently defining plans for another five years (2012-2017) of operations and development. New GAC reprocessing efforts are planned and new methodologies will be tested. Central questions here will be how to increase the quantitative use of the products through improving error and uncertainty estimates and how to compile the information in a way to allow meaningful and efficient ways of using the data for e.g. validation of climate model information.

  18. In-situ wastewater treatment and groundwater remediation at a sugar beet processing facility

    SciTech Connect

    Olson, J.L.; Fuller-Pratt, P.R.; Mielke, R.A.

    1996-06-01

    Groundwater monitoring data collected at the Western Sugar Company sugar beet processing plant, in Billings, Montana identified groundwater mounding and groundwater nitrogen concentration increases associated with lime slurry discharge to an on-site storage pile. The nitrogen impacts (primarily ammonia) likely originated through decomposition of organic matter in the slurry. Initially, Western Sugar considered constructing an expensive anaerobic and nitrification-denitrification wastewater treatment system. However, further investigation of the lime pile revealed that it was already serving as an efficient filter and anaerobic reactor. Comparisons of slurry application with other land application systems suggested that groundwater nitrogen impacts could be minimized through groundwater capture, re-application, and improved slurry management. The resultant system required little capitol and maintenance cost. The immediate effect was to substantially decrease the groundwater mound. Subsequent monitoring has demonstrated a gradual decline in nitrogen concentrations under the lime pile and a considerable concentration decrease downgradient of the groundwater recovery system.

  19. W-007H B Plant Process Condensate Treatment Facility. Revision 3

    SciTech Connect

    Rippy, G.L.

    1995-01-20

    B Plant Process Condensate (BCP) liquid effluent stream is the condensed vapors originating from the operation of the B Plant low-level liquid waste concentration system. In the past, the BCP stream was discharged into the soil column under a compliance plan which expired January 1, 1987. Currently, the BCP stream is inactive, awaiting restart of the E-23-3 Concentrator. B Plant Steam Condensate (BCS) liquid effluent stream is the spent steam condensate used to supply heat to the E-23-3 Concentrator. The tube bundles in the E-23-3 Concentrator discharge to the BCS. In the past, the BCS stream was discharged into the soil column. Currently, the BCS stream is inactive. This project shall provide liquid effluent systems (BCP/BCS/BCE) capable of operating for a minimum of 20 years, which does not include the anticipated decontamination and decommissioning (D and D) period.

  20. Process centrifuge operating problems and equipment failures in canyon reprocessing facilities at the Savannah River Site

    SciTech Connect

    Durant, W.S.; Baughman, D.F.

    1990-03-01

    The Savannah River Laboratory (SRL) maintains a compilation of operating problems and equipment failures that have occurred in the fuel reprocessing areas of the Savannah River Site (SRS). At present, the data bank contains more than 230,000 entries ranging from minor equipment malfunctions to incidents with the potential for injury or contamination of personnel, or for economic loss. The data bank has been used extensively for a wide variety of purposes, such as failure analyses, trend analyses, and preparation of safety analyses. Typical of the data are problems associated with the canyon process centrifuges. This report contains a compilation of the centrifuge operating problems and equipment failures primarily as an aid to organizations with related equipment. Publication of these data was prompted by a number of requests for this information by other Department of Energy (DOE) sites. 11 refs., 2 figs., 4 tabs.

  1. Modeling community asbestos exposure near a vermiculite processing facility: Impact of human activities on cumulative exposure.

    PubMed

    Adgate, John L; Cho, Sook Ja; Alexander, Bruce H; Ramachandran, Gurmurthy; Raleigh, Katherine K; Johnson, Jean; Messing, Rita B; Williams, A L; Kelly, James; Pratt, Gregory C

    2011-01-01

    Contaminated vermiculite ore from Libby, Montana was processed in northeast Minneapolis from 1936 to 1989 in a densely populated urban residential neighborhood, resulting in non-occupational exposure scenarios from plant stack and fugitive emissions as well as from activity-based scenarios associated with use of the waste rock in the surrounding community. The objective of this analysis was to estimate potential cumulative asbestos exposure for all non-occupationally exposed members of this community. Questionnaire data from a neighborhood-exposure assessment ascertained frequency of potential contact with vermiculite processing waste. Monte Carlo simulation was used to develop exposure estimates based on activity-based concentration estimates and contact durations for four scenarios: S1, moved asbestos-contaminated waste; S2, used waste at home, on lawn or garden; S3, installed/removed vermiculite insulation; S4, played in or around waste piles at the plant. The simulation outputs were combined with air-dispersion model results to provide total cumulative asbestos exposure estimates for the cohort. Fiber emissions from the plant were the largest source of exposure for the majority of the cohort, with geometric mean cumulative exposures of 0.02 fibers/cc month. The addition of S1, S2 and S3 did not significantly increase total cumulative exposure above background exposure estimates obtained from dispersion modeling. Activity-based exposures were a substantial contributor to the upper end of the exposure distribution: 90th percentile S4 exposure estimates are ?10 times higher than exposures from plant emissions. Pile playing is the strongest source of asbestos exposure in this cohort, with other activity scenarios contributing less than from plant emissions. PMID:21343955

  2. Reevaluation of Vitrified High-Level Waste Form Criteria for Potential Cost Savings at the Defense Waste Processing Facility - 13598

    SciTech Connect

    Ray, J.W.; Marra, S.L.; Herman, C.C.

    2013-07-01

    At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form. (authors)

  3. The SRTM is in place in the Space Station Processing Facility to undergo pre-launch preparations

    NASA Technical Reports Server (NTRS)

    1999-01-01

    In the Space Station Processing Facility (SSPF), workers (lower right) disconnect the transport vehicle from the Shuttle Radar Topography Mission (SRTM) after moving it into the building for pre-launch preparations. The primary payload on mission STS-99, the SRTM consists of a specially modified radar system that will fly onboard the Space Shuttle during the 11-day mission targeted for launch in September 1999. This radar system will gather data that will result in the most accurate and complete topographic map of the Earth's surface that has ever been assembled. SRTM is an international project spearheaded by the National Imagery and Mapping Agency and NASA, with participation of the German Aerospace Center DLR. Its objective is to obtain the most complete high-resolution digital topographic database of the Earth.

  4. Reevaluation Of Vitrified High-Level Waste Form Criteria For Potential Cost Savings At The Defense Waste Processing Facility

    SciTech Connect

    Ray, J. W.; Marra, S. L.; Herman, C. C.

    2013-01-09

    At the Savannah River Site (SRS) the Defense Waste Processing Facility (DWPF) has been immobilizing SRS's radioactive high level waste (HLW) sludge into a durable borosilicate glass since 1996. Currently the DWPF has poured over 3,500 canisters, all of which are compliant with the U. S. Department of Energy's (DOE) Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms (WAPS) and therefore ready to be shipped to a federal geologic repository for permanent disposal. Due to DOE petitioning to withdraw the Yucca Mountain License Application (LA) from the Nuclear Regulatory Commission (NRC) in 2010 and thus no clear disposal path for SRS canistered waste forms, there are opportunities for cost savings with future canister production at DWPF and other DOE producer sites by reevaluating high-level waste form requirements and compliance strategies and reducing/eliminating those that will not negatively impact the quality of the canistered waste form.

  5. Final deactivation report on the Radioactive Gas Processing Facility, Building 3033, and the Actinide Fabrication Facility, Building 3033A, at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    SciTech Connect

    1997-09-01

    The purpose of this report is to document the condition of Buildings 3033 and 3033A, after completion of deactivation activities as outlined by the Department of Energy Office of Nuclear Materials and Facility Stabilization Program (EM-60) guidance documentation. This report outlines the activities conducted to place the facility in a safe and environmentally sound condition for transfer to the Department of Energy Office of Environmental Restoration Program (EM-40). This report provides a history and profile of Buildings 3033 and 3033A prior to commencing deactivation activities and a profile of the building after completion of deactivation activities. Turnover items, such as the Post-Deactivation Surveillance and Maintenance Plan, remaining hazardous materials, radiological controls, Safeguards and Security, quality assurance, facility operations, and supporting documentation provided in the Office of Nuclear Materials and Facility Stabilization Program (EM-60) Turnover package are discussed. Buildings 3033 and 3033A will require access to facilitate required S and M activities to maintain the building safety envelope. Buildings 3033 and 3033A were stabilized during deactivation so that when transferred to the EM-40 program, only a minimal S and M effort would be required to maintain the building safety envelope. Other than the minimal S and M activities the building will be unoccupied and the exterior doors locked to prevent unauthorized access. The building will be entered only to perform the required S and M. All materials have been removed from the building, and all utility systems, piping, and alarms have been deactivated.

  6. DEVELOPMENT OF REMOTE HANFORD CONNECTOR GASKET REPLACEMENT TOOLING FOR THE SAVANNAH RIVER SITE'S DEFENSE WASTE PROCESSING FACILITY

    SciTech Connect

    Krementz, D

    2007-11-27

    The Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) requested development of tooling for remote replacement of gaskets in mechanical Hanford connectors. The facility has compressed air supply, two master-slave manipulators (MSM's) and a lightweight robotic arm for operation of the remote tools. The Savannah River National Laboratory (SRNL) developed and tested multiple tools to perform the gasket replacement tasks. Separate pneumatic snap-ring removal tools that use the connector skirt as a reaction surface were developed for removal of the snap ring and spent gasket on both vertical and horizontal Hanford connectors. A pneumatic tool that clamps and centers on the jumper pipe ID was developed to simultaneously install the new gasket and snap ring. A pneumatic snap-ring-loading tool was developed that compresses the snap ring and places it in a groove in the installation tool. All of the tools are located on a custom work table with a pneumatic valve station that directs compressed air to the desired tool and vents the tools as needed. The entire system has been successfully tested using MSM's to manipulate the various tools. Deployment of the entire system is expected during FY08. The Hanford connector gasket replacement tooling has been successfully tested using MSM's to manipulate the various tools. Nitric acid is used in many of the decontamination processes performed in the REDC, where the tooling will be deployed. Although most of the tool components were fabricated/purchased with nitric acid and radioactive service in mind, some of the prototype parts must be replaced with parts that are more compatible with nitric acid/radioactive service. Several modifications to the various tools are needed to facilitate maintenance and replacement of failed components. Development of installation tools for replacement of 1-inch, 2-inch and multi-hole gaskets is being considered. Deployment of the existing system in the DWPF REDC is expected during FY08.

  7. Spacelab data processing facility (SLDPF) Quality Assurance (QA)/Data Accounting (DA) expert systems: Transition from prototypes to operational systems

    NASA Technical Reports Server (NTRS)

    Basile, Lisa

    1988-01-01

    The SLDPF is responsible for the capture, quality monitoring processing, accounting, and shipment of Spacelab and/or Attached Shuttle Payloads (ASP) telemetry data to various user facilities. Expert systems will aid in the performance of the quality assurance and data accounting functions of the two SLDPF functional elements: the Spacelab Input Processing System (SIPS) and the Spacelab Output Processing System (SOPS). Prototypes were developed for each as independent efforts. The SIPS Knowledge System Prototype (KSP) used the commercial shell OPS5+ on an IBM PC/AT; the SOPS Expert System Prototype used the expert system shell CLIPS implemented on a Macintosh personal computer. Both prototypes emulate the duties of the respective QA/DA analysts based upon analyst input and predetermined mission criteria parameters, and recommended instructions and decisions governing the reprocessing, release, or holding for further analysis of data. These prototypes demonstrated feasibility and high potential for operational systems. Increase in productivity, decrease of tedium, consistency, concise historial records, and a training tool for new analyses were the principal advantages. An operational configuration, taking advantage of the SLDPF network capabilities, is under development with the expert systems being installed on SUN workstations. This new configuration in conjunction with the potential of the expert systems will enhance the efficiency, in both time and quality, of the SLDPF's release of Spacelab/AST data products.

  8. Spacelab data processing facility (SLDPF) quality assurance (QA)/data accounting (DA) expert systems - Transition from prototypes to operational systems

    NASA Technical Reports Server (NTRS)

    Basile, Lisa

    1988-01-01

    The SLDPF is responsible for the capture, quality monitoring processing, accounting, and shipment of Spacelab and/or Attached Shuttle Payloads (ASP) telemetry data to various user facilities. Expert systems will aid in the performance of the quality assurance and data accounting functions of the two SLDPF functional elements: the Spacelab Input Processing System (SIPS) and the Spacelab Output Processing System (SOPS). Prototypes were developed for each as independent efforts. The SIPS Knowledge System Prototype (KSP) used the commercial shell OPS5+ on an IBM PC/AT; the SOPS Expert System Prototype used the expert system shell CLIPS implemented on a Macintosh personal computer. Both prototypes emulate the duties of the respective QA/DA analysts based upon analyst input and predetermined mission criteria parameters, and recommended instructions and decisions governing the reprocessing, release, or holding for further analysis of data. These prototypes demonstrated feasibility and high potential for operational systems. Increase in productivity, decrease of tedium, consistency, concise historical records, and a training tool for new analyses were the principal advantages. An operational configuration, taking advantage of the SLDPF network capabilities, is under development with the expert systems being installed on SUN workstations. This new configuration in conjunction with the potential of the expert systems will enhance the efficiency, in both time and quality, of the SLDPF's release of Spacelab/AST data products.

  9. HANFORD CONTAINERIZED CAST STONE FACILITY TASK 1 PROCESS TESTING & DEVELOPMENT FINAL TEST REPORT

    SciTech Connect

    LOCKREM, L L

    2005-07-13

    Laboratory testing and technical evaluation activities on Containerized Cast Stone (CCS) were conducted under the Scope of Work (SOW) contained in CH2M HILL Hanford Group, Inc. (CHG) Contract No. 18548 (CHG 2003a). This report presents the results of testing and demonstration activities discussed in SOW Section 3.1, Task I--''Process Development Testing'', and described in greater detail in the ''Containerized Grout--Phase I Testing and Demonstration Plan'' (CHG, 2003b). CHG (2003b) divided the CCS testing and evaluation activities into six categories, as follows: (1) A short set of tests with simulant to select a preferred dry reagent formulation (DRF), determine allowable liquid addition levels, and confirm the Part 2 test matrix. (2) Waste form performance testing on cast stone made from the preferred DRF and a backup DRF, as selected in Part I, and using low activity waste (LAW) simulant. (3) Waste form performance testing on cast stone made from the preferred DRF using radioactive LAW. (4) Waste form validation testing on a selected nominal cast stone formulation using the preferred DRF and LAW simulant. (5) Engineering evaluations of explosive/toxic gas evolution, including hydrogen, from the cast stone product. (6) Technetium ''getter'' testing with cast stone made with LAW simulant and with radioactive LAW. In addition, nitrate leaching observations were drawn from nitrate leachability data obtained in the course of the Parts 2 and 3 waste form performance testing. The nitrate leachability index results are presented along with other data from the applicable activity categories.

  10. Assessment of environmental radioactivity at uranium mining, processing and tailings management facility at Jaduguda, India.

    PubMed

    Tripathi, R M; Sahoo, S K; Jha, V N; Khan, A H; Puranik, V D

    2008-11-01

    The uranium mines at Jaduguda and nearby areas of the Singhbhum thrust belt of Jharkhand State are the only operating mines in India, which supply fuel to nuclear power plants. The gamma radiation dose rates observed at different locations 1m above the tailings surface vary from 0.8 to 3.3 microGy h(-1). The geometric mean activity concentration of (222)Rn in air over the tailings ponds I and II were found to be 30 and 23 Bq m(-3), respectively, but reduces to the local background level at the boundaries of the tailings ponds. The uranium and (226)Ra levels in the ground water sources in the vicinity of the tailings pond are very similar to the regional average of 3.6 microg L(-1) and 23 mBq L(-1), respectively, indicating that there is no ground water migration of radioactive material from the tailings pond. This paper gives a brief account of the environmental radioactivity monitoring during uranium mining, ore processing and waste management operations. PMID:18653352

  11. A Guide for Developing Standard Operating Job Procedures for the Activated Sludge - Aeration & Sedimentation Process Wastewater Treatment Facility. SOJP No. 5.

    ERIC Educational Resources Information Center

    Mason, George J.

    This guide for developing standard operating job procedures for wastewater treatment facilities is devoted to the activated sludge aeration and sedimentation process. This process is for conversion of nonsettleable and nonfloatable materials in wastewater to settleable, floculated biological groups and separation of the settleable solids from the

  12. Analyses by the Defense Waste Processing Facility Laboratory of Thorium Glasses from the Sludge Batch 6 Variability Study

    SciTech Connect

    Edwards, T.; Click, D.; Feller, M.

    2011-02-28

    The Savannah River Remediation (SRR) Defense Waste Processing Facility (DWPF) is currently processing Sludge Batch 6 (SB6) with Frit 418. At times during the processing of this glass system, thorium is expected to be at concentrations in the final wasteform that make it a reportable element for the first time since startup of radioactive operations at the DWPF. The Savannah River National Laboratory (SRNL) supported the qualification of the processing of this glass system at the DWPF. A recommendation from the SRNL studies was the need for the DWPF Laboratory to establish a method to measure thorium by Inductively Coupled Plasma - Atomic Emission Spectroscopy (ICPAES). This recommendation led to the set of thorium-bearing glasses from the SB6 Variability Study (VS) being submitted to the DWPF Laboratory for chemical composition measurement. The measurements were conducted by the DWPF Laboratory using the sodium peroxide fusion preparation method routinely employed for analysis of samples from the Slurry Mix Evaporator (SME). These measurements are presented and reviewed in this report. The review indicates that the measurements provided by the DWPF Laboratory are comparable to those provided by Analytical Development's laboratory at SRNL for these same glasses. As a result, the authors of this report recommend that the DWPF Laboratory begin using its routine peroxide fusion dissolution method for the measurement of thorium in SME samples of SB6. The purpose of this technical report is to present the measurements generated by the DWPF Laboratory for the SB6 VS glasses and to compare the measurements to the targeted compositions for these VS glasses as well as to SRNL's measurements (both sets, targeted and measured, of compositional values were reported by SRNL in [2]). The goal of these comparisons is to provide information that will lead to the qualification of peroxide fusion dissolution as a method for the measurement by the DWPF Laboratory of thorium in SME glass samples.

  13. PFGE characterisation and adhesion ability of Listeria monocytogenes isolates obtained from bovine carcasses and beef processing facilities.

    PubMed

    Galvo, Newton Nascentes; Chiarini, Eb; Destro, Maria Teresa; de Aguiar Ferreira, Mrcia; Nero, Lus Augusto

    2012-12-01

    Listeria monocytogenes is a pathogen capable of adhering to many surfaces and forming biofilms, which may explain its persistence in food processing environments. This study aimed to genetically characterise L. monocytogenes isolates obtained from bovine carcasses and beef processing facilities and to evaluate their adhesion abilities. DNA from 29 L. monocytogenes isolates was subjected to enzymatic restriction digestion (AscI and ApaI), and two clusters were identified for serotypes 4b and 1/2a, with similarities of 48% and 68%, respectively. The adhesion ability of the isolates was tested considering: inoculum concentration, culture media, carbohydrate source, NaCl concentration, incubation temperature, and pH. Each isolate was tested at 10? CFU mL? and classified according to its adhesion ability as weak (8 isolates), moderate (17) or strong (4). The isolates showed higher adhesion capability in non-diluted culture media, media at pH 7.0, incubation at 25C and 37 C, and media with NaCl at 5% and 7%. No relevant differences were observed for adhesion ability with respect to the carbohydrate source. The results indicated a wide diversity of PFGE profiles of persistent L. monocytogenes isolates, without relation to their adhesion characteristics. Also, it was observed that stressing conditions did not enhance the adhesion profile of the isolates. PMID:22748307

  14. 3D Geospatial Models for Visualization and Analysis of Groundwater Contamination at a Nuclear Materials Processing Facility

    NASA Astrophysics Data System (ADS)

    Stirewalt, G. L.; Shepherd, J. C.

    2003-12-01

    Analysis of hydrostratigraphy and uranium and nitrate contamination in groundwater at a former nuclear materials processing facility in Oklahoma were undertaken employing 3-dimensional (3D) geospatial modeling software. Models constructed played an important role in the regulatory decision process of the U.S. Nuclear Regulatory Commission (NRC) because they enabled visualization of temporal variations in contaminant concentrations and plume geometry. Three aquifer systems occur at the site, comprised of water-bearing fractured shales separated by indurated sandstone aquitards. The uppermost terrace groundwater system (TGWS) aquifer is composed of terrace and alluvial deposits and a basal shale. The shallow groundwater system (SGWS) aquifer is made up of three shale units and two sandstones. It is separated from the overlying TGWS and underlying deep groundwater system (DGWS) aquifer by sandstone aquitards. Spills of nitric acid solutions containing uranium and radioactive decay products around the main processing building (MPB), leakage from storage ponds west of the MPB, and leaching of radioactive materials from discarded equipment and waste containers contaminated both the TGWS and SGWS aquifers during facility operation between 1970 and 1993. Constructing 3D geospatial property models for analysis of groundwater contamination at the site involved use of EarthVision (EV), a 3D geospatial modeling software developed by Dynamic Graphics, Inc. of Alameda, CA. A viable 3D geohydrologic framework model was initially constructed so property data could be spatially located relative to subsurface geohydrologic units. The framework model contained three hydrostratigraphic zones equivalent to the TGWS, SGWS, and DGWS aquifers in which groundwater samples were collected, separated by two sandstone aquitards. Groundwater data collected in the three aquifer systems since 1991 indicated high concentrations of uranium (>10,000 micrograms/liter) and nitrate (> 500 milligrams/liter) around the MPB and elevated nitrate (> 2000 milligrams/ liter) around storage ponds. Vertical connectivity was suggested between the TGWS and SGWS, while the DGWS appeared relatively isolated from the overlying aquifers. Lateral movement of uranium was also suggested over time. For example, lateral migration in the TGWS is suggested along a shallow depression in the bedrock surface trending south-southwest from the southwest corner of the MPB. Another pathway atop the buried bedrock surface, trending west-northwest from the MPB and partially reflected by current surface topography, suggested lateral migration of nitrate in the SGWS. Lateral movement of nitrate in the SGWS was also indicated north, south, and west of the largest storage pond. Definition of contaminant plume movement over time is particularly important for assessing direction and rate of migration and the potential need for preventive measures to control contamination of groundwater outside facility property lines. The 3D geospatial property models proved invaluable for visualizing and analyzing variations in subsurface uranium and nitrate contamination in space and time within and between the three aquifers at the site. The models were an exceptional visualization tool for illustrating extent, volume, and quantitative amounts of uranium and nitrate contamination in the subsurface to regulatory decision-makers in regard to site decommissioning issues, including remediation concerns, providing a perspective not possible to achieve with traditional 2D maps. The geohydrologic framework model provides a conceptual model for consideration in flow and transport analyses.

  15. The consideration of geological uncertainty in the siting process for a Geological Disposal Facility for radioactive waste

    NASA Astrophysics Data System (ADS)

    Mathers, Steve; McEvoy, Fiona; Shaw, Richard

    2015-04-01

    Any decision about the site of a Geological Disposal Facility at depth for medium to high level radioactive waste is based on a safety case which in turn is based on an understanding of the geological environment which enables, for example, understanding groundwater flows and groundwater chemical composition. Because the information on which geological understanding is based cannot be fully understood, it is important to ensure that: i. Inferences are made from data in a way that is consistent with the data. ii. The uncertainty in the inferred information is described, quantitatively where this is appropriate. Despite these uncertainties decisions can and must be made, and so the implications of the uncertainty need to be understood and quantified. To achieve this it is important to ensure that: i. An understanding of how error propagates in all models and decision tools. Information which is collected to support the decision-making process may be used as input into models of various kinds to generate further information. For example, a process model may be used to predict groundwater flows, so uncertainty in the properties which are input to the model (e.g. on rock porosity and structure) will give rise to uncertainty in the model predictions. Understanding how this happens is called the analysis of error propagation. It is important that there is an understanding of how error propagates in all models and decision tools, and therefore knowledge of how much uncertainty remains in the process at any stage. As successive phases of data collection take place the analysis of error propagation shows how the uncertainty in key model outputs is gradually reduced. ii. The implications of all uncertainties can be traced through the process. A clear analysis of the decision-making process is necessary so that the implications of all uncertainties can be traced through the process. This means that, when a final decision is made, one can state with a high level of confidence that site conditions, while not known exactly, fall within an acceptable range.

  16. Comparative risk assessments for the production and interim storage of glass and ceramic waste forms: defense waste processing facility

    SciTech Connect

    Huang, J C; Wright, W V

    1982-04-01

    The Defense Waste Processing Facility (DWPF) for immobilizing nuclear high level waste (HLW) is scheduled to be built at the Savannah River Plant (SRP). High level waste is produced when SRP reactor components are subjected to chemical separation operations. Two candidates for immobilizing this HLW are borosilicate glass and crystalline ceramic, either being contained in weld-sealed stainless steel canisters. A number of technical analyses are being conducted to support a selection between these two waste forms. The present document compares the risks associated with the manufacture and interim storage of these two forms in the DWPF. Process information used in the risk analysis was taken primarily from a DWPF processibility analysis. The DWPF environmental analysis provided much of the necessary environmental information. To perform the comparative risk assessments, consequences of the postulated accidents are calculated in terms of: (1) the maximum dose to an off-site individual; and (2) the dose to off-site population within 80 kilometers of the DWPF, both taken in terms of the 50-year inhalation dose commitment. The consequences are then multiplied by the estimated accident probabilities to obtain the risks. The analyses indicate that the maximum exposure risk to an individual resulting from the accidents postulated for both the production and interim storage of either waste form represents only an insignificant fraction of the natural background radiation of about 90 mrem per year per person in the local area. They also show that there is no disaster potential to the off-site population. Therefore, the risks from abnormal events in the production and the interim storage of the DWPF waste forms should not be considered as a dominant factor in the selection of the final waste form.

  17. Molecular and immunological approaches in quantifying the air-borne food allergen tropomyosin in crab processing facilities.

    PubMed

    Kamath, Sandip D; Thomassen, Marte R; Saptarshi, Shruti R; Nguyen, Hong M X; Aasmoe, Lisbeth; Bang, Berit E; Lopata, Andreas L

    2014-09-01

    Tropomyosin is a cross-reactive allergenic protein present in ingested shellfish species. Exposure and sensitization to this protein via inhalation is particularly important in the crustacean processing industry where workers are continuously exposed to the aerosolized form of this allergen. The aim of this study was to develop an antibody-based immunoassay to enable the specific and sensitive quantification of aerosolized tropomyosin present in the environment of two crab processing facilities. Anti-tropomyosin antibody was generated in rabbits against tropomyosins from four different crustacean species. These antibodies were purified using recombinant tropomyosin using an immuno-affinity column. The recombinant tropomyosin was also used as an allergen standard for the sandwich ELISA. In order to quantify aerosolized tropomyosin, air collection was performed in the personal breathing zone of 80 workers during two crab processing activities, edible crab (Cancer pagurus) and king crab (Paralithodes camtschaticus) using polytetrafluoroethylene filters. The purified antibody was able to detect tropomyosin selectively from different crustaceans but not from vertebrate sources. The limit of detection (LOD) for the developed sandwich ELISA was 60 picogram/m(3) and limit of quantitation (LOQ) 100 picogram/m(3). Immunoassay validation was based on linearity (R(2) 0.999), matrix interference test (78.8±6.5%), intra-assay CV (9.8%) and inter-assay CV (11%). The novel immunoassay was able to successfully identify working activities, which generated low, medium or high concentrations of the aerosolized food allergen. We describe an IgG antibody-based immunoassay for quantification of the major food allergen tropomyosin, with high sensitivity and specificity. This modified immunological approach can be adapted for the detection of other aerosolized food allergens, assisting in the identification of high-risk allergen exposure areas in the food industry. PMID:24755444

  18. Methods to estimate equipment and materials that are candidates for removal during the decontamination of fuel processing facilities

    SciTech Connect

    Duncan, D.R.; Valero, O.J.; Hyre, R.A.; Pottmeyer, J.A.; Millar, J.S.; Reddick, J.A.

    1995-02-01

    The methodology presented in this report provides a model for estimating the volume and types of waste expected from the removal of equipment and other materials during Decontamination and Decommissioning (D and D) of canyon-type fuel reprocessing facilities. This methodology offers a rough estimation technique based on a comparative analysis for a similar, previously studied, reprocessing facility. This approach is especially useful as a planning tool to save time and money while preparing for final D and D. The basic methodology described here can be extended for use at other types of facilities, such as glovebox or reactor facilities.

  19. Tritium dynamics in soils and plants grown under three irrigation regimes at a tritium processing facility in Canada.

    PubMed

    Mihok, S; Wilk, M; Lapp, A; St-Amant, N; Kwamena, N-O A; Clark, I D

    2016-03-01

    The dynamics of tritium released from nuclear facilities as tritiated water (HTO) have been studied extensively with results incorporated into regulatory assessment models. These models typically estimate organically bound tritium (OBT) for calculating public dose as OBT itself is rarely measured. Higher than expected OBT/HTO ratios in plants and soils are an emerging issue that is not well understood. To support the improvement of models, an experimental garden was set up in 2012 at a tritium processing facility in Pembroke, Ontario to characterize the circumstances under which high OBT/HTO ratios may arise. Soils and plants were sampled weekly to coincide with detailed air and stack monitoring. The design included a plot of native grass/soil, contrasted with sod and vegetables grown in barrels with commercial topsoil under natural rain and either low or high tritium irrigation water. Air monitoring indicated that the plume was present infrequently at concentrations of up to about 100 Bq/m(3) (the garden was not in a major wind sector). Mean air concentrations during the day on workdays (HTO 10.3 Bq/m(3), HT 5.8 Bq/m(3)) were higher than at other times (0.7-2.6 Bq/m(3)). Mean Tissue Free Water Tritium (TFWT) in plants and soils and OBT/HTO ratios were only very weakly or not at all correlated with releases on a weekly basis. TFWT was equal in soils and plants and in above and below ground parts of vegetables. OBT/HTO ratios in above ground parts of vegetables were above one when the main source of tritium was from high tritium irrigation water (1.5-1.8). Ratios were below one in below ground parts of vegetables when irrigated with high tritium water (0.4-0.6) and above one in vegetables rain-fed or irrigated with low tritium water (1.3-2.8). In contrast, OBT/HTO ratios were very high (9.0-13.5) when the source of tritium was mainly from the atmosphere. TFWT varied considerably through time as a result of SRBT's operations; OBT/HTO ratios showed no clear temporal pattern in above or below ground plant parts. Native soil after ∼20 years of operations at SRBT had high initial OBT that persisted through the growing season; little OBT formed in garden plot soil during experiments. High OBT in native soil appeared to be a signature of higher past releases at SRBT. This phenomenon was confirmed in soils obtained at another processing facility in Canada with a similar history. The insights into variation in OBT/HTO ratios found here are of regulatory interest and should be incorporated in assessment models to aid in the design of relevant environmental monitoring programs for OBT. PMID:26773512

  20. Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

    NASA Astrophysics Data System (ADS)

    Rahman, Nur Aira Abd; Yussup, Nolida; Salim, Nazaratul Ashifa Bt. Abdullah; Ibrahim, Maslina Bt. Mohd; Mokhtar, Mukhlis B.; Soh@Shaari, Syirrazie Bin Che; Azman, Azraf B.; Ismail, Nadiah Binti

    2015-04-01

    Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on `Development of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)'. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6.