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1

PERFORMANCE PROPERTIES OF SALTSTONE PRODUCED USING SWPF SIMULANTS  

SciTech Connect

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 inc

Harbour, J.; Edwards, T.

2010-02-16

2

BLENDING ANALYSIS FOR RADIOACTIVE SALT WASTE PROCESSING FACILITY  

SciTech Connect

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.

Lee, S.

2012-05-10

3

Defense Waste Processing Facility (DWPF), Modular CSSX Unit (CSSX), and Waste Transfer Line System of Salt Processing Program (U)  

SciTech Connect

All of the waste streams from ARP, MCU, and SWPF processes will be sent to DWPF for vitrification. The impact these new waste streams will have on DWPF's ability to meet its canister production goal and its ability to support the Salt Processing Program (ARP, MCU, and SWPF) throughput needed to be evaluated. DWPF Engineering and Operations requested OBU Systems Engineering to evaluate DWPF operations and determine how the process could be optimized. The ultimate goal will be to evaluate all of the Liquid Radioactive Waste (LRW) System by developing process modules to cover all facilities/projects which are relevant to the LRW Program and to link the modules together to: (1) study the interfaces issues, (2) identify bottlenecks, and (3) determine the most cost effective way to eliminate them. The results from the evaluation can be used to assist DWPF in identifying improvement opportunities, to assist CBU in LRW strategic planning/tank space management, and to determine the project completion date for the Salt Processing Program.

CHANG, ROBERT

2006-02-02

4

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

SciTech Connect

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.

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

2011-11-07

5

Modular Containerless Processing Facility  

NASA Technical Reports Server (NTRS)

The Modular Containerless Processing Facility (MCPF) of the Space Station Freedom, being developed by the Jet Propulsion Laboratory, is described. The MCPF will be capable of positioning, manipulating, and performing processing operations on samples completely free of container walls. It will be comprised of a host facility and a series of interchangeable plug-in modules. Initial iterations of MCPF modules will be flown on the U.S. Microgravity Laboratory (USML) series of Shuttle flights. The Drop Physics Module schedualed to fly on USML-1 in March 1992 is also considered.

Morrison, Andrew D.

1990-01-01

6

Studsvik Processing Facility Update  

Microsoft Academic Search

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

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

2003-01-01

7

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

SciTech Connect

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

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

2010-06-29

8

Conceptual Design of a Simplified Skid-Mounted Caustic-Side Solvent Extraction Process for Removal of Cesium from Savannah Rive Site High-Level Waste  

SciTech Connect

This report presents the results of a conceptual design of a solvent extraction process for the selective removal of {sup 137}Cs from high-level radioactive waste currently stored in underground tanks at the U.S. Department of Energy's Savannah River Site (SRS). This study establishes the need for and feasibility of deploying a simplified version of the Caustic-Side Solvent Extraction (CSSX) process; cost/benefit ratios ranging from 33 to 55 strongly support the considered deployment. Based on projected compositions, 18 million gallons of dissolved salt cake waste has been identified as having {sup 137}Cs concentrations that are substantially lower than the worst-case design basis for the CSSX system that is to be deployed as part of the Salt Waste Processing Facility (SWPF) but that does not meet the waste acceptance criteria for immobilization as grout in the Saltstone Manufacturing and Disposal Facility at SRS. Absent deployment of an alternative cesium removal process, this material will require treatment in the SWPF CSSX system, even though the cesium decontamination factor required is far less than that provided by that system. A conceptual design of a CSSX processing system designed for rapid deployment and having reduced cesium decontamination factor capability has been performed. The proposed accelerated-deployment CSSX system (CSSX-A) has been designed to have a processing rate of 3 million gallons per year, assuming 90% availability. At a more conservative availability of 75% (reflecting the novelty of the process), the annual processing capacity is 2.5 million gallons. The primary component of the process is a 20-stage cascade of centrifugal solvent extraction contactors. The decontamination and concentration factors are 40 and 15, respectively. The solvent, scrub, strip, and wash solutions are to have the same compositions as those planned for the SWPF CSSX system. As in the SWPF CSSX system, the solvent and scrub flow rates are equal. The system is designed to facilitate remote operation and direct maintenance. Two general deployment concepts were considered: (1) deployment in an existing but unused SRS facility and (2) deployment in transportable containers. Deployment in three transportable containers was selected as the preferred option, based on concerns regarding facility availability (due to competition from other processing alternatives) and decontamination and renovation costs. A risk assessment identified environmental, safety, and health issues that exist. These concerns have been addressed in the conceptual design by inclusion of mitigating system features. Due to the highly developed state of CSSX technology, only a few technical issues remain unresolved; however, none of these issues have the potential to make the technology unviable. Recommended development tasks that need to be performed to address technical uncertainties are discussed in this report. Deployment of the proposed CSSX-A system provides significant qualitative and quantitative benefits. The qualitative benefits include (1) verification of full-scale contactor performance under CSSX conditions that will support SWPF CSSX design and deployment; (2) development of design, fabrication, and installation experience bases that will be at least partially applicable to the SWPF CSSX system; and (3) availability of the CSSX-A system as a means of providing contactor-based solvent extraction system operating experience to SWPF CSSX operating personnel. Estimates of fixed capital investment, development costs, and annual operating cost for SRS deployment of the CSSX-A system (in mid-2003 dollars) are $9,165,199, $2,734,801, and $2,108,820, respectively. When the economics of the CSSX-A system are compared with those of the baseline SWPF CSSX system, benefit-to-cost ratios ranging from 20 to 47 are obtained. The benefits in the cost/benefit comparison arise from expedited tank closure and reduced engineering, construction, and operating costs for the SWPF CSSX system. No significant impediments to deployment were determined in the reported a

Birdwell, JR.J.F.

2004-05-12

9

The Facilities Audit. A Process for Improving Facilities Conditions.  

ERIC Educational Resources Information Center

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…

Kaiser, Harvey H.

10

Springfield Processing Plant (SPP) Facility Information  

SciTech Connect

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.

Leach, Janice; Torres, Teresa M.

2012-10-01

11

SALTSTONE PROCESSING FACILITY TRANSFER SAMPLE  

SciTech Connect

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.

Cozzi, A.; Reigel, M.

2010-08-04

12

The Medina County, Ohio, central processing facility  

SciTech Connect

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.

White, K.M.

1994-08-01

13

Materials evaluation for a transuranic processing facility  

SciTech Connect

The Westinghouse Hanford Company, with the assistance of the Pacific Northwest Laboratory, is developing a transuranium extraction process for preheating double-shell tank wastes at the Hanford Site to reduce the volume of transuranic waste being sent to a repository. The bench- scale transuranium extraction process development is reaching a stage where a pilot plant design has begun for the construction of a facility in the existing B Plant. Because of the potential corrosivity of neutralized cladding removal waste process streams, existing embedded piping alloys in B Plant are being evaluated and new'' alloys are being selected for the full-scale plant screening corrosion tests. Once the waste is acidified with HNO{sub 3}, some of the process streams that are high in F{sup {minus}} and low in Al and zr can produce corrosion rates exceeding 30,000 mil/yr in austenitic alloys. Initial results results are reported concerning the applicability of existing plant materials to withstand expected process solutions and conditions to help determine the feasibility of locating the plant at the selected facility. In addition, process changes are presented that should make the process solutions less corrosive to the existing materials. Experimental work confirms that Hastelloy B is unsatisfactory for the expected process solutions; type 304L, 347 and 309S stainless steels are satisfactory for service at room temperature and 60{degrees}C, if process stream complexing is performed. Inconel 625 was satisfactory for all solutions. 17 refs., 5 figs., 8 tabs.

Barker, S.A., Schwenk, E.B. (Westinghouse Hanford Co., Richland, WA (USA)); Divine, J.R. (Pacific Northwest Lab., Richland, WA (USA))

1990-11-01

14

15 CFR 923.13 - Energy facility planning process.  

Code of Federal Regulations, 2010 CFR

...13 Energy facility planning process. The management program must contain a planning process for energy facilities likely...the coastal zone, including a process for anticipating the management of the impacts resulting...

2010-01-01

15

Safeguards Approaches for Black Box Processes or Facilities  

SciTech Connect

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.

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

2013-09-25

16

A Central Processing Facility within a Distributed Data Processing System  

NASA Astrophysics Data System (ADS)

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.

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

2009-04-01

17

Facilities for pyrochemical process studies at ENEA  

SciTech Connect

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.

De Angelis, G.; Fedeli, C.; Tiranti, G. [Italian National Agency for New Technology, Energy and the Environment - ENEA, Casaccia Research Center, Via Anguillarese 301, 00123 S. Maria di Galeria, Roma (Italy); Baicchi, E. [ENEA, Brasimone Research Center, 40032 Camugnano, Bologna (Italy)

2013-07-01

18

Electromagnetic Containerless Processing Facility TEMPUS (Tiegelfreies Elektromagnetisches  

NASA Technical Reports Server (NTRS)

TEMPUS, an electromagnetic levitation facility that allows containerless processing of metallic samples in microgravity, first flew on the IML-2 Spacelab mission. The principle of electromagnetic levitation is used commonly in ground-based experiments to melt and then cool metallic melts below their freezing points without solidification occurring. The TEMPUS operation is controlled by its own microprocessor system; although commands may be sent remotely from the ground and real time adjustments may be made by the crew. Two video cameras, a two-color pyrometer for measuring sample temperatures, and a fast infrared detector for monitoring solidification spikes, will be mounted to the process chamber to facilitate observation and analysis. In addition, a dedicated high-resolution video camera can be attached to the TEMPUS to measure the sample volume precisely.

1994-01-01

19

Waste minimization and pollution prevention at a plutonium processing facility  

Microsoft Academic Search

If nuclear facilities are to achieve public acceptance, they must develop strong programs in waste minimization, pollution prevention, and environmentally sound recycling. These programs are specially essential for defense production facilities that process large quantities of special nuclear materials. The plutonium processing facility at Los Alamos has initiated a focused research and development program with a strategic goal of becoming

K PILLAY; K. K. S

1994-01-01

20

A graded approach to safety documentation at processing facilities  

SciTech Connect

Westinghouse Savannah River Company (WSRC) has over 40 major Safety Analysis Reports (SARs) in preparation for non-reactor facilities. These facilities include nuclear material production facilities, waste management facilities, support laboratories and environmental remediation facilities. The SARs for these various projects encompass hazard levels from High to Low, and mission times from startup, through operation, to shutdown. All of these efforts are competing for scarce resources, and therefore some mechanism is required for balancing the documentation requirements. Three of the key variables useful for the decision making process are Depth of Safety Analysis, Urgency of Safety Analysis, and Resource Availability. This report discusses safety documentation at processing facilities.

Cowen, M.L.

1992-01-01

21

A graded approach to safety documentation at processing facilities  

SciTech Connect

Westinghouse Savannah River Company (WSRC) has over 40 major Safety Analysis Reports (SARs) in preparation for non-reactor facilities. These facilities include nuclear material production facilities, waste management facilities, support laboratories and environmental remediation facilities. The SARs for these various projects encompass hazard levels from High to Low, and mission times from startup, through operation, to shutdown. All of these efforts are competing for scarce resources, and therefore some mechanism is required for balancing the documentation requirements. Three of the key variables useful for the decision making process are Depth of Safety Analysis, Urgency of Safety Analysis, and Resource Availability. This report discusses safety documentation at processing facilities.

Cowen, M.L.

1992-09-01

22

Waste Receiving and Processing Facility (WRAP) Drawing List  

SciTech Connect

This supporting document delineates the process of identification, categorization, and/or classification of the WRAP facility drawings used to support facility operations and maintenance. This document provides a listing of those essential or safety related drawings which have been identified to date. All other WRAP facility drawings have been classified as general.

WEIDERT, J.R.

1999-10-25

23

Northwestern University Facility for Clean Catalytic Process Research  

SciTech Connect

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.

Marks, Tobin Jay [Northwestern University

2013-05-08

24

77 FR 823 - Guidance for Fuel Cycle Facility Change Processes  

Federal Register 2010, 2011, 2012, 2013, 2014

...uranium processing, fabrication of uranium fuel or fuel assemblies, uranium enrichment, enriched uranium hexafluoride conversion, plutonium processing, or fabrication...fuel assemblies. Such fuel cycle facility licensees must establish a...

2012-01-06

25

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

SciTech Connect

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.

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

1990-01-01

26

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...

27

The Lofar Central Processing Facility Architecture  

NASA Astrophysics Data System (ADS)

Reconfiguration is a key feature characteristic of the LOFAR telescope. Software platforms are utilised to program out the required data transformations in the generation of scientific end-products. Reconfigurable resources nowadays often replace the hard-wired processing systems from the past. This paper describes how this paradigm is implemented in a purely general-purpose telescope back-end. Experiences from high performance computing, stream processing and software engineering have been combined, leading to a state-of-the-art processing platform. The processing platform offers a total processing power of 35 TFlops, which is used to process a sustained input data- stream of 320 Gbps. The architecture of this platform is optimised for streaming data processing and offers appropriate processing resources for each step in the data processing chains. Typical data processing chains include Fourier transformations and correlation tasks along with controlling tasks such as fringe rotation correction. These tasks are defined in a high level programming language and mapped onto the available resources at run time. A scheduling system is used to control a collection of concurrently executing observations, providing each associated application with the appropriate resources to meet its timing constraint and give the integrated system the correct on-line and off-line look and feel.

Schaaf, Kjeld; Broekema, Chris; Diepen, Ger; Meijeren, Ellen

2004-06-01

28

9 CFR 590.546 - Albumen flake process drying facilities.  

Code of Federal Regulations, 2010 CFR

... FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.546 Albumen...

2010-01-01

29

Advanced Alarm Processing Facilities Installed on Eskom's Energy Management System  

Microsoft Academic Search

Eskom's Transmission division is commissioning a new Energy Management System (EMS) known as TEMSE. This EMS included requirements for advanced alarm processing facilities and enhanced Human Machine Interface functionality. The requirements covered alarm data reduction and the provision of \\

Richard Candy; J. Taisne

2007-01-01

30

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

NASA Technical Reports Server (NTRS)

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.

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

1987-01-01

31

Ninth Processing Campaign in the Waste Calcining Facility  

SciTech Connect

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.

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

1982-04-01

32

Opportunities for Process Monitoring Techniques at Delayed Access Facilities  

SciTech Connect

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.

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

2013-09-20

33

Decommissioning of an enriched uranium processing facility  

Microsoft Academic Search

The Los Alamos National Laboratory TA-21, Buildings 3 and 4 South decontamination and decommissioning (D&D) project began remediation on September 20, 1993. The project is one of the largest U.S. Department of Energy-sponsored D&D projects currently under way. The project involves the decontamination, dismantlement, and demolition of two enriched-uranium processing buildings, which is an area of â¼10000 ft². The enriched-uranium

Stout

1994-01-01

34

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

SciTech Connect

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.

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

1997-12-31

35

Health physics monitoring at the Defense Waste Processing Facility  

SciTech Connect

Remote radiation monitoring has been designed into the Vitrification portion of the Defense Waste Processing Facility (DWPF) at the Savannah River Site in South Carolina. Local alarms and remote readings are provided for area radiation levels, door alarms, airborne radioactivity, effluent air activity and liquid (process system) activity.

Hogue, M.G.; Priester, H.P.

1994-06-01

36

Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory  

SciTech Connect

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.

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

1999-04-02

37

The Defense Waste Processing Facility: Two Years of Radioactive Operation  

SciTech Connect

The Defense Waste Processing Facility (DWPF) at the Savannah River Site in Aiken, SC is currently immobilizing high level radioactive sludge waste in borosilicate glass. The DWPF began vitrification of radioactive waste in May, 1996. Prior to that time, an extensive startup test program was completed with simulated waste. The DWPF is a first of its kind facility. The experience gained and data collected during the startup program and early years of operation can provide valuable information to other similar facilities. This experience involves many areas such as process enhancements, analytical improvements, glass pouring issues, and documentation/data collection and tracking. A summary of this experience and the results of the first two years of operation will be presented.

Marra, S.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Gee, J.T.; Sproull, J.F.

1998-05-01

38

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...

39

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 ...

40

General view from outside the Orbiter Processing Facility at the ...  

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

General view from outside the Orbiter Processing Facility at the Kennedy Space Center with the bay doors open as the Orbiter Discovery is atop the transport vehicle prepared to be moved over to the Vehicle Assembly Building. - Space Transportation System, Orbiter Discovery (OV-103), Lyndon B. Johnson Space Center, 2101 NASA Parkway, Houston, Harris County, TX

41

Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility  

SciTech Connect

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.

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

1996-06-01

42

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

SciTech Connect

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.

DAVIS, W.E.

2000-03-08

43

Lowering respirable dust exposures at mineral processing facilities  

SciTech Connect

This article discusses three research projects performed by the National Institute for Occupational Safety and Health (formerly the Bureau of Mines), that reduce the respirable dust exposure of plant workers at mineral processing facilities. All three of these projects are very different but they all have same goal of reducing worker exposure to respirable dust at mineral processing facilities. The first project deals with a total mill ventilation system that reduces dust levels throughout an entire building and lowers the dust exposure of everyone working in the structure. The second project describes a bag and belt cleaner device that reduces the amount of dust on the outside of bags of product and primarily reduces the dust exposure of the bag stackers, as well as anyone handling the bags until their end use. The third project discusses how to reduce a worker's dust exposure from secondary dust sources through improved work practices. This area of research can potentially impact all workers at these facilities. All three of these research projects have been shown to significantly reduce the dust exposure of workers at mineral processing facilities.

Cecala, A.B.; Timko, R.J.; Thimons, E.D.

1999-07-01

44

APET methodology for Defense Waste Processing Facility: Mode C operation  

SciTech Connect

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.

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

1995-04-01

45

Design characteristics for facilities which process hazardous particulate  

SciTech Connect

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.

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

1998-12-01

46

76 FR 44049 - Guidance for Fuel Cycle Facility Change Processes  

Federal Register 2010, 2011, 2012, 2013, 2014

On July 14, 2011 (76 FR 41527), the U.S. Nuclear Regulatory Commission (NRC or Commission) re-issued Draft Regulatory Guide, DG- 3037, ``Guidance for Fuel Cycle Facility Change Processes'' in the Federal Register for a 30 day public comment period. The NRC is extending the public comment period for DG-3037 from August 12, 2011 to September 16, 2011. DG-3037 describes the types of changes for fuel......

2011-07-22

47

NASA Regional Planetary Image Facility image retrieval and processing system  

NASA Technical Reports Server (NTRS)

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.

Slavney, Susan

1986-01-01

48

Waste Receiving & Processing (WRAP) Facility Final Safety Analysis Report (FSAR)  

SciTech Connect

The hazard and accident analysis concludes that all risks associated with operation of Waste Receiving and Processing Facility (WRAP) are within evaluation guidelines. Unmitigated effects of releases in all bounding accidents are below safety class criteria, eliminating the need for safety-class designation of any structures, systems, or components. Process enclosures are considered to be safety-significant, based on worker safety considerations and maintenance of defense in depth. This Final Safety Analysis Report demonstrates that adherence to the safety basis will ensure necessary operational safety considerations have been addressed sufficiently and justifies the adequacy of the safety basis in protecting the health and safety of the public, workers, and the environment.

TOMASZEWSKI, T.A.

2001-07-10

49

Accident Fault Trees for Defense Waste Processing Facility  

SciTech Connect

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).

Sarrack, A.G.

1999-06-22

50

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

SciTech Connect

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.

Edwards, T.; Peeler, D.

2014-10-28

51

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

Code of Federal Regulations, 2014 CFR

...false Process for modifying covered chemicals and facilities. 372.20 Section...COMMUNITY RIGHT-TO-KNOW PROGRAMS TOXIC CHEMICAL RELEASE REPORTING: COMMUNITY RIGHT-TO-KNOW...20 Process for modifying covered chemicals and facilities. (a) Request...

2014-07-01

52

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

Code of Federal Regulations, 2012 CFR

...false Process for modifying covered chemicals and facilities. 372.20 Section...COMMUNITY RIGHT-TO-KNOW PROGRAMS TOXIC CHEMICAL RELEASE REPORTING: COMMUNITY RIGHT-TO-KNOW...20 Process for modifying covered chemicals and facilities. (a) Request...

2012-07-01

53

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

Code of Federal Regulations, 2013 CFR

...false Process for modifying covered chemicals and facilities. 372.20 Section...COMMUNITY RIGHT-TO-KNOW PROGRAMS TOXIC CHEMICAL RELEASE REPORTING: COMMUNITY RIGHT-TO-KNOW...20 Process for modifying covered chemicals and facilities. (a) Request...

2013-07-01

54

An Automated 476 MHz RF Cavity Processing Facility at SLAC  

SciTech Connect

The 476 MHz accelerating cavities currently used at SLAC are those installed on the PEP-II B-Factory collider accelerator. They are designed to operate at a maximum accelerating voltage of 1 MV and are routinely utilized on PEP-II at voltages up to 750 kV. During the summer of 2003, SPEAR3 will undergo a substantial upgrade, part of which will be to replace the existing 358.54 MHz RF system with essentially a PEP-II high energy ring (HER) RF station operating at 476.3 MHz and 3.2 MV (or 800 kV/cavity). Prior to installation, cavity RF processing is required to prepare them for use. A dedicated high power test facility is employed at SLAC to provide the capability of conditioning each cavity up to the required accelerating voltage. An automated LabVIEW based interface controls and monitors various cavity and test stand parameters, increasing the RF fields accordingly such that stable operation is finally achieved. This paper describes the high power RF cavity processing facility, highlighting the features of the automated control system and illustrating its operation with some recent high power processing results.

McIntosh, P.

2003-07-29

55

Orbiter processing facility service platform failure and redesign  

NASA Technical Reports Server (NTRS)

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.

Harris, Jesse L.

1988-01-01

56

Nuclear criticality safety evaluation -- DWPF Late Wash Facility, Salt Process Cell and Chemical Process Cell  

SciTech Connect

The Savannah River Site (SRS) High Level Nuclear Waste will be vitrified in the Defense Waste Processing Facility (DWPF) for long term storage and disposal. This is a nuclear criticality safety evaluation for the Late Wash Facility (LWF), the Salt Processing Cell (SPC) and the Chemical Processing Cell (CPC). of the DWPF. Waste salt solution is processed in the Tank Farm In-Tank Precipitation (ITP) process and is then further washed in the DWPF Late Wash Facility (LWF) before it is fed to the DWPF Salt Processing Cell. In the Salt Processing Cell the precipitate slurry is processed in the Precipitate Reactor (PR) and the resultant Precipitate Hydrolysis Aqueous (PHA) produce is combined with the sludge feed and frit in the DWPF Chemical Process Cell to produce a melter feed. The waste is finally immobilized in the Melt Cell. Material in the Tank Farm and the ITP and Extended Sludge processes have been shown to be safe against a nuclear criticality by others. The precipitate slurry feed from ITP and the first six batches of sludge feed are safe against a nuclear criticality and this evaluation demonstrates that the processes in the LWF, the SPC and the CPC do not alter the characteristics of the materials to compromise safety.

Williamson, T.G.

1994-10-17

57

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

SciTech Connect

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

Lambert, D.P.

2000-03-22

58

Risk assessment on processing facility of raw organic garbage.  

PubMed

To investigate the cause of an explosion during disposal processing of raw garbage, the property of the raw garbage was primarily examined by a thermo gravimetry-differential thermal analyzer. With mutable oil concentration, the results showed variable onset temperatures of the exothermal reaction for the samples, for example, decreasing from 150 degrees C in the samples typically containing 10.9-14.1% oil to 114 degrees C when the oil content was raised to 40%. The disposal process was then simulated in a laboratory-scale facility being heated by hot air of 150 degrees C, which was blown into the bottom through nozzles. In the case of the dried garbage containing 14.1% oil, white smoke emitted after several hours, accompanying with an abrupt rise of the temperatures in particular at the bottom of the facility. The maximum temperature reached to 1070 degrees C. Meanwhile, gases, including flammable ones, whose amounts were CO2 approximately CO>H2>methane>ethane in order, were yielded. It indicated that smoldering developed from the zones near the hot air supply nozzle and propagated along the pathway of the imposed air. The continuously released gases possibly induced the transition of smoldering to flame or explosion after accumulating for hours. PMID:18006152

Li, Xin-Rui; Koseki, Hiroshi; Iwata, Yusaku

2008-06-15

59

Leonardo MPLM in the Space Station Processing Facility  

NASA Technical Reports Server (NTRS)

(Center) The Multi-Purpose Launch Module, named Leonardo, awaits processing in the Space Station Processing Facility (SSPF). At left is a Rack Insertion Device. Above the Leonardo are the windows of the tour room where visitors can watch the activities in the SSPF. Scheduled to be launched on STS-100 on Dec. 2, 1999, the Italian-built MPLM will be carried in the payload bay of the Shuttle orbiter, and will provide storage and additional work space for up to two astronauts when docked to the International Space Station. The Leonardo is the first of three modules being provided by Alenia Aerospazio. The second MPLM, to be handed over in April 1999, is named Raffaello. A third module, to be named Donatello, is due to be delivered in October 2000 for launch in January 2001.

1998-01-01

60

Containerless Processing in Reduced Gravity Using the TEMPUS Facility  

NASA Technical Reports Server (NTRS)

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).

Roger, Jan R.; Robinson, Michael B.

1996-01-01

61

Characterization of emissions from scrap metal processing facilities  

SciTech Connect

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.

Norco, J.E. [Versar, Inc., Lombard, IL (United States); Tyler, T. [Inst. of Scrap Recycling Industries, Inc., Washington, DC (United States)

1997-12-31

62

A survey of decontamination processes applicable to DOE nuclear facilities  

SciTech Connect

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.

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

1997-05-01

63

Defense Waste Processing Facility wasteform and canister description: Revision 2  

SciTech Connect

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.

Baxter, R.G.

1988-12-01

64

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

SciTech Connect

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.

Ziehm, Ronny; Pichurin, Sergey Grigorevich

2003-02-27

65

10 CFR 70.72 - Facility changes and change process.  

Code of Federal Regulations, 2013 CFR

... Section 70.72 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED...DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Additional Requirements...Possess a Critical Mass of Special Nuclear Material § 70.72 Facility... (i) Create new types of accident sequences that, unless...

2013-01-01

66

10 CFR 70.72 - Facility changes and change process.  

Code of Federal Regulations, 2011 CFR

... Section 70.72 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED...DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Additional Requirements...Possess a Critical Mass of Special Nuclear Material § 70.72 Facility... (i) Create new types of accident sequences that, unless...

2011-01-01

67

10 CFR 70.72 - Facility changes and change process.  

Code of Federal Regulations, 2014 CFR

... Section 70.72 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED...DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Additional Requirements...Possess a Critical Mass of Special Nuclear Material § 70.72 Facility... (i) Create new types of accident sequences that, unless...

2014-01-01

68

10 CFR 70.72 - Facility changes and change process.  

Code of Federal Regulations, 2012 CFR

... Section 70.72 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED...DOMESTIC LICENSING OF SPECIAL NUCLEAR MATERIAL Additional Requirements...Possess a Critical Mass of Special Nuclear Material § 70.72 Facility... (i) Create new types of accident sequences that, unless...

2012-01-01

69

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

Microsoft Academic Search

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

Pillay; K. K. S

1994-01-01

70

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

71

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

72

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

73

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

74

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

75

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

76

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

77

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing plants and Support...

2010-07-01

78

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

Code of Federal Regulations, 2010 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2010-07-01

79

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

Code of Federal Regulations, 2014 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing plants and Support...

2014-07-01

80

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

Code of Federal Regulations, 2012 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2012-07-01

81

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

Code of Federal Regulations, 2013 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2013-07-01

82

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

Code of Federal Regulations, 2014 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2014-07-01

83

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

Code of Federal Regulations, 2012 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2012-07-01

84

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

Code of Federal Regulations, 2014 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2014-07-01

85

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

Code of Federal Regulations, 2014 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2014-07-01

86

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

Code of Federal Regulations, 2013 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2013-07-01

87

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

Code of Federal Regulations, 2013 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2013-07-01

88

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

Code of Federal Regulations, 2013 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2013-07-01

89

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

Code of Federal Regulations, 2014 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2014-07-01

90

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

Code of Federal Regulations, 2012 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2012-07-01

91

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

Code of Federal Regulations, 2011 CFR

...false Special performance standards-coal processing plants and support facilities...827 Special performance standards—coal processing plants and support facilities...Permanent Program Performance Standards—Coal Processing Plants and Support...

2011-07-01

92

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

SciTech Connect

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.

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

2003-02-26

93

Integrating Sustainability Programs into the Facilities Capital Planning Process  

ERIC Educational Resources Information Center

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…

Buchanan, Susan

2011-01-01

94

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

SciTech Connect

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.

Eibling, R.E.

1990-01-01

95

Hardware Development Process for Human Research Facility Applications  

NASA Technical Reports Server (NTRS)

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.

Bauer, Liz

2000-01-01

96

Safety and environmental process for the design and construction of the National Ignition Facility  

SciTech Connect

The National Ignition Facility (NIF) is a U.S. Department of Energy (DOE) laser fusion experimental facility currently under construction at the Lawrence Livermore National Laboratory (LLNL). This paper describes the safety and environmental processes followed by NIF during the design and construction activities.

Brereton, S.J., LLNL

1998-05-27

97

Pulmonary alveolar proteinosis in workers at an indium processing facility.  

PubMed

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 granulocytemacrophage-colonystimulating 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

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

2010-03-01

98

Receipt of the Observatory at the Orbital Processing Facility - Duration: 1:01.  

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...

99

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

SciTech Connect

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.

NELSON, J.V.

1999-05-12

100

Criticality Safety Evaluation Report for the Cold Vacuum Drying (CVD) Facilities Process Water Handling System  

SciTech Connect

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.

KESSLER, S.F.

2000-08-10

101

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

SciTech Connect

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.

Amato, L.C.; Franklin, J.D.; Hyre, R.A.; Lowy, R.M.; Millar, J.S.; Pottmeyer, J.A. [Los Alamos Technical Associates, Kennewick, WA (United States); Duncan, D.R. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01

102

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

SciTech Connect

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.

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

1996-07-26

103

Determination of Satisfactory Scale for Data Processing Facilities  

ERIC Educational Resources Information Center

An analysis to ascertain which electronic data processing (EDP) systems are most flexible in processing wide ranges of volumes efficiently. A simulation model of the job environment of three common EDP systems provides information on the shape of their cost functions in the neighborhood of optimality. (Author/LS)

Solomon, Susan L.

1974-01-01

104

CONTROLLING AIRBORNE AND WATER CONTAMINATION OF SHELL EGG PROCESSING FACILITIES  

Technology Transfer Automated Retrieval System (TEKTRAN)

For both food safety and quality reasons, distribution and level of bacteria in a food processing environment are of great concern to plant management, regulatory officials and consumers. Two of the primary methods by which bacteria become distributed in a processing plant are air and water. The st...

105

St. Louis demonstration final report: refuse processing plant equipment, facilities, and environmental evaluations  

Microsoft Academic Search

The results are presented 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 the power plants. Data on plant material flows and operating parameters, plant operating costs, characteristics of plant material flows, and emissions from various processing operations were obtained during

D. E. Fiscus; P. G. Gorman; M. P. Schrag; L. J. Shannon

1977-01-01

106

A new design concept for an automated peanut processing facility  

SciTech Connect

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.

Ertas, A.; Tanju, B.T. [Texas Tech Univ., Lubbock, TX (United States); Fair, W.T. [Long Shot, Inc., Seminole, TX (United States); Butts, C. [National Peanut Research Lab., Dawson, GA (United States)

1996-12-31

107

Lessons learned from the Siting Process of an Interim Storage Facility in Spain - 12024  

SciTech Connect

On 29 December 2009, the Spanish government launched a site selection process to host a centralised interim storage facility for spent fuel and high-level radioactive waste. It was an unprecedented call for voluntarism among Spanish municipalities to site a controversial facility. Two nuclear municipalities, amongst a total of thirteen municipalities from five different regions, presented their candidatures to host the facility in their territories. For two years the government did not make a decision. Only in November 30, 2011, the new government elected on 20 November 2011 officially selected a non-nuclear municipality, Villar de Canas, for hosting this facility. This paper focuses on analysing the factors facilitating and hindering the siting of controversial facilities, in particular the interim storage facility in Spain. It demonstrates that involving all stakeholders in the decision-making process should not be underestimated. In the case of Spain, all regional governments where there were candidate municipalities willing to host the centralised interim storage facility, publicly opposed to the siting of the facility. (author)

Lamolla, Meritxell Martell [MERIENCE Strategic Thinking, 08734 Olerdola, Barcelona (Spain)

2012-07-01

108

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

SciTech Connect

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)

Bricker, Jonathan M.; Fellinger, Terri L.; Staub, Aaron V.; Ray, Jeff W.; Iaukea, John F. [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)] [Savannah River Remediation, Aiken, South Carolina, 29808 (United States)

2013-07-01

109

Lax regulation of oil vessels and processing facilities continues  

SciTech Connect

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.

Sankovitch, N.

1993-12-31

110

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 ...

111

Attached Bacterial Cell Contamination of Shell Egg Processing Facilities  

Technology Transfer Automated Retrieval System (TEKTRAN)

Sanitation is vital to providing safe, healthy food to consumers. Understanding the degree to which microorganisms persist on specific equipment or locations contributes to developing effective sanitation programs. Certain microbial populations may be used to determine areas within a processing pl...

112

Portable ATP Luminometry for Evaluating Salmon Roe Processing Facilities  

Microsoft Academic Search

Sanitation conditions in two salmon roe processing operations were evaluated by adenosine triphosphate (ATP) assays using a portable luminometer and single-use reaction swabs. The bioluminescent reaction provided real-time testing (< 1 min) when compared to standard microbiological analyses (48-72 hr). The ATP assay was quicker and more sensitive than a rapid protein assay (10 min) in detecting presence of biological

Brian H. Himelbloom; Susan M. Vitt; Chuck Crapo

2004-01-01

113

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

SciTech Connect

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.

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

1982-08-01

114

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

SciTech Connect

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)

Landon, L.F. (comp.)

1980-05-01

115

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...

116

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...

117

Facile one-step transfer process of graphene.  

PubMed

Chemical vapour deposition (CVD) is emerging as a popular method for growing large-area graphene on metal substrates. For transferring graphene to other substrates the technique generally used involves deposition of a polymer support with subsequent etching of the metal substrate. Here we report a simpler one-step transfer process. Few-layer graphene (FLG) grown on a Cu substrate were transferred to a silanized wafer by just pressing them together. Hydrogen bonding between the hydroxyl group on FLG and the amine group on silane molecules facilitate the transfer. PMID:21454931

Bajpai, Reeti; Roy, Soumyendu; Jain, Lokendra; Kulshrestha, Neha; Hazra, Kiran S; Misra, D S

2011-06-01

118

Defense waste processing facility (DWPF) environmental dosimetry data  

SciTech Connect

The original Environmental Impact Statement for the DWPF was issued in 1982. Since that time, estimated releases of radioactivity to the environment have changed because of the DWPF process. In addition, the methodology for calculating offsite doses from routine releases has changed. In anticipation of a potential supplement to the 1982 EIS, current dosimetry methodology has been used to estimate offsite doses from the current as-constructed estimate of radioactivity releases. Offsite doses have also been calculated for the radioactivity release data published in the 1982 EIS using current dosimetry methodology. The two data sets may therefore be used to compare the estimated original and current impacts. This memorandum documents the results of the offsite dose calculations for routine operation of the DWPF. Also included is a brief description of methodology and parameters used in the calculations. 8 refs., 2 figs., 10 tabs.

Marter, W.L.; Bauer, L.R.

1990-04-09

119

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

SciTech Connect

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.

TOMASZEWSKI, T.A.

2000-04-25

120

Radon Reduction Experience at a Former Uranium Processing Facility  

SciTech Connect

Approximately 6,200 cubic meters of waste containing about 2.0E8 MBq of radium-226 are stored in two large silos at the Fernald Site in southwest Ohio. The material is scheduled for retrieval, packaging, off site shipment and disposal by burial. Air in the silos above the stored material contained radon-222 at a concentration of 7.4 E5 Bq/L. Short-lived daughters formed by decay in these headspaces generated dose rates at contact with the top of the silos up to 1.05 mSv/hr and there complicate the process of retrieval. A Radon Control System (RCS) employing carbon adsorption beds has been designed under contract with the Fluor Fernald to remove most of the radon in the headspaces and maintain lower concentrations during periods when work on or above the domes is needed. Removing the radon also removes the short-lived daughters and reduces the dose rate near the domes to 20 to 30 {mu}Sv/hr. Failing to remove the radon would be costly, in the exposure of personnel needed to work extended periods at these moderate dose rates, or in dollars for the application of remote retrieval techniques. In addition, the RCS minimizes the potential for environmental releases. This paper describes the RCS, its mode of operation, and early experiences. The results of the test described herein and the experience gained from operation of the RCS during its first phase of continuous operation, will be used to determine the best air flow, and air flow distribution, the most desirable number and sequence number and sequence of adsorption beds to be used and the optimum application of air recycle within the RCS.

Eger, K. J.; Rutherford, L.; Rickett, K.; Fellman, R.; Hungate, S.

2004-02-29

121

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

SciTech Connect

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.

Not Available

1993-02-01

122

Facility siting as a decision process at the Savannah River Site  

SciTech Connect

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.

Wike, L.D.

1995-12-31

123

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

NASA Technical Reports Server (NTRS)

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.

Carter, Robert W.

2009-01-01

124

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

SciTech Connect

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.)

Not Available

1994-03-01

125

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

SciTech Connect

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.

Pillay, K.K.S.

1994-02-01

126

Ecological survey for the siting of the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility  

Microsoft Academic Search

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

Hoskinson

1994-01-01

127

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

SciTech Connect

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.

Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Garrett, R.J. [ABB Government Services, Aiken, SC (United States)

1993-10-01

128

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

SciTech Connect

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.

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

2013-01-26

129

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

SciTech Connect

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.

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

2012-11-09

130

Development and demonstration of the DWPF (Defense Waste Processing Facility) canister decontamination process using frit slurry blasting  

SciTech Connect

Stainless steel canisters will be filled with high-level radioactive waste glass in the Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The canister surface must be decontaminated to an acceptable level before welding the permanent closure and transferring the canister to temporary storage. This will be accomplished by blasting with an air-injected glass frit slurry which will remove the contaminated brown oxide layer that is produced during glass pouring. The contaminated slurry from the decon process becomes feed for the melter, thereby producing no secondary waste. Development of the equipment design, blasting sequence, and process parameters was achieved by testing a full-scale Experimental Canister Frit Blaster. The design improvements were incorporated in the fabrication of the remotely operated DWPF Canister Decontamination Chambers. Demonstration of these improvements and the additional equipment in the first CDC will be accomplished through operability testing at the Equipment Test Facility. 5 refs., 6 figs., 1 tab.

Harris, A.H.; Ward, C.R.

1986-01-01

131

Software systems for processing and analysis at the NOVA high-energy laser facility  

Microsoft Academic Search

A typical laser interaction experiment at the NOVA high-energy laser facility produces in excess of 20 Mbytes of digitized data. Extensive processing and analysis of this raw data from a wide variety of instruments is necessary to produce results that can be readily used to interpret the experiment. Using VAX-based computer hardware, software systems have been set up to convert

J. M. Auerbach; D. S. Montgomery; E. W. McCauley; G. F. Stone

1986-01-01

132

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

Microsoft Academic Search

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

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

2008-01-01

133

Renovation of CPF (Chemical Processing Facility) for Development of Advanced Fast Reactor Fuel Cycle System  

Microsoft Academic Search

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

Shinichi Aose; Takafumi Kitajima; Kouji Ogasawara; Kazunori Nomura; Shigehiko Miyachi; Yoshiaki Ichige; Tadahiro Shinozaki; Shinichi Ohuchi

2008-01-01

134

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...

135

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

SciTech Connect

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.

Starkey, J.G.

1993-05-01

136

Regulatory Requirements for Pollution Prevention for the Salt Waste Processing Facility at Savannah River Site  

Microsoft Academic Search

Savannah River Site (SRS) is a Department of Energy facility for production of nuclear materials located near Aiken, South Carolina that is operated by the Westinghouse Savannah River Company. Waste sludges and salts generated from the processing of nuclear materials have been stored in underground storage tanks since operations began in the 1950s. These sludges and salts contain high levels

Malik

1999-01-01

137

Performance evaluation of process safety management systems of paint manufacturing facilities  

Microsoft Academic Search

The objective of this work was to develop a model to evaluate the performance of process safety management systems of paint manufacturing facilities. The model was constructed based on a three-level multi-attribute value model (MAVT) approach. The first level consisted of Deming's PDCA cycle, labeled as Plan, Do, Control, and Act Factors. The 20 attributes of the second level and

James I. Chang; Chiu-Lan Liang

2009-01-01

138

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

NASA Astrophysics Data System (ADS)

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.

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

139

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

SciTech Connect

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.

Bronfenbrenner, J.C.

1983-09-01

140

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

SciTech Connect

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.

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

141

Processing liquid radioactive waste by centrifuge and indrum dehydration facility at NPP Philippsburg  

SciTech Connect

Until 1989 the evaporator and filter concentrates have been treated by concreting. The centrifuge facility is used for the liquid waste from laundry, showers and also for processing filter concentrates and evaporator feedwater. The hot high pressure compacting of filter concentrates gives a volume reduction by a factor of 6. The evaporator concentrate is drained in a 200 l drum and this drum is heated by an external heating device. The indrum-dehydration facility reduces the treated volume by a factor of 12 compared with the former cementation.

Grundke, E.; Blaser, W. [NPP Philippsburg (Germany)

1993-12-31

142

Use of process monitoring for verifying facility design of large-scale reprocessing plants  

SciTech Connect

During the decade of the 1990s, the International Atomic Energy Agency (IAEA) faces the challenge of implementing safeguards in large, new reprocessing facilities. The Agency will be involved in the design, construction, checkout and initial operation of these new facilities to ensure effective safeguards are implemented. One aspect of the Agency involvement is in the area of design verification. The United States Support Program has initiated a task to develop methods for applying process data collection and validation during the cold commissioning phase of plant construction. This paper summarizes the results of this task. 14 refs., 1 tab.

Hakkila, E.A.; Zack, N.R. (Los Alamos National Lab., NM (USA)); Ehinger, M.H. (Oak Ridge National Lab., TN (USA)); Franssen, F. (International Atomic Energy Agency, Vienna (Austria))

1991-01-01

143

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

SciTech Connect

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.

Angelini, P

2004-04-27

144

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

SciTech Connect

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.

Angelini, P

2004-04-27

145

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

SciTech Connect

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.

RYAN GW

2008-04-25

146

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

NASA Technical Reports Server (NTRS)

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.

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

1999-01-01

147

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

SciTech Connect

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).

Sullivan, N.

1995-05-02

148

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

SciTech Connect

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.

Casella, V

2006-04-24

149

Distinguishing between Natural Crude Oil Seepage and Anthropogenic Petroleum Hydrocarbons in Soils at a Crude Oil Processing Facility, Coastal California  

Microsoft Academic Search

Crude oil from offshore deposits in the Miocene Monterey Formation is commonly processed at facilities along the California coast. This formation is known for natural crude oil seepage (NCS), manifested at a California oil and gas processing facility (the site) as small pools on the ground surface, discharge from an adjacent bluff, and as free product in a hand-dug well.

Susan J. McCaffery; Andy Davis; David Craig

2009-01-01

150

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

SciTech Connect

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.

Hsu, R.H.; Delley, A.O.; Alexander, G.J.; Clark, E.A.; Holder, J.S.; Lutz, R.N.; Malstrom, R.A.; Nobles, B.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Carson, S.D. [Sandia National Laboratories, New Mexico, NM (United States); Peterson, P.K. [Sandia National Laboratories, New Mexico, NM (United States)

1997-11-30

151

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

SciTech Connect

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.

Forest, Cary B.

2013-09-19

152

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

NASA Technical Reports Server (NTRS)

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.

1993-01-01

153

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

SciTech Connect

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.

Ades, M.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Garrett, R.J. [ABB Government Services, Aiken, SC (United States)

1993-12-31

154

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

PubMed

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

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

2008-05-01

155

STS-99 Payload Door Closure in Orbiter Processing Facility # 2, Endeavour, (SRTM)  

NASA Technical Reports Server (NTRS)

The primary objective of the STS-99 mission was to complete high resolution mapping of large sections of the Earth's surface using the Shuttle Radar Topography Mission (SRTM), a specially modified radar system. This videotape shows the SRTM in Endeavour's payload bay, while the payload bay doors are being closed. There are some views of the Orbiter Processing Facility and technicians in the clean room environment.

1999-01-01

156

U.S. Postal Service Brings Energy Efficiency, Solar Power to Northern California Processing Facility  

Microsoft Academic Search

As part of its ongoing drive to optimize efficiency and conserve natural resources, the U.S. Postal Service (USPS) completed major energy efficiency upgrades and one of the largest federal solar power installations in the nation, at the USPS's West Sacramento Processing & Distribution Center. The 573,000-square-foot mail facility is a major Postal Service hub in Northern California, employing more than

Ralph Petty; Diane Sable

2005-01-01

157

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

Microsoft Academic Search

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

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

2007-01-01

158

Process-related risk of beryllium sensitization and disease in a copper-beryllium alloy facility  

Microsoft Academic Search

Background Chronic beryllium disease (CBD), which primarily affects the lungs, occurs in sensitized beryllium-exposed individuals. At a copper-beryllium alloy strip and wire finishing facility we performed a cross-sectional survey to examine prevalences of beryllium sensitization and CBD, and relationships between sensitization and CBD and work areas\\/processes. Methods Current employees (185) were offered beryllium lymphocyte proliferation testing (BeLPT) for sensitization, clinical

Christine R. Schuler; Michael S. Kent; David C. Deubner; Michael T. Berakis; Michael McCawley; Paul K. Henneberger; Milton D. Rossman; Kathleen Kreiss

2005-01-01

159

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

SciTech Connect

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)

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

1988-12-01

160

Systematic engineering tools for describing and improving medication administration processes at rural healthcare facilities.  

PubMed

This study demonstrates a series of systematic methods for mapping medication administration processes and for elaborating violations of work standards at two rural hospitals. Thirty-four observational periods were conducted to capture the details of clinical activities, and hierarchical task analysis (HTA) was used to demonstrate the current medication administration process. Facility nurse managers in five units across the two facilities participated in focus group discussions to validate the observational data and to generate a reliable context-appropriate medication administration process. The potential errors or misconduct when passing the drugs were identified, such as unsafe storage and transportation of drugs from room to room. Those hazards would cause drug contamination, loss, or access by unauthorized individuals. Hospitals without 24-hour pharmacy coverage and other interruptions would hinder the medication administration process. Preparing drugs for more than one patient at a time would increase the risk of passing the drugs to the wrong patient. This study shows the use of observation and focus groups to describe and identify violations in the medication administration process. A clear road map for continuous clinical process improvement obtained from the current study could be used to help future health information technology implementation. PMID:25024094

Huang, Yuan-Han; Gramopadhye, Anand K

2014-11-01

161

Space Station microgravity and materials processing facility A national laboratory dedicated to U.S. interests  

NASA Technical Reports Server (NTRS)

The Microgravity and Materials Processing Facility (MMPF) of the Space Station is examined. The MMPF is designed to accommodate individual experiments and associated hardware and is to be housed in the Manufacturing and Technology Laboratory Module. The objectives of the microgravity and materials processing study and the user, experiment/equipment, MMPF system requirements, and programmatics and planning development tasks of the study are described. Consideration is given to the acceleration environment, on-orbit sample preparation and analysis, mission-time-line analyses, and payload complement trades. Diagrams of the MMPF are presented.

Atkins, H. L.; Pevey, E. R.; Mookherji, T.

1986-01-01

162

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

PubMed

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

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

2002-09-01

163

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

SciTech Connect

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.

Jasen, W.G.

1998-01-07

164

Solid waste facilities location using of analytical network process and data envelopment analysis approaches.  

PubMed

Selection of the appropriate site for solid waste facilities is a complex problem and requires an extensive evaluation process, because it is very difficult to develop a selection criterion that can precisely describe the preference of one location over another. Therefore selection of these sites can be viewed as a multiple criteria decision-making or multiple attributes decision-making problem. For this purpose, we propose a technique that can effectively take managerial preferences and subjective data into consideration, along with quantitative factors. The tool proposed here relies on the use of the analytical network process (ANP) and to help integrate managerial evaluations into a more quantitatively based decision tool, data envelopment analysis (DEA) is applied. In this paper, a location selection procedure is presented to construct an undesirable facility applying ANP and DEA approaches in two stages. In the first stage ANP approach is used, results of this stage are inputs for the second stage. In this stage, DEA is applied to select the best location. Finally, to illustrate the proposed framework, at "Results and discussion" section, a total of four undesirable facility locations are evaluated. PMID:22382043

Khadivi, M R; Fatemi Ghomi, S M T

2012-06-01

165

Containerless Processing in Reduced Gravity Using the TEMPUS Facility during MSL-1 and MSL-1R  

NASA Technical Reports Server (NTRS)

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. equal to 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 (Tiegelfreies ElektroMagnetisches Prozessieren Unter Schwerelosgkeit) facility is a research instrument designed to perform electromagnetic levitation studies in reduced gravity. TEMPUS is a joint undertaking between DARA, the German Space Agency, and the Microgravity Science and Applications Division of NASA. The George C. Marshall Space Flight Center provides the leadership for scientific and management efforts which support the four US PI teams which performed experiments in the TEMPUS facility. The facility is sensitive to accelerations in the 1-10 Hz range. This became evident during the MSL-1 mission. Analysis of accelerometer and video data indicated that loss of sample control occurred during crew exercise periods which created disturbances in this frequency range. Prior to the MSL-1R flight the TEMPUS team, the accelerometer support groups and the mission operations team developed a strategy to provide for the operation of the facility without such disturbances. The successful implementation of this plan led to the highly successful operation of this facility during MSL-1R.

Rogers, Jan R.

1998-01-01

166

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

SciTech Connect

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.

Coates, Gareth [Centre for Sustainable Manufacturing and Reuse/Recycling Technologies (SMART), Wolfson School of Mechanical and Manufacturing Engineering, Loughborough University, Loughborough LE11 3TU (United Kingdom)], E-mail: G.Coates@lboro.ac.uk; Rahimifard, Shahin [Centre for Sustainable Manufacturing and Reuse/Recycling Technologies (SMART), Wolfson School of Mechanical and Manufacturing Engineering, Loughborough University, Loughborough LE11 3TU (United Kingdom)

2009-01-15

167

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

NASA Astrophysics Data System (ADS)

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.

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

168

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

E-print Network

The Canadian Penning Trap mass spectrometer has made mass measurements of 33 neutron-rich nuclides provided by the new Californium Rare Isotope Breeder Upgrade (CARIBU) facility at Argonne National Laboratory. The studied region includes the 132Sn 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.

J. Van Schelt; D. Lascar; G. Savard; J. A. Clark; P. F. Bertone; S. Caldwell; A. Chaudhuri; 1 A. F. Levand; G. Li; G. E. Morgan; R. Orford; R. E. Segel; K. S. Sharma; M. G. Sternberg

2013-07-01

169

First results from the CARIBU facility: mass measurements on the r-process path.  

PubMed

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 132Sn 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. PMID:23971550

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

170

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

NASA Technical Reports Server (NTRS)

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.

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

1993-01-01

171

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

NASA Technical Reports Server (NTRS)

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.

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

172

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

SciTech Connect

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.

Jantzen, C.; Johnson, F.

2012-06-05

173

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

NASA Astrophysics Data System (ADS)

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.

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

2009-07-01

174

STS-35 Astronomy Laboratory 1 (ASTRO-1) telescopes at KSC processing facility  

NASA Technical Reports Server (NTRS)

STS-35 Astronomy Laboratory 1 (ASTRO-1) payload is processed at Kennedy Space Center (KSC) facility. In the foreground, mounted on a two-axis pointing system (TAPS) is the Broad Band X Ray Telescope (BBXRT). Only one of the three ultraviolet telescopes mounted on the instrument pointing system (IPS) is visible - the Ultraviolet Imaging Telescope (UIT). Above the UIT is a star tracker (AST). ASTRO-1 telescopes on unpressurized pallets (u-pallets) will be inserted in Columbia's, Orbiter Vehicle (OV) 102's, payload bay (PLB). The STS-35 payload is the first horizontal payload flown since late 1985. View provided by KSC with alternate number KSC-90PC-398.

1990-01-01

175

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

Code of Federal Regulations, 2012 CFR

...RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE MICHIGAN § 922.827 Special performance standards—coal processing plants and support facilities not located at or near the...

2012-07-01

176

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

Code of Federal Regulations, 2011 CFR

...RECLAMATION AND ENFORCEMENT, DEPARTMENT OF THE INTERIOR PROGRAMS FOR THE CONDUCT OF SURFACE MINING OPERATIONS WITHIN EACH STATE IDAHO § 912.827 Special performance standards—coal processing plants and support facilities not located at or near the...

2011-07-01

177

A Facile Approach to Robust Superhydrophobic 3D Coatings via Connective-Particle Formation using the Electrospraying Process  

PubMed Central

This work demonstrates a facile fabrication method to produce superhydrophobic coatings on chemically distinct materials using the electrospraying process. Coatings are mechanically robust, three-dimensional, and formed using a single fabrication step. PMID:23235806

Yohe, Stefan T.; Grinstaff, Mark W.

2013-01-01

178

A facile approach to robust superhydrophobic 3D coatings via connective-particle formation using the electrospraying process.  

PubMed

This work demonstrates a facile fabrication method to produce superhydrophobic coatings on chemically distinct materials using the electrospraying process. Coatings are mechanically robust, three-dimensional, and formed using a single fabrication step. PMID:23235806

Yohe, Stefan T; Grinstaff, Mark W

2013-01-28

179

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

SciTech Connect

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.

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

2008-01-15

180

Recent Process and Equipment Improvements to Increase High Level Waste Throughput at The Defense Waste Processing Facility (DWPF)  

SciTech Connect

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 an 8 % waste throughput increase over the standard 28 % waste loading based upon operational efficiencies. Improvements in canister production include the pour spout heated bellows liner (7 %), 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 14 %. 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. (authors)

O'Driscoll, R.J.; Barnes, A.B.; Coleman, J.R.; Glover, T.L.; Hopkins, R.C.; Iverson, D.C.; Leita, J.N. [Defense Waste Processing Facility, Washington Savannah River Co. (WSRC), Aiken, SC (United States)

2008-07-01

181

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

SciTech Connect

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.

Koopman, D. C.

2004-12-31

182

St. Louis demonstration: refuse processing plant equipment, facilities, and environmental evaluations. Final report Sep 74Sep 75  

Microsoft Academic Search

The 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 operating parameters, plant operating costs, characteristics of plant material flows, and emissions from various processing operations were obtained during

D. E. Fiscus; P. G. Gorman; M. P. Schrag; L. J. Shannon

1977-01-01

183

Exposure assessment for a cohort of workers at a former uranium processing facility.  

PubMed

Exposure was assessed for a cohort of 6409 workers at a former uranium processing facility as part of a mortality study. Workers at the facility had potential for exposure to a wide variety of radiological and chemical agents including uranium, thorium, radon, external ionizing radiation, acid mists, asbestos, and various solvents. Organ dose from internal exposure to uranium was assessed, along with dose from external ionizing radiation and exposure to radon. Qualitative assessment of exposure to thorium, acid mists, asbestos, coal dust, welding fumes, and other chemicals was also performed. Mean cumulative organ dose from internal uranium exposure ranged from 1.1 mGy (lung) to 6.7 ?Gy (pancreas). Mean cumulative external ionizing radiation dose was 13.4 mGy. Mean cumulative radon exposure was 26 working level months (WLMs). The chemical agents to which the largest numbers of study subjects were exposed were acid mists, machining fluids, and a tributyl phosphate/kerosene mixture used in the refining process. PMID:22534696

Anderson, Jeri L; Daniels, Robert D; Fleming, Donald A; Tseng, Chih-Yu

2012-07-01

184

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

SciTech Connect

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)

Behrouzi, Aria [Savannah River Remediation, LLC (United States); Zamecnik, Jack [Savannah River National Laboratory, Aiken, South Carolina, 29808 (United States)

2012-07-01

185

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

SciTech Connect

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.

Hastings, R.L.

1993-09-01

186

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

SciTech Connect

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.

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

1993-10-01

187

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

SciTech Connect

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)

Ping, M.; Hill, M.; Harrison, J.; Wise, D. [Studsvik, Inc., Erwin, TN (United States)

2007-07-01

188

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

NASA Technical Reports Server (NTRS)

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.

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

1995-01-01

189

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

NASA Astrophysics Data System (ADS)

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.

Ramli, Razamin; Cheng, Kok-Min

2014-07-01

190

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

SciTech Connect

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.

SK Sundaram; JM Perez, Jr.

2000-09-06

191

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

SciTech Connect

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.

Amerine, D.B.

1982-09-01

192

Bisphenol A concentrations in receiving waters near US manufacturing and processing facilities.  

PubMed

Bisphenol A (BPA) (CAS 80-05-7) was analyzed in receiving waters upstream and downstream of US manufacturers (1996 and 1997) and processors (1997) during seasonal low flow periods. BPA was not detected (< 1 microgram/l) in any surface water sample in 1996 or at six of seven sites in 1997. Concentrations near the seventh site ranged from 2 to 8 micrograms/l; however, its receiving stream had no measurable flow and concentrations represent undiluted effluent. All surface water concentrations from this and other studies were less than the freshwater predicted no effect concentration (PNEC) of 64 micrograms/l, suggesting that BPA discharges from manufacturing and processing facilities to surface water do not pose an environmental concern. PMID:10665389

Staples, C A; Dorn, P B; Klecka, G M; O'Block, S T; Branson, D R; Harris, L R

2000-03-01

193

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

NASA Technical Reports Server (NTRS)

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.

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

1976-01-01

194

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

SciTech Connect

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.

Toyonobu Nabemoto; Fujio Katahira; Tadatsugu Sakaya [IHI Corporation: Isogo-ku, Yokohama, Kanagawa pref, 235-8501 (Japan); Shinichi Aose; Takafumi Kitajima; Kouji Ogasawara; Kazunori Nomura; Shigehiko Miyachi; Yoshiaki Ichige; Tadahiro Shinozaki; Shinichi Ohuchi [Japan Atomic Energy Agency: Tokai-mura, Naka-gun, Ibaraki pref, 319-1194 (Japan)

2008-01-15

195

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

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…

Schwing, Carl M.

196

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

SciTech Connect

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.

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

1997-12-31

197

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)

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.

Hill, Gerald M.; Evans, Richard K.

2009-01-01

198

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

SciTech Connect

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.

Sanders, M.E.

1996-02-01

199

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

SciTech Connect

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'.

Best, D.

2010-08-04

200

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

NASA Technical Reports Server (NTRS)

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.

1988-01-01

201

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

SciTech Connect

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)

Anderson, Keith [Environmental Chemical Corporation, 1240 Bayshore Hwy, Burlingame, CA 94010 (United States)

2007-07-01

202

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

PubMed

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 16°C). 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

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

2014-10-17

203

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

SciTech Connect

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.

Edwards, T.; Mahannah, R.

2011-07-05

204

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

SciTech Connect

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.

Edwards, T.; Feller, M.

2011-07-05

205

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

SciTech Connect

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.

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

2010-06-09

206

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

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.

HOPKINS, A.M.; MINETTE, M.J.; KLOS, D.B.

2007-01-25

207

Reconnaissance hydrogeologic investigation of the Defense Waste Processing Facility and Vicinity, Savannah River Plant, South Carolina  

SciTech Connect

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.

Dennehy, K.F.; Prowell, D.C.; McMahon, P.B.

1989-01-01

208

CHARACTERIZATION OF A PRECIPITATE REACTOR FEED TANK (PRFT) SAMPLE FROM THE DEFENSE WASTE PROCESSING FACILITY (DWPF)  

SciTech Connect

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 ?m 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

Crawford, C.; Bannochie, C.

2014-05-12

209

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

SciTech Connect

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.

Farnsworth, R.K.; Mishima, J.

1988-12-01

210

Bioassay testing of simulated effluent from the Defense Waste Processing Facility  

SciTech Connect

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.

Fliermans, C.B.

1984-12-11

211

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...

212

Hypertension and hematologic parameters in a community near a uranium processing facility  

SciTech Connect

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.

Wagner, Sara E., E-mail: swagner@uga.edu [College of Public Health, Department of Epidemiology and Biostatistics, Paul D. Coverdell Center for Biomedical and Health Sciences, University of Georgia, 500 D.W. Brooks Drive, Athens, GA 30602-7396 (United States); Burch, James B. [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States) [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC (United States); WJB Dorn Veteran's Affairs Medical Center, Columbia, SC (United States); Bottai, Matteo [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States)] [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); Pinney, Susan M. [College of Medicine, Department of Environmental Health, University of Cincinnati, Cincinnati, OH (United States)] [College of Medicine, Department of Environmental Health, University of Cincinnati, Cincinnati, OH (United States); Puett, Robin [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States) [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC (United States); Arnold School of Public Health, Department of Environmental Health Sciences, University of South Carolina, Columbia, SC (United States); Porter, Dwayne [Arnold School of Public Health, Department of Environmental Health Sciences, University of South Carolina, Columbia, SC (United States)] [Arnold School of Public Health, Department of Environmental Health Sciences, University of South Carolina, Columbia, SC (United States); Vena, John E. [College of Public Health, Department of Epidemiology and Biostatistics, Paul D. Coverdell Center for Biomedical and Health Sciences, University of Georgia, 500 D.W. Brooks Drive, Athens, GA 30602-7396 (United States)] [College of Public Health, Department of Epidemiology and Biostatistics, Paul D. Coverdell Center for Biomedical and Health Sciences, University of Georgia, 500 D.W. Brooks Drive, Athens, GA 30602-7396 (United States); Hebert, James R. [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States) [Arnold School of Public Health, Department of Epidemiology and Biostatistics, University of South Carolina, Columbia, SC (United States); South Carolina Statewide Cancer Prevention and Control Program, Columbia, SC (United States)

2010-11-15

213

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

Microsoft Academic Search

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

2006-01-01

214

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

Microsoft Academic Search

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

J. L. WESTCOTT

2007-01-01

215

A Microsoft Project-Based Planning, Tracking, and Management Tool for the National Transonic Facility's Model Changeover Process  

NASA Technical Reports Server (NTRS)

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.

Vairo, Daniel M.

1998-01-01

216

Screening study for waste biomass to ethanol production facility using the Amoco process in New York State. Final report  

SciTech Connect

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.

NONE

1995-08-01

217

Mechanical design and fabrication of a prototype facility for processing NaK using a chlorine reaction method  

SciTech Connect

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.

Dafoe, R.; Keller, D.; Stoll, F.

1990-01-01

218

Integration of the bio-ethanol process in a network of facilities for heat and power production from renewable sources using process simulation  

Microsoft Academic Search

The economic competitiveness of ethanol as a liquid fuel strongly depends on the amount of energy used during the production. To a sustainable production of fuel ethanol contributes also the use of energy from renewable sources. Process simulation is used to integrate a bio-ethanol plant in a network of facilities for heat and power production from residues of ethanol and

Walter Wukovits; Martin Pfeffer; Bettina Liebmann; Anton Friedl

2007-01-01

219

Automatic methods of the processing of data from track detectors on the basis of the PAVICOM facility  

NASA Astrophysics Data System (ADS)

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].

Aleksandrov, A. B.; Goncharova, L. A.; Davydov, D. A.; Publichenko, P. A.; Roganova, T. M.; Polukhina, N. G.; Feinberg, E. L.

2007-02-01

220

Analysis of the process applied to end-of-life vehicles in Authorised Treatment Facilities  

NASA Astrophysics Data System (ADS)

Authorised treatment facilities (ATFs) play a key role in the process undergone by vehicles when they reach their end of life (EoL) within the context of Directive 2000/53/EC. Whenever an EoL vehicle is received at an ATF, a certificate of destruction is issued. The process continues with the depollution of hazardous waste materials from the vehicle and dismantling of parts that will be reused or recycled. Finally, the remaining parts of the vehicle are transported to a shredding plant. Directive 2000/53/EC sets a number of environmental goals regarding the reuse and recycling of vehicle parts and the recovery of waste materials at the EoL of vehicles. These goals will condition the evolution of ATFs as they gradually become more restrictive. As of today, the goals set by Directive 2000/53/EC for the year 2006 are being met (1). However, it would be necessary to assess the situation of those parts that comprise the fraction of the vehicle that is not recycled, reused or recovered in order to predict the degree of compliance with the goals set for the year 2015 (recycling, reusing or recovering 95% by weight of EoL vehicles). The use of lighter materials—light alloys and reinforced plastics—as a vehicle weight-reducing strategy should be coordinated with the process carried out at ATFs in order to ensure compliance with the aforementioned goals. The results of our study seem to indicate that the most usual EoL scenario today—that in which practically all of the ferrous and non-ferrous metals are recycled and the lightweight fraction of vehicles and remaining inert materials are sent to a landfill—should be revised in order to reach the environmental goals set for the year 2015. To that avail, new strategies will have to be developed to allow for an adequate treatment—recycling, reuse or recovery—of those vehicle components that are presently sent to a landfill.

Muñoz, C.; Garraín, D.; Franco, V.; Royo, M.; Justel, D.; Vidal, R.

2009-11-01

221

The Earthscope USArray Array Network Facility (ANF): Evolution of Data Acquisition, Processing, and Storage Systems  

NASA Astrophysics Data System (ADS)

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.

Davis, G. A.; Battistuz, B.; Foley, S.; Vernon, F. L.; Eakins, J. A.

2009-12-01

222

Airborne concentrations of chrysotile asbestos in serpentine quarries and stone processing facilities in Valmalenco, Italy.  

PubMed

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 ?m 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

Cattaneo, Andrea; Somigliana, Anna; Gemmi, Mauro; Bernabeo, Ferruccio; Savoca, Domenico; Cavallo, Domenico M; Bertazzi, Pier A

2012-07-01

223

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

SciTech Connect

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).

Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

1993-02-01

224

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

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.

Aaron, G.; Wilmarth, B.

2011-09-19

225

Elimination Of Catalytic Hydrogen Generation In Defense Waste Processing Facility Slurries  

SciTech Connect

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.

Koopman, D. C.

2013-01-22

226

Processing capabilties for the elimination of contaminated metal scrapyards at DOE/ORO-managed sites. [Metal smelting facility  

SciTech Connect

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.

Mack, J.E.; Williams, L.C.

1982-01-01

227

The project RTPPP (Development of a realtime PPP processing facility) is planned to be a followup project of RAPPP (Innovative Algorithms for Rapid Precise Point Positioning),  

E-print Network

RTPPP The project RTPPP (Development of a realtime PPP processing facility) is planned to be a followup project of RAPPP (Innovative Algorithms for Rapid Precise Point Positioning), which has project. The performance of the developed realtime PPP processing facility will be evaluated

Schuh, Harald

228

Facile adsorption-dry process to incorporate Cu into TiO2 nanotube for highly efficient photocatalytic hydrogen production.  

PubMed

Cu species was introduced into TiO2 nanotube prepared by hydrothermal method via a facile adsorption-dry process. The fabricated sample exhibited excellent H2 generation activity (76.3 mmol h(-1) g(-1)(catalyst)), which was higher than most of the reported Cu incorporated TiO2 samples, even superior to some Pt/Pd/Au/Ni incorporated TiO2. Compared to wet impregnation and in-situ photo-deposition methods, the facile adsorption-dry process was much simpler but more efficient to introduce Cu species into TiO2 for H2 production. To fully understand the adsorption-dry process, characterizations of the samples were carried out by high-resolution transmission electron microscope, X-ray diffractometer, energy dispersive X-ray spectrometer, BET surface area analysis, UV-visible spectrophotometer and X-ray photoelectron spectroscopy. It was found that the facile adsorption-dry process could well maintain the morphology of TiO2 support, for instance, 1-D tubular structure and large BET surface area of TiO2 nanotube; moreover, the introduced Cu species was highly dispersed and intensively bonded with TiO2. All of these contributed to the high H2 generation activity. PMID:24245156

Xu, Shiping; Sun, Darren Delai

2013-10-01

229

An analysis of workplace exposures to benzene over four decades at a petrochemical processing and manufacturing facility (1962-1999).  

PubMed

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

Sahmel, J; Devlin, K; Burns, A; Ferracini, T; Ground, M; Paustenbach, D

2013-01-01

230

Evaluation Of A Turbidity Meter For Use At The Defense Waste Processing Facility  

SciTech Connect

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.

Mahannah, R. N.; Edwards, T. B.

2013-01-15

231

EVALUATION OF A TURBIDITY METER FOR USE AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

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.

Mahannah, R.; Edwards, T.

2013-06-04

232

QUALIFICATION OF THE SECOND ICS-3000 ION CHROMATOGRAPH FOR USE AT THE DEFENSE WASTE PROCESSING FACILITY  

SciTech Connect

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.

Edwards, T.; Mahannah, R.

2009-12-03

233

Qualification of the First ICS-3000 ION Chromatograph for use at the Defense Waste Processing Facility  

SciTech Connect

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.

Edwards, T; Mahannah, R.

2011-07-05

234

Renovation of CPF (Chemical Processing Facility) for Development of Advanced Fast Reactor Fuel Cycle System  

SciTech Connect

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.

Shinichi Aose; Takafumi Kitajima; Kouji Ogasawara; Kazunori Nomura; Shigehiko Miyachi; Yoshiaki Ichige; Tadahiro Shinozaki; Shinichi Ohuchi [Japan Atomic Energy Agency:4-33, Tokai-mura, Naka-gun, Ibaraki pref, 319-1194 (Japan)

2008-01-15

235

SUMMARY OF FY11 SULFATE RETENTION STUDIES FOR DEFENSE WASTE PROCESSING FACILITY GLASS  

SciTech Connect

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

Fox, K.; Edwards, T.

2012-05-08

236

Defense Waste Processing Facility: Report of task force on options to mitigate the effect of nitrite on DWPF operations  

SciTech Connect

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.

Randall, D. (ed.); Marek, J.C.

1992-03-01

237

Chemical hazards database and detection system for Microgravity and Materials Processing Facility (MMPF)  

NASA Technical Reports Server (NTRS)

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.

Steele, Jimmy; Smith, Robert E.

1991-01-01

238

SHORT CIRCUIT COORDINATION STUDY & ARC FLASH EVALUATION FOR LIQUID PROCESSING & CAPSULE STORAGE 310 FACILITY  

SciTech Connect

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.

TOWNE, C.M.

2003-12-26

239

Inorganic analyses of volatilized and condensed species within prototypic Defense Waste Processing Facility (DWPF) canistered waste  

SciTech Connect

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.

Jantzen, C.M.

1992-06-30

240

Wetland and Sensitive Species Survey Report for Y-12: Proposed Uranium Processing Facility (UPF)  

SciTech Connect

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.

Giffen, N.; Peterson, M.; Reasor, S.; Pounds, L.; Byrd, G.; Wiest, M. C.; Hill, C. C.

2009-11-01

241

Novel two-to-three hard hadronic processes and possible studies of generalized parton distributions at hadron facilities  

NASA Astrophysics Data System (ADS)

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 für 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.

Kumano, S.; Strikman, M.; Sudoh, K.

2009-10-01

242

INVITED EDITORIAL: Health effects of radiation exposure at uranium processing facilities  

Microsoft Academic Search

There is substantial public and scientific interest in the health consequences of exposures to ionising radiation in nuclear installations, in particular at nuclear fuels enrichment and production facilities. In this issue of Journal of Radiological Protection, McGeoghegan and Binks report on the follow-up of a cohort of over 19 000 uranium fuel and uranium hexafluoride production workers employed at the

Elisabeth Cardis; David Richardson

2000-01-01

243

Improving the Quality of Services in Residential Treatment Facilities: A Strength-Based Consultative Review Process  

ERIC Educational Resources Information Center

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…

Pavkov, Thomas W.; Lourie, Ira S.; Hug, Richard W.; Negash, Sesen

2010-01-01

244

Potential For Energy, Peak Demand, and Water Savings in California Tomato Processing Facilities  

E-print Network

Tomato processing is a major component of California's food industry. Tomato processing is extremely energy intensive, with the processing season coinciding with the local electrical utility peak period. Significant savings are possible...

Trueblood, A. J.; Wu, Y. Y.; Ganji, A. R.

2013-01-01

245

Ecological survey for the siting of the Mixed and Low-Level Waste Treatment Facility and the Idaho Waste Processing Facility  

SciTech Connect

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).

Hoskinson, R.L.

1994-05-01

246

Integrated knowledge-based system for the process/product design and fault diagnosis of plastics recycling facilities  

SciTech Connect

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.

DiRaddo, R.W.; Pecora, L.; Lim, B.; Salloum, G. [National Research Council of Canada, Boucherville, Quebec (Canada)

1995-11-01

247

STS-34 Galileo processing at KSC's SAEF-2 planetary spacecraft facility  

NASA Technical Reports Server (NTRS)

At the Kennedy Space Center's (KSC's) Spacecraft and Assembly Encapsulation Facility 2 (SAEF-2), the planetary spacecraft checkout facility, clean-suited technicians examine the Galileo spacecraft. The entire Galileo assembly includes a 5870-pound spacecraft, and an inertial upper stage (IUS) booster. Galileo is scheduled for launch aboard Atlantis, Orbiter Vehicle (OV) 104, on Space Shuttle Mission STS-34 in October 1989. After an initial boost from the IUS, Galileo will require a triple gravity assist from Venus and Earth to reach Jupiter in 1995. This complex trajectory will allow the first close flyby of two asteroids. The spacecraft will orbit Jupiter ten times, yielding the first extended observations of the planet, its satellites, and intense magnetospheric environment. NASA's Jet Propulsion Laboratory (JPL) manages the Galileo project. View provided by KSC with alternate number KSC-89P-570.

1989-01-01

248

Risk-Based Disposal Plan for PCB Paint in the TRA Fluorinel Dissolution Process Mockup and Gamma Facilities Canal  

SciTech Connect

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.

R. A. Montgomery

2008-05-01

249

FEASIBILITY EVALUATION AND RETROFIT PLAN FOR COLD CRUCIBLE INDUCTION MELTER DEPLOYMENT IN THE DEFENSE WASTE PROCESSING FACILITY AT SAVANNAH RIVER SITE 8118  

Microsoft Academic Search

Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste glass melting at the Defense Waste Processing Facility (DWPF) at Savannah River Site (SRS) as well as for other waste vitrification facilities. Proponents of this technology cite high temperature operation, high tolerance for noble metals and aluminum, high waste loading, high throughput capacity, and low equipment

A Barnes; D Dan Iverson; B Brannen Adkins

2008-01-01

250

Feasibility Evaluation and Retrofit Plan for Cold Crucible Induction Melter Deployment in the Defense Waste Processing Facility at Savannah River Site  

Microsoft Academic Search

Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste glass melting at the Defense Waste Processing Facility (DWPF) at Savannah River Site (SRS) as well as for other waste vitrification facilities. Proponents of this technology cite high temperature operation, high tolerance for noble metals and aluminum, high waste loading, high throughput capacity, and low equipment

A. B. Barnes; D. C. Iverson; B. J. Adkins; E. Tchemitcheff

2008-01-01

251

FEASIBILITY EVALUATION AND RETROFIT PLAN FOR COLD CRUCIBLE INDUCTION MELTER DEPLOYMENT IN THE DEFENSE WASTE PROCESSING FACILITY AT SAVANNAH RIVER SITE - 8118  

Microsoft Academic Search

Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste glass melting at the Defense Waste Processing Facility (DWPF) at Savannah River Site (SRS) as well as for other waste vitrification facilities. Proponents of this technology cite high temperature operation, high tolerance for noble metals and aluminum, high waste loading, high throughput capacity, and low equipment

A Barnes; D Dan Iverson; B Brannen Adkins

2007-01-01

252

Successful Demolition of Historic Cape Canaveral Air Force Station Launch Facilities: Managing the Process to Maximize Recycle Value to Fund Demolition  

Microsoft Academic Search

This paper will present the history of the Atlas 36 and Titan 40 Space Launch Complexes (SLC), the facility assessment process, demolition planning, recycle methodology, and actual facility demolition that resulted in a 40% reduction in baseline cost. These two SLC launched hundreds of payloads into space from Cape Canaveral Air Force Station (AFS), Florida. The Atlas-Centaur family of rockets

A. Jones; L. Hambro; K. Hooper

2008-01-01

253

RADIOLOGICAL CONTROLS FOR PLUTONIUM CONTAMINATED PROCESS EQUIPMENT REMOVAL FROM 232-Z CONTAMINATED WASTE RECOVERY PROCESS FACILITY AT THE PLUTONIUM FINSHING PLANT (PFP)  

SciTech Connect

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).

MINETTE, M.J.

2007-05-30

254

In-process inventory estimation in a reprocessing facility for near-real-time accounting  

SciTech Connect

An In-Process Inventory Technique (IPI) has been developed and tested at the Barnwell Nuclear Fuel Plant (BNFP) to provide frequent inventories without cost or instrusiveness to plant operability. A computerized measurement system makes available process measurements and process control analytical information. These data are processed to determine the process inventory. The calculation routines use routinely available process control measurements and sample results. The technique requires no shutdown, no special preparations, and no special measurements, or samples. With this technique, hourly inventory frequencies and material balance closures have been achieved during demonstration runs in the 1500 MTU/y at BNFP. Results show sensitivities of 2 to 5% of the normal process inventory are achievable during normal operations. Recent improvements in data handling routines indicate the technique can be sensitive during transient process conditions as well.

Ehinger, M.H.; Ellis J.E.; Plummer, K.E.

1981-01-01

255

75 FR 71733 - Requirements for Measurement Facilities Used for the Royalty Valuation of Processed Natural Gas  

Federal Register 2010, 2011, 2012, 2013, 2014

...This equipment includes any metering, sampling, or recording devices associated with...BOEMRE to inspect the measurement and sampling equipment of natural gas processing plants...of: Inspecting the measurement and sampling equipment of natural gas processing...

2010-11-24

256

Energy Efficiency Opportunities in Fresh Fruit and Vegetable Processing\\/Cold Storage Facilities  

Microsoft Academic Search

In this paper, the results from detailed plant-wide energy audits of seven fresh fruit and vegetable processing plants in California will be described and potential savings opportunities for large and small size processing plants will be addressed. The details of fresh fruit and vegetable processing from a viewpoint of energy consumption and operating cost will be discussed, and potential measures

Bryan Hackett; Sandra Chow; Ahmad R. Ganji

257

Comparative risk assessments for the production and interim storage of glass and ceramic waste forms: Defense waste processing facility  

NASA Astrophysics Data System (ADS)

The Defense Waste Processing Facility (DWPF) for immobilizing nuclear high level waste (HLW) is scheduled to be built. High level waste is produced when 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 risks associated with the manufacture and interim storage of these two forms in the DWPF are compared. 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.

Huang, J. C.; Wright, W. V.

1982-04-01

258

Aerobic biodegradation of sludge with high hydrocarbon content generated by a Mexican natural gas processing facility.  

PubMed

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

Roldán-Carrillo, T; Castorena-Cortés, G; Zapata-Peñasco, I; Reyes-Avila, J; Olguín-Lora, P

2012-03-01

259

Single-crystalline twinned ZnO nanoleaf structure via a facile hydrothermal process.  

PubMed

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

Qiu, Jijun; Lil, Xiaomin; Gao, Xiangdong; Gan, Xiaoyan; He, Weizhen; Kim, Hyung-Kook; Hwang, Yoon-Hwae

2011-03-01

260

RESEARCH AND DEVELOPMENT OF AN INTEGRAL SEPARATOR FOR A CENTRIFUGAL GAS PROCESSING FACILITY  

SciTech Connect

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.

LANCE HAYS

2007-02-27

261

Extrinsic and intrinsic complexities of the Los Alamos Plutonium Processing Facility  

SciTech Connect

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.

Bearse, R.C.; Longmire, V.L.; Roberts, N.J.

1985-01-01

262

A facile process for soak-and-peel delamination of CVD graphene from substrates using water  

NASA Astrophysics Data System (ADS)

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.

Gupta, Priti; Dongare, Pratiksha D.; Grover, Sameer; Dubey, Sudipta; Mamgain, Hitesh; Bhattacharya, Arnab; Deshmukh, Mandar M.

2014-01-01

263

Design of generic coal conversion facilities: Process release---Direct coal liquefaction  

SciTech Connect

The direct liquefaction portion of the PETC generic direct coal liquefaction process development unit (PDU) is being designed to provide maximum operating flexibility. The PDU design will permit catalytic and non-catalytic liquefaction concepts to be investigated at their proof-of-the-concept stages before any larger scale operations are attempted. The principal variations from concept to concept are reactor configurations and types. These include thermal reactor, ebullating bed reactor, slurry phase reactor and fixed bed reactor, as well as different types of catalyst. All of these operating modes are necessary to define and identify the optimum process conditions and configurations for determining improved economical liquefaction technology.

Not Available

1991-09-01

264

A facile process for soak-and-peel delamination of CVD graphene from substrates using water  

PubMed Central

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

Gupta, Priti; Dongare, Pratiksha D.; Grover, Sameer; Dubey, Sudipta; Mamgain, Hitesh; Bhattacharya, Arnab; Deshmukh, Mandar M.

2014-01-01

265

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 ...

266

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...

267

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...

268

SURVEY OF ENTEROBACTERIACEAE CONTAMINATION OF NEST RUN EGG CARTS IN SHELL EGG PROCESSING FACILITIES  

Technology Transfer Automated Retrieval System (TEKTRAN)

Enterobacteriaceae are frequent contaminants of food and several members of this bacterial family are human pathogens. High levels 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 ...

269

The Challenges of Preserving Historic Resources During the Deactivation and Decommissioning of Highly Contaminated Historically Significant Plutonium Process Facilities  

SciTech Connect

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)

Hopkins, A.; Minette, M.; Sorenson, D.; Heineman, R.; Gerber, M. [Fluor Hanford, Inc., PO Box 1000 Richland WA 99352 (United States); Charboneau, S. [US Department of Energy PO Box 550, Richland WA 99352 (United States); Bond, F. [Washington State Department of Ecology, WDOE 3100 Port of Benton Blvd., Richland WA, 99354 (United States)

2006-07-01

270

CHALLENGES OF PRESERVING HISTORIC RESOURCES DURING THE D & D OF HIGHLY CONTAMINATED HISTORICALLY SIGNIFICANT PLUTONIUM PROCESS FACILITIES  

SciTech Connect

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.

HOPKINS, A.M.

2006-03-17

271

Microbial quality of condensation in fresh and ready-to-eat processing facilities  

Microsoft Academic Search

The objective was to determine the microbial risks associated with condensation in harvest, fabrication, and ready-to-eat (RTE) meat processing environments. A total of 2281 samples were collected before and during operation from areas of visible condensation, overhead pipes, and dripping pans in three plants each season during a one-year period. Significant interactions between season and plant type were observed for

M. M. Brashears; A. J. Garmyn; J. C. Brooks; D. Harris; G. Loneragan; A. Echeverry; T. E. Jackson; J. M. Mehaffey; M. F. Miller

272

Risk-Based Decision Process for Accelerated Closure of a Nuclear Weapons Facility  

SciTech Connect

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.

Butler, L.; Norland, R. L.; DiSalvo, R.; Anderson, M.

2003-02-25

273

A facile processing way of silica needle arrays with tunable orientation by tube arrays fabrication and etching method  

SciTech Connect

A simple method to fabricate silica micro/nano-needle arrays (SNAs) is presented based on tube-etching mechanism. Using silica fibers as templates, highly aligned and free-standing needle arrays are created over large area by simple processes of polymer infiltration, cutting, chemical etching and polymer removal. Their sizes and orientations can be arbitrarily and precisely tuned by simply selecting fiber sizes and the cutting directions, respectively. This technique enables the needle arrays with special morphology to be fabricated in a greatly facile way, thereby offers them the potentials in various applications, such as optic, energy harvesting, sensors, etc. As a demonstration, the super hydrophobic property of PDMS treated SNAs is examined. - Graphical abstract: Silica needle arrays are fabricated by tube arrays fabrication and etching method. They show super hydrophobic property after being treated with PDMS.

Zhu Mingwei; Gao Haigen; Li Hongwei; Xu Jiao [National Laboratory of Solid State Microstructures and Department of Materials Science and Engineering, Nanjing University, Nanjing 210093 (China); Chen Yanfeng, E-mail: yfchen@nju.edu.c [National Laboratory of Solid State Microstructures and Department of Materials Science and Engineering, Nanjing University, Nanjing 210093 (China)

2010-03-15

274

Reevaluation of Vitrified High-Level Waste Form Criteria for Potential Cost Savings at the Defense Waste Processing Facility - 13598  

SciTech Connect

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)

Ray, J.W. [Savannah River Remediation (United States)] [Savannah River Remediation (United States); Marra, S.L.; Herman, C.C. [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)] [Savannah River National Laboratory, Savannah River Site, Aiken, SC 29808 (United States)

2013-07-01

275

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

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…

Mason, George J.

276

Supercritical water oxidation technology for DWPF. [Defense Waste Processing Facility (DWPF)  

SciTech Connect

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.

Carter, J.T.; Gentilucci, J.A.

1992-02-07

277

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

Code of Federal Regulations, 2010 CFR

...LNG terminal facilities and other natural gas facilities prior to filing of applications...DEPARTMENT OF ENERGY REGULATIONS UNDER NATURAL GAS ACT APPLICATIONS FOR CERTIFICATES OF...ABANDONMENT UNDER SECTION 7 OF THE NATURAL GAS ACT Applications for Certificates...

2010-04-01

278

Spacelab data processing facility (SLDPF) quality assurance (QA)/data accounting (DA) expert systems - Transition from prototypes to operational systems  

NASA Technical Reports Server (NTRS)

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.

Basile, Lisa

1988-01-01

279

Spacelab data processing facility (SLDPF) Quality Assurance (QA)/Data Accounting (DA) expert systems: Transition from prototypes to operational systems  

NASA Technical Reports Server (NTRS)

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.

Basile, Lisa

1988-01-01

280

W-007H B Plant Process Condensate Treatment Facility. Revision 3  

SciTech Connect

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.

Rippy, G.L.

1995-01-20

281

Guide to research facilities  

SciTech Connect

This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

Not Available

1993-06-01

282

HANFORD CONTAINERIZED CAST STONE FACILITY TASK 1 PROCESS TESTING & DEVELOPMENT FINAL TEST REPORT  

SciTech Connect

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.

LOCKREM, L L

2005-07-13

283

COMPARATIVE MEDICINE LABORATORY ANIMAL FACILITIES  

E-print Network

3.E.2 COMPARATIVE MEDICINE LABORATORY ANIMAL FACILITIES STANDARD OPERATING PROCEDURES for REGULATED bags, autoclaved, and processed as RMW through Stericycle. Laboratory Animal Facilities Incinerator Use

Krovi, Venkat

284

QUALIFICATION OF A RADIOACTIVE HIGH ALUMINUM GLASS FOR PROCESSINGIN THE DEFENSE WASTE PROCESSING FACILITY AT THE SAVANNAH RIVER SITE  

SciTech Connect

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 borosilicate glass for approximately eleven years. Currently the DWPF is immobilizing HLW sludge in Sludge Batch 4 (SB4). Each sludge batch is nominally two million liters of HLW and produces nominally five hundred stainless steel canisters 0.6 meters in diameter and 3 meters tall filled with the borosilicate glass. In SB4 and earlier sludge batches, the Al concentration has always been rather low, (less than 9.5 weight percent based on total dried solids). It is expected that in the future the Al concentrations will increase due to the changing composition of the HLW. Higher Al concentrations could introduce problems because of its known effect on the viscosity of glass melts and increase the possibility of the precipitation of nepheline in the final glass and decrease its durability. In 2006 Savannah River National Laboratory (SRNL) used DWPF processes to immobilize a radioactive HLW slurry containing 14 weight percent Al to ensure that this waste is viable for future DWPF processing. This paper presents results of the characterization of the high Al glass prepared in that demonstration. At SRNL, a sample of the processed high Al HLW slurry was mixed with an appropriate glass frit as performed in the DWPF to make a waste glass containing nominally 30% waste oxides. The glass was prepared by melting the frit and waste remotely at 1150 C. The glass was then characterized by: (1) determining the chemical composition of the glass including the concentrations of several actinide and U-235 fission products; (2) calculating the oxide waste loading of the glass based on the chemical composition and comparing it to that of the target; (3) determining if the glass composition met the DWPF processing constraints such as glass melt viscosity and liquidus temperature along with a waste form affecting constraint that prevents the precipitation of nepheline (NaAlSiO{sub 4}) crystals in the glass melt; (4) measuring the durability of the glass using the ASTM Standard Product Consistency Test (PCT) leach test to determine if the durability of the glass based on B, Li, and Na releases met the requirements for acceptance in a US geologic repository; (5) measuring the leachability of several radionuclides using the ASTM Standard PCT leach test and comparing them to the B, Li, and Na releases; and (6) examining the glass by scanning electron microscopy and energy dispersive X-ray spectrometry to determine if any crystals had formed in the glass melt. Results indicate that the high Al glass met all the requirements for processing and product quality in the DWPF.

Bibler, N; John Pareizs, J; Tommy Edwards,T; Charles02 Coleman, C; Charles Crawford, C

2008-01-29

285

Molecular and immunological approaches in quantifying the air-borne food allergen tropomyosin in crab processing facilities.  

PubMed

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

Kamath, Sandip D; Thomassen, Marte R; Saptarshi, Shruti R; Nguyen, Hong M X; Aasmoe, Lisbeth; Bang, Berit E; Lopata, Andreas L

2014-09-01

286

[Evaluating the activity of the Italian Mental Health Services inpatient and residential facilities: the PRISM (Process Indicator System for Mental health) indicators].  

PubMed

This article describes the activities of a project aimed at developing a system of process and process/outcome indicators suitable to monitor over time the quality of psychiatric care of Italian inpatient and residential psychiatric facilities. This system, named PRISM (Process Indicator System for Mental health), was developed by means of a standardized evaluation made by a panel of experts and a consecutive pilot study in 17 inpatient and 13 residential psychiatric facilities. Materials and methods. A total of 28 indicators were selected from a set of 251 candidate indicators developed by the most relevant and qualified Italian and international authorities. These indicators are derived by data from medical records and information about characteristics of facilities, and they cover processes of care, operational equipment of facilities, staff training and working, relationships with external agencies, and sentinel events. Results. The procedure followed for the development of the indicator system was reliable and innovative. The data collected from the pilot study suggested a favourable benefit-cost ratio between the workload associated with regular use of the indicators into the context of daily clinical activities and the advantages related to the information gathered through regular use of the indicators. Conclusions. The PRISM system provides additional information about the healthcare processes with respect to the information gathered via routine information systems, and it might prove useful for both continuous quality improvement programs and health services research. PMID:25668628

Picardi, Angelo; Tarolla, Emanuele; de Girolamo, Giovanni; Gigantesco, Antonella; Neri, Giovanni; Rossi, Elisabetta; Biondi, Massimo

2014-01-01

287

Dismantling of Highly Contaminated Process Installations of the German Reprocessing Facility (WAK) - Status of New Remote Handling Technology - 13287  

SciTech Connect

Decommissioning and dismantling of the former German Pilot Reprocessing Plant Karlsruhe (WAK) including the Vitrification Facility (VEK) is being executed in different Project steps related to the reprocessing, HLLW storage and vitrification complexes /1/. While inside the reprocessing building the total inventory of process equipment has already been dismantled and disposed of, the HLLW storage and vitrification complex has been placed out of operation since vitrification and tank rinsing procedures where finalized in year 2010. This paper describes the progress made in dismantling of the shielded boxes of the highly contaminated laboratory as a precondition to get access to the hot cells of the HLLW storage. The major challenges of the dismantling of this laboratory were the high dose rates up to 700 mSv/h and the locking technology for the removal of the hot cell installations. In parallel extensive prototype testing of different carrier systems and power manipulators to be applied to dismantle the HLLW-tanks and other hot cell equipment is ongoing. First experiences with the new manipulator carrier system and a new master slave manipulator with force reflection will be reported. (authors)

Dux, Joachim; Friedrich, Daniel; Lutz, Werner; Ripholz, Martina [WAK Rueckbau- und Entsorgungs- GmbH, P.O. Box 12 63, 76339 Eggenstein-Leopoldshafen (Germany)] [WAK Rueckbau- und Entsorgungs- GmbH, P.O. Box 12 63, 76339 Eggenstein-Leopoldshafen (Germany)

2013-07-01

288

Proposed Use of a Constructed Wetland for the Treatment of Metals in the S-04 Outfall of the Defense Waste Processing Facility at the Savannah River Site  

SciTech Connect

The DWPF is part of an integrated waste treatment system at the SRS to treat wastes containing radioactive contaminants. In the early 1980s the DOE recognized that there would be significant safety and cost advantages associated with immobilizing the radioactive waste in a stable solid form. The Defense Waste Processing Facility was designed and constructed to accomplish this task.

Glover, T.

1999-11-23

289

Implementing waste minimization at an active plutonium processing facility: Successes and progress at technical area (TA) -55 of the Los Alamos National Laboratory  

Microsoft Academic Search

The Los Alamos National Laboratory has ongoing national security missions that necessitate increased plutonium processing. The bulk of this activity occurs at Technical Area -55 (TA-55), the nations only operable plutonium facility. TA-55 has developed and demonstrated a number of technologies that significantly minimize waste generation in plutonium processing (supercritical COâ, Mg(OH)â precipitation, supercritical HâO oxidation, WAND), disposition of excess

J. J. Balkey; M. A. Robinson; J. Boak

1997-01-01

290

Screening study for waste biomass to ethanol production facility using the amoco process in New York State. Appendices to the final report  

SciTech Connect

In 1994, the New York City Department of Sanitation (NYCDOS) intended to solicit proposals for a City-based recycling facility using mixed waste paper. Because Amoco was interested in manufacturing ethanol from biomass, it proposed to do a siting screen in NYC, after which the study was expanded to include upstate locations as well. The objective was to identify and evaluate two sites in New York City and three sites in other New York State urban centers that would be appropriate for construction and long-term operation of a financially attractive and environmentally sound waste biomass-to-ethanol production facility using Amoco`s biomass conversion technology (the `Amoco Process`).

Gastwirth, H.

1995-08-01

291

Defense Waste Processing Facility: Report of task force on options to mitigate the effect of nitrite on DWPF operations. Savannah River Site 200-S Area  

SciTech Connect

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.

Randall, D. [ed.; Marek, J.C.

1992-03-01

292

Intensive archeological survey of the proposed Saltcrete area of the Defense Waste Processing Facility, Savannah River Plant, Aiken County, South Carolina. Research manuscript series 172  

SciTech Connect

An intensive archeological survey of the proposed Saltcrete (200-Z) area of the Defense Waste Processing Facility on the Savannah River Plant, Aiken County, South Carolina was conducted. The purpose was to locate, describe and assess the archeological resources within the proposed construction area and to provide the Department of Energy with the recommendations as to the significance of the resources. This report presents a summary of the background, methods, results and recommendations resulting from the Saltcrete area intensive survey.

Brooks, R.D.

1981-06-01

293

Two-stage coal liquefaction process materials from the Wilsonville Facility operated in the nonintegrated and integrated modes: chemical analyses and biological testing  

SciTech Connect

This document reports the results from chemical analyses and biological testing of process materials sampled during operation of the Wilsonville Advanced Coal Liquefaction Research and Development Facility (Wilsonville, Alabama) in both the noncoupled or nonintegrated (NTSL Run 241) and coupled or integrated (ITSL Run 242) two-stage liquefaction operating modes. Mutagenicity and carcinogenicity assays were conducted in conjunction with chromatographic and mass spectrometric analyses to provide detailed, comparative chemical and biological assessments of several NTSL and ITSL process materials. In general, the NTSL process materials were biologically more active and chemically more refractory than analogous ITSL process materials. To provide perspective, the NTSL and ITSL results are compared with those from similar testing and analyses of other direct coal liquefaction materials from the solvent refined coal (SRC) I, SRC II and EDS processes. Comparisons are also made between two-stage coal liquefaction materials from the Wilsonville pilot plant and the C.E. Lummus PDU-ITSL Facility in an effort to assess scale-up effects in these two similar processes. 36 references, 26 figures, 37 tables.

Later, D.W.

1985-01-01

294

An overview of the waste handling and packaging plant, a major processing facility for remote-handled transuranic waste  

Microsoft Academic Search

The Waste Handling and Packaging Plant (WHPP) is a FY 1991 line item project proposed for construction at the Oak Ridge National Laboratory (ORNL). The purpose of the facility is to receive, package, certify and ship remote-handled (RH) and special case (SC) transuranic (TRU) waste to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The scope of the

D. W. Turner; R. C. Stewart; S. P. du Mont

1988-01-01

295

Advocating for a Parent with Dementia in a Long-term Care FacilityThe Process Experienced by Daughters  

Microsoft Academic Search

Daughter caregivers of elders with dementia become their parents' advocates over time. This role takes on even greater importance when one or both parents are placed in a long-term care facility. This article presents the results of a qualitative study aimed at explaining how this advocacy role evolves following institutionalization. In-depth interviews were conducted with daughters (N = 14) of

Alain Legault; Francine Ducharme

2009-01-01

296

40 CFR 80.513 - What provisions apply to transmix processing facilities and pipelines that produce diesel fuel...  

Code of Federal Regulations, 2014 CFR

...facility will segregate any 500 ppm LM diesel fuel produced subject to the standards...ppm LM will also have access to 15 ppm diesel fuel for use in those engines that require the use of 15 ppm diesel fuel. The compliance plan must...

2014-07-01

297

40 CFR 80.513 - What provisions apply to transmix processing facilities and pipelines that produce diesel fuel...  

Code of Federal Regulations, 2013 CFR

...facility will segregate any 500 ppm LM diesel fuel produced subject to the standards...ppm LM will also have access to 15 ppm diesel fuel for use in those engines that require the use of 15 ppm diesel fuel. The compliance plan must...

2013-07-01

298

Handbook on Planning School Facilities.  

ERIC Educational Resources Information Center

This guide details the development of a 10-year Comprehensive Educational Facilities Plan (CEFP), along with its components and governing regulations. Chapters examine the CEFP process and requirements in the following areas: educational facilities planning; site design; common facilities necessary for school operation; facilities for primary…

Clutter, Wayne, Comp.; Elswick, Bill, Comp.

299

Proof of concept simulations of the Multi-Isotope Process monitor: An online, nondestructive, near-real-time safeguards monitor for nuclear fuel reprocessing facilities  

NASA Astrophysics Data System (ADS)

The International Atomic Energy Agency will require the development of advanced technologies to effectively safeguard nuclear material at increasingly large-scale nuclear recycling facilities. Ideally, the envisioned technologies would be capable of nondestructive, near-real-time, autonomous process monitoring. This paper describes recent results from model simulations designed to test the Multi-Isotope Process (MIP) monitor, a novel addition to a safeguards system for reprocessing facilities. The MIP monitor combines the detection of intrinsic gamma ray signatures emitted from process solutions with multivariate analysis to detect off-normal conditions in process streams nondestructively and in near-real-time. Three computer models including ORIGEN-ARP, AMUSE, and SYNTH were used in series to predict spent nuclear fuel composition, estimate element partitioning during separation, and simulate spectra from product and raffinate streams using a variety of gamma detectors, respectively. Simulations were generated for fuel with various irradiation histories and under a variety of plant operating conditions. Principal component analysis was applied to the simulated gamma spectra to investigate pattern variations as a function of acid concentration, burnup, and cooling time. Hierarchical cluster analysis and partial least squares (PLS) were also used in the analysis. The MIP monitor was found to be sensitive to induced variations of several operating parameters including distinguishing ±2.5% variation from normal process acid concentrations. The ability of PLS to predict burnup levels from simulated spectra was also demonstrated to be within 3.5% of measured values.

Orton, Christopher R.; Fraga, Carlos G.; Christensen, Richard N.; Schwantes, Jon M.

2011-02-01

300

Facilities maintenance handbook  

NASA Technical Reports Server (NTRS)

This handbook is a guide for facilities maintenance managers. Its objective is to set minimum facilities maintenance standards. It also provides recommendations on how to meet the standards to ensure that NASA maintains its facilities in a manner that protects and preserves its investment in the facilities in a cost-effective manner while safely and efficiently performing its mission. This handbook implements NMI 8831.1, which states NASA facilities maintenance policy and assigns organizational responsibilities for the management of facilities maintenance activities on all properties under NASA jurisdiction. It is a reference for facilities maintenance managers, not a step-by-step procedural manual. Because of the differences in NASA Field Installation organizations, this handbook does not assume or recommend a typical facilities maintenance organization. Instead, it uses a systems approach to describe the functions that should be included in any facilities maintenance management system, regardless of its organizational structure. For documents referenced in the handbook, the most recent version of the documents is applicable. This handbook is divided into three parts: Part 1 specifies common definitions and facilities maintenance requirements and amplifies the policy requirements contained in NMI 8831. 1; Part 2 provides guidance on how to meet the requirements of Part 1, containing recommendations only; Part 3 contains general facilities maintenance information. One objective of this handbook is to fix commonality of facilities maintenance definitions among the Centers. This will permit the application of uniform measures of facilities conditions, of the relationship between current replacement value and maintenance resources required, and of the backlog of deferred facilities maintenance. The utilization of facilities maintenance system functions will allow the Centers to quantitatively define maintenance objectives in common terms, prepare work plans, and develop management information in order to statistically identify and analyze variances from those plans. It will also add credibility to the NASA facilities maintenance budgeting process. The key to a successful maintenance program is the understanding and support of the senior Center managers.

1991-01-01

301

New Instrumental Facilities to study High Energy Processes in the Sun, Interplanetary Space and their Effects in the Earth Atmosphere  

NASA Astrophysics Data System (ADS)

We present a new instrumental facility to study the physical mechanisms of high-energy releases taking place in solar quiet and explosive active regions, and their signatures in the Earth's atmosphere. These facilities will be installed in the CASLEO (2550 m asl) observatory, and complement solar flare diagnostic obtained there at millimeter waves (45 and 90 GHZ), submillimeter waves (212 and 405 GHz), IR (30 THz), as well as X-ray radiation imprints in the ionosphere (VLF subionospheric propagation), and of energetic charged particles in Earth's atmosphere (Cosmic Ray CARPET sensor).Specifically, we propose to complement these existing instrumental facilities with a new detector of solar and atmospheric neutrons, a gamma-ray scintillation device, and ELF/VLF wave sensors. The main objectives are: (i) to better characterize the high-frequency radio and high-energy photon flare spectra, in order to provide new clues on the emission mechanism resulting in submillimeter and THz radiation which are still unexplained; (ii) to provide a continuous monitoring of solar energetic phenomena and investigate if they are more frequent than what we do observe nowadays; (iii) to investigate the causal relationship between atmospheric phenomena as lightning occurrence, high-energy photon and neutron production, Terrestrial Gamma-ray Flashes, and cosmic ray fluxes.

Raulin, Jean-Pierre; Makhmutov, Vladimir

302

Electro-Mechanical Manipulator for Use in the Remote Equipment Decontamination Cell at the Defense Waste Processing Facility, Savannah River Site - 12454  

SciTech Connect

One of the legacies of the cold war is millions of liters of radioactive waste. One of the locations where this waste is stored is at the Savannah River Site (SRS) in South Carolina. A major effort to clean up this waste is on-going at the defense waste processing facility (DWPF) at SRS. A piece of this effort is decontamination of the equipment used in the DWPF to process the waste. The remote equipment decontamination cell (REDC) in the DWPF uses electro-mechanical manipulators (EMM) arms manufactured and supplied by PaR Systems to decontaminate DWPF process equipment. The decontamination fluid creates a highly corrosive environment. After 25 years of operational use the original EMM arms are aging and need replacement. To support continued operation of the DWPF, two direct replacement EMM arms were delivered to the REDC in the summer of 2011. (authors)

Lambrecht, Bill; Dixon, Joe [Par Systems, Shoreview, Minnesota, 55126 (United States); Neuville, John R. [Savannah River Remediation, Savannah River Site, Aiken, South Carolina, 29808 (United States)

2012-07-01

303

Implementing waste minimization at an active plutonium processing facility: Successes and progress at technical area (TA) -55 of the Los Alamos National Laboratory  

SciTech Connect

The Los Alamos National Laboratory has ongoing national security missions that necessitate increased plutonium processing. The bulk of this activity occurs at Technical Area -55 (TA-55), the nations only operable plutonium facility. TA-55 has developed and demonstrated a number of technologies that significantly minimize waste generation in plutonium processing (supercritical CO{sub 2}, Mg(OH){sub 2} precipitation, supercritical H{sub 2}O oxidation, WAND), disposition of excess fissile materials (hydride-dehydride, electrolytic decontamination), disposition of historical waste inventories (salt distillation), and Decontamination & Decommissioning (D&D) of closed nuclear facilities (electrolytic decontamination). Furthermore, TA-55 is in the process of developing additional waste minimization technologies (molten salt oxidation, nitric acid recycle, americium extraction) that will significantly reduce ongoing waste generation rates and allow volume reduction of existing waste streams. Cost savings from reduction in waste volumes to be managed and disposed far exceed development and deployment costs in every case. Waste minimization is also important because it reduces occupational exposure to ionizing radiation, risks of transportation accidents, and transfer of burdens from current nuclear operations to future generations.

Balkey, J.J.; Robinson, M.A.; Boak, J.

1997-12-01

304

Associations between oil- and gas-well sites, processing facilities, flaring, and beef cattle reproduction and calf mortality in western Canada.  

PubMed

From the fall of 1992 through calving 1996, detailed cow breeding outcome records were maintained actively for seven large cow-calf herds in western Canada. The numbers of mature females in the study for the breeding seasons beginning in 1992, 1993, 1994, and 1995 were 1122, 1177, 1251, and 1236, respectively. Outcomes included pregnancy status, calving interval, and the occurrence of twins, abortions, stillbirths, and neonatal mortality. Information also was collected on other risk factors known to influence beef-herd health and productivity. Detailed maps of active and inactive oil and natural-gas sites, batteries, compressor stations and processing plants were verified. Records of flaring activity at each facility were obtained from the government regulatory agency. Each flaring site then was classified as sour or sweet based on the presence or absence of hydrogen sulfide in the flared gas. A detailed inventory was prepared itemizing the type and number of facilities within 1.6 km (1 mile) of the center of each quarter section used for pasture. The total volume of gas flared within 1.6 km of the center of each pasture was determined for each month of the study. Appropriate risk periods where specified for each outcome and a cumulative exposure calculated for each breeding female (using detailed individual-animal records of cow movements between pastures and herd-management groups). Generalized estimating equations were used to evaluate the association between exposure and outcome and to adjust for potential confounders and clustering of binomial outcomes within herd. Increased risk of non-pregnancy was sometimes associated with exposure to one or more of the following facility types: sour-gas flaring battery facilities, all battery-flaring sites, active gas wells, and larger field facilities. The associations were not, however, consistent among years or even among risk periods for the same year. Facility proximity and flaring were not associated with increased abortion risk. Volume of flared sour gas from battery sites was associated with increased risk of stillbirth. Finally, sour-gas flaring was associated with increased calf-mortality risk for the 1992-1993 calf crop. Several examples of associations between exposure and increased productivity also were found (most of which involved either oil wells or all well sites). PMID:11448492

Waldner, C L; Ribble, C S; Janzen, E D; Campbell, J R

2001-07-19

305

Rheology Of MonoSodium Titanate (MST) And Modified Mst (mMST) Mixtures Relevant To The Salt Waste Processing Facility  

SciTech Connect

The Savannah River National Laboratory performed measurements of the rheology of suspensions and settled layers of treated material applicable to the Savannah River Site Salt Waste Processing Facility. Suspended solids mixtures included monosodium titanate (MST) or modified MST (mMST) at various solid concentrations and soluble ion concentrations with and without the inclusion of kaolin clay or simulated sludge. Layers of settled solids were MST/sludge or mMST/sludge mixtures, either with or without sorbed strontium, over a range of initial solids concentrations, soluble ion concentrations, and settling times.

Koopman, D. C.; Martino, C. J.; Shehee, T. C.; Poirier, M. R.

2013-07-31

306

Proof of Concept Experiments of the Multi-Isotope Process Monitor: An Online, Nondestructive, Near Real-Time Monitor for Spent Nuclear Fuel Reprocessing Facilities  

SciTech Connect

Operators, national regulatory agencies and the IAEA will require the development of advanced technologies to efficiently control and safeguard nuclear material at increasingly large-scale nuclear recycling facilities. Ideally, the envisioned technologies would be capable of non-destructive, near-real-time (NRT), autonomous process monitoring. This paper describes results from proof-of-principle experiments designed to test the Multi-Isotope Process (MIP) Monitor, a novel approach to safeguarding reprocessing facilities. The MIP Monitor combines the detection of intrinsic gamma ray signatures emitted from process solutions with multivariate analysis to detect off-normal conditions in process streams nondestructively and in NRT. Commercial spent nuclear fuel of various irradiation histories was dissolved and separated using a PUREX-based batch solvent extraction. Extractions were performed at various nitric acid concentrations to mimic both normal and off-normal industrial plant operating conditions. Principal Component Analysis (PCA) was applied to the simulated gamma spectra to investigate pattern variations as a function of acid concentration, burnup and cooling time. Partial Least Squares (PLS) regression was applied to attempt to quantify both the acid concentration and burnup of the dissolved spent fuel during the initial separation stage of recycle. The MIP Monitor demonstrated sensitivity to induced variations of acid concentration, including the distinction of {+-} 1.3 M variation from normal process conditions by way of PCA. Acid concentration was predicted using measurements from the organic extract and PLS resulting in predictions with <0.7 M relative error. Quantification of burnup levels from dissolved fuel spectra using PLS was demonstrated to be within 2.5% of previously measured values.

Orton, Christopher R.; Fraga, Carlos G.; Christensen, Richard; Schwantes, Jon M.

2012-04-21

307

Proof of concept experiments of the multi-isotope process monitor: An online, nondestructive, near real-time monitor for spent nuclear fuel reprocessing facilities  

NASA Astrophysics Data System (ADS)

Operators, national regulatory agencies and the IAEA will require the development of advanced technologies to efficiently control and safeguard nuclear material at increasingly large-scale nuclear recycling facilities. Ideally, the envisioned technologies would be capable of non-destructive, near real-time (NRT), autonomous process monitoring. This paper describes results from proof-of-principle experiments designed to test the multi-isotope process (MIP) monitor, a novel approach to monitoring and safeguarding reprocessing facilities. The MIP Monitor combines the detection of intrinsic gamma ray signatures emitted from process solutions with multivariate analysis to detect off-normal conditions in process streams nondestructively and in NRT. Commercial spent nuclear fuel of various irradiation histories was dissolved and separated using a PUREX-based batch solvent extraction. Extractions were performed at various nitric acid concentrations to mimic both normal and off-normal industrial plant operating conditions. Principal component analysis (PCA) was applied to the simulated gamma spectra to investigate pattern variations as a function of acid concentration, burnup and cooling time. Partial least squares (PLS) regression was applied to attempt to quantify both the acid concentration and burnup of the dissolved spent fuel during the initial separation stage of recycle. The MIP Monitor demonstrated sensitivity to induced variations of acid concentration, including the distinction of ±1.3 M variation from normal process conditions by way of PCA. Acid concentration was predicted using measurements from the organic extract and PLS resulting in predictions with <0.7 M relative error. Quantification of burnup levels from dissolved fuel spectra using PLS was demonstrated to be within 2.5% of previously measured values.

Orton, Christopher R.; Fraga, Carlos G.; Christensen, Richard N.; Schwantes, Jon M.

2012-04-01

308

300 Area process sewer piping upgrade and 300 Area treated effluent disposal facility discharge to the City of Richland Sewage System, Hanford Site, Richland, Washington  

SciTech Connect

The U.S. Department of Energy (DOE) is proposing to upgrade the existing 300 Area Process Sewer System by constructing and operating a new process sewer collection system that would discharge to the 300 Area Treated Effluent Disposal Facility. The DOE is also considering the construction of a tie-line from the TEDF to the 300 Area Sanitary Sewer for discharging the process wastewater to the City of Richland Sewage System. The proposed action is needed because the integrity of the old piping in the existing 300 Area Process Sewer System is questionable and effluents might be entering the soil column from leaking pipes. In addition, the DOE has identified a need to reduce anticipated operating costs at the new TEDF. The 300 Area Process Sewer Piping Upgrade (Project L-070) is estimated to cost approximately $9.9 million. The proposed work would involve the construction and operation of a new process sewer collection system. The new system would discharge the effluents to a collection sump and lift station for the TEDF. The TEDF is designed to treat and discharge the process effluent to the Columbia River. The process waste liquid effluent is currently well below the DOE requirements for radiological secondary containment and is not considered a RCRA hazardous waste or a State of Washington Hazardous Waste Management Act dangerous waste. A National Pollutant Discharge Elimination, System (NPDES) permit has been obtained from the U.S. Environmental Protection Agency for discharge to the Columbia River. The proposed action would upgrade the existing 300 Area Process Sewer System by the construction and operation of a new combined gravity, vacuum, and pressurized process sewer collection system consisting of vacuum collection sumps, pressure pump stations, and buried polyvinyl chloride or similar pipe. Two buildings would also be built to house a main collection station and a satellite collection station.

NONE

1995-05-01

309

Regional efficiency in the organization of agricultural processing facilities: an application to oilseeds industry in the Sudan  

SciTech Connect

There has been an increase in the production of oilseeds in the Sudan during the last few years following a policy of diversifying production. The increase in supply has also been accompanied by an export policy that is directed towards exporting processed products rather than seeds. Assuming that the present trend of increased production and exports of processed oilseeds will continue, and knowing that the present marketing services of oilseeds in the country are rather inefficient, economic information is needed to give more precise direction to the expected changes in marketing services. The present research used an economic framework to analyze the costs of transportation, storage, and processing of oilseeds in the Sudan. The objectives of the study were to describe the present marketing system of oilseeds and evaluate the performance of the institutions involved, to determine the optimum location, number and size of processing plants for 1979/80 and 1989/90, and to analyze the impact of changes in selected variables in the model on plant location, marketing costs and product flow. Results of the analysis showed that increasing the present processing capacity of 50 to 70% as expected did not increase the per unit cost of processing. The 70% processing capacity was considered the basic solution. Optimum plant location was obtained by removing the constraints on processing capacity.

Babiker, B.I.

1982-01-01

310

A Guide for Developing Standard Operating Job Procedures for the Primary Sedimentation Process Wastewater Treatment Facility. SOJP No. 4.  

ERIC Educational Resources Information Center

This guide describes standard operating job procedures for the primary sedimentation process of wastewater treatment plants. The primary sedimentation process involves removing settleable and suspended solids, in part, from wastewater by gravitational forces, and scum and other floatable solids from wastewater by mechanical means. Step-by-step…

Charles County Community Coll., La Plata, MD.

311

Reducing Plug and Process Loads for a Large Scale, Low Energy Office Building: NREL's Research Support Facility; Preprint  

SciTech Connect

This paper documents the design and operational plug and process load energy efficiency measures needed to allow a large scale office building to reach ultra high efficiency building goals. The appendices of this document contain a wealth of documentation pertaining to plug and process load design in the RSF, including a list of equipment was selected for use.

Lobato, C.; Pless, S.; Sheppy, M.; Torcellini, P.

2011-02-01

312

A Guide for Developing Standard Operating Job Procedures for the Tertiary Multimedia Filtration Process Wastewater Treatment Facility. SOJP No. 7.  

ERIC Educational Resources Information Center

This guide describes the standard operating job procedures for the tertiary multimedia filtration process of wastewater treatment plants. The major objective of the filtration process is the removal of suspended solids from the reclaimed wastewater. The guide gives step-by-step instructions for pre-start up, start-up, continuous operation, and…

Petrasek, Al, Jr.

313

The multi-isotope process monitor: Non-destructive, near-real-time nuclear safeguards monitoring at a reprocessing facility  

NASA Astrophysics Data System (ADS)

The IAEA will require advanced technologies to effectively safeguard nuclear material at envisioned large scale nuclear reprocessing plants. This dissertation describes results from simulations and experiments designed to test the Multi-Isotope Process (MIP) Monitor, a novel safeguards approach for process monitoring in reprocessing plants. The MIP Monitor combines the detection of intrinsic gamma ray signatures emitted from process solutions with multivariate analysis to detect off-normal conditions in process streams, nondestructively and in near-real time (NRT). Three different models were used to predict spent nuclear fuel composition, estimate chemical distribution during separation, and simulate spectra from a variety of gamma detectors in product and raffinate streams for processed fuel. This was done for fuel with various irradiation histories and under a variety of plant operating conditions. Experiments were performed to validate the results from the model. Three segments of commercial spent nuclear fuel with variations in burnup and cooling time were dissolved and subjected to a batch PUREX method to separate the uranium and plutonium from fission and activation products. Gamma spectra were recorded by high purity germanium (HPGe) and cadmium zinc telluride (CZT) detectors. Hierarchal Cluster Analysis (HCA) and Principal Component Analysis (PCA) were applied to spectra from both model and experiment to investigate spectral variations as a function of acid concentration, burnup level and cooling time. Partial Least Squares was utilized to extract quantitative information about process variables, such as acid concentration or burnup. The MIP Monitor was found to be sensitive to the induced variations of the process and was capable of extracting quantitative process information from the analyzed spectra.

Orton, Christopher Robert

314

Single-solvent facile synthesis of monodisperse sub-20 nm polymeric nanoparticles via self-assembly process.  

PubMed

Nanoparticles with sizes less than 20 nm present unique properties and potential applications, whereas encounter great synthetic challenges. In this work, we demonstrate a single-solvent method for facile synthesis of uniform polymeric nanoparticles in the regime of 1-20 nm. Short-chain block copolymers, such as polystyrene-b-poly(1,2-butadiene) (PS-b-PB) and polystyrene-b-poly(4-vinylpyridine) (PS-b-P4VP), directly self-assemble into micelles or reverse micelles in specific selective solvents. The following in situ crosslinking of the micelle core or corona produces a variety of extremely tiny organic nanoparticles. Representatively, sub-10nm nanoparticles with either elastic core or corona are obtained from PS-b-PB block copolymers and sub-20 nm nanoparticles with highly stretched core and loosely packed corona are prepared from PS-b-P4VP block copolymers. These nanoparticles could show priority in the preparation of novel nanocomposites or in modeling the nanocytotoxicities. PMID:24370419

Zhang, Yong; Wang, Qian

2014-02-15

315

Successful Demolition of Historic Cape Canaveral Air Force Station Launch Facilities: Managing the Process to Maximize Recycle Value to Fund Demolition  

SciTech Connect

This paper will present the history of the Atlas 36 and Titan 40 Space Launch Complexes (SLC), the facility assessment process, demolition planning, recycle methodology, and actual facility demolition that resulted in a 40% reduction in baseline cost. These two SLC launched hundreds of payloads into space from Cape Canaveral Air Force Station (AFS), Florida. The Atlas-Centaur family of rockets could lift small- to medium-size satellites designed for communications, weather, or military use, placing them with near pinpoint accuracy into their intended orbits. The larger Titan family was relied upon for heavier lifting needs, including launching military satellites as well as interplanetary probes. But despite their efficiency and cost-effectiveness, the Titan rockets, as well as earlier generation Atlas models, were retired in 2005. Concerns about potential environmental health hazards from PCBs and lead-based paint chipping off the facilities also contributed to the Air Force's decision in 2005 to dismantle and demolish the Atlas and Titan missile-launching systems. Lockheed Martin secured the complex following the final launch, removed equipment and turned over the site to the Air Force for decommissioning and demolition (D and D). AMEC was retained by the Air Force to perform demolition planning and facility D and D in 2004. AMEC began with a review of historical information, interviews with past operations personnel, and 100% facility assessment of over 100 structures. There where numerous support buildings that due to their age contained asbestos containing material (ACM), PCB-impacted material, and universal material that had to be identified and removed prior to demolition. Environmental testing had revealed that the 36B mobile support tower (MST) exceeded the TSCA standard for polychlorinated biphenyls (PCB) paint (<50 ppm), as did the high bay sections of the Titan Vertical Integration Building (VIB). Thus, while most of the steel structures could be completely recycled, about one-third of 36B MST and the affected areas of the VIB were to be consigned to an on-site regulated waste landfill. In all, it is estimated that approximately 10,000,000 kg (11,000 tons) of PCB-coated steel will be land-filled and 23,000,000 kg (25,000 tons) will be recycled. The recycling of the steel and other materials made it possible to do additional demolition by using these funds. Therefore, finding ways to maximize the recycle value of materials became a key factor in the pre-demolition characterization and implementation strategy. This paper will present the following: - Critical elements in demolition planning working at an active launch facility; - Characterization and strategy to maximize steel recycle; - Waste disposition strategy to maximize recycle/reuse and minimize disposal; - Recycle options available at DOD installations that allow for addition funds for demolition; - Innovation in demolition methodologies for large structures - explosive demolition and large-scale dismantlement; - H and S aspects of explosive demolition and large scale dismantlement. In conclusion: The Cape Canaveral AFS Demolition Program has been a great success due to the integration of multiple operations and contractors working together to determine the most cost-effective demolition methods. It is estimated that by extensive pre-planning and working with CCAFS representatives, as well as maximizing the recycle credits of various material, primarily steel, that the government will be able to complete what was base-lined to be a $30 M demolition program for < $20 M. Other factors included a competitive subcontractor environment where they were encouraged with incentives to maximize recycle/reuse of material and creative demolition solutions. Also, by overlapping multiple demolition tasks at multiple facilities allowed for a reduction in field oversight. (authors)

Jones, A.; Hambro, L. [AMEC Earth and Environmental, Inc., Cocoa, FL (United States); Hooper, K. [U.S. Air Force 45th Space Wing, Patrick AFB, Florida (United States)

2008-07-01

316

Do You Know Buildings? Facility Planning Knowledge and Skills.  

ERIC Educational Resources Information Center

A school business administrator should be equipped to lead a district facility planning effort. Describes the processes of demographic planning, facility assessing, long-range financial facility plan budgeting, and aligning the facility plan with the district strategic plan. (MLF)

Glass, Thomas E.

1994-01-01

317

Salmonella and Campylobacter prevalence and concentration on pasture-raised broilers processed on-farm, in a Mobile Processing Unit, and at small USDA-inspected facilities  

Technology Transfer Automated Retrieval System (TEKTRAN)

The small-scale, pasture-raised poultry production model is a growing niche in the locally grown food movement. There is limited research that focuses on the food safety of small-scale broiler processing methods. The objective of this study was to compare Salmonella and Campylobacter prevalence and ...

318

U.S. Army Engineer Waterways Experiment Station (WES) support to Department of Energy Rocky Flats Facility (DOE RF) saltcrete processing. Progress report, April 1--June 30, 1994  

SciTech Connect

Accomplishments during this report period for waste cementation/processing operations are summarized. During this report period, the team completed an important site visit to the Rocky Flats Facility (RF). This visit focused on extensive interaction with DOE contract personnel about microstructural and phase characterization of saltcrete. A copy of the trip report prepared by the WES team is enclosed. The team prepared a document detailing procedures for sample preparation and analysis to enhance the usefulness of results of the forensic work underway at RF. A copy of this document is enclosed. A proposal was prepared for additional short-term tasks to contribute significantly to gaining the most benefit from data gathered during forensic analyses of saltcrete, and waste-treatment studies, by EG and G. A copy of this proposal was forwarded to RF at the end of May, and it is included.

NONE

1994-07-26

319

Conical scan impact study. Volume 1: General central data processing facility. [multispectral band scanner design alternatives for earth resources data  

NASA Technical Reports Server (NTRS)

The impact of a conical scan versus a linear scan multispectral scanner (MSS) instrument was studied in terms of: (1) design modifications required in framing and continuous image recording devices; and (2) changes in configurations of an all-digital precision image processor. A baseline system was defined to provide the framework for comparison, and included pertinent spacecraft parameters, a conical MSS, a linear MSS, an image recording system, and an all-digital precision processor. Lateral offset pointing of the sensors over a range of plus or minus 20 deg was considered. The study addressed the conical scan impact on geometric, radiometric, and aperture correction of MSS data in terms of hardware and software considerations, system complexity, quality of corrections, throughput, and cost of implementation. It was concluded that: (1) if the MSS data are to be only film recorded, then there is only a nomial concial scan impact on the ground data processing system; and (2) if digital data are to be provided to users on computer compatible tapes in rectilinear format, then there is a significant conical scan impact on the ground data processing system.

Ebert, D. H.; Eppes, T. A.; Thomas, D. J.

1973-01-01

320

Fabrication of flower-shaped Bi 2O 3 superstructure by a facile template-free process  

NASA Astrophysics Data System (ADS)

A novel flower-shaped Bi 2O 3 superstructure has been successfully synthesized by calcination of the precursor, which was prepared via a citric acid assisted hydrothermal process. The precursor and Bi 2O 3 were characterized with respect to morphology, crystal structure and elemental chemical state by field-emission scanning electron microscopy (FESEM), transmission electron microscopy (TEM), X-ray diffraction (XRD) and X-ray photoelectron spectroscopy (XPS). It was shown that both the precursor and Bi 2O 3 flower-shaped superstructure were constructed of numerous nanosheets while the nanosheets consisted of a great deal of nanoparticles. Furthermore, key factors for the formation of the superstructures have been proposed; a mechanism for the growth of the superstructure has been presented based on the FESEM investigation of different growth stages.

Zhang, Li; Hashimoto, Yoshio; Taishi, Toshinori; Nakamura, Isao; Ni, Qing-Qing

2011-05-01

321

NASA/NOAA implementation of the USAID-sponsored satellite ground station and data processing facility for Bangladesh  

NASA Technical Reports Server (NTRS)

A description is given of a project to transfer multiple environmental satellite data reception, processing, and interpretation capabilities from the U.S. to Bangladesh. The goal of the project is to improve the management of resources related primarily to agriculture, water development, forestry, and fisheries. It is also hoped to improve the existing cyclone/storm surge warning system. An account is given of the interagency and international cooperation underlying the project. The remote-sensing installation in Dhaka, Bangladesh, is described, and the most likely system applications are summarized. Attention is also given to the special requirements concerning this type of technology transfer, and an assessment is made of the project's practical value to Bangladesh.

Dodge, J. C.; Vermillion, C. H.

1983-01-01

322

Requalification of the 235-F Metallograph Facility gloveboxes for use in the 773-A Pre-Processing/Re-Processing Laboratory and plutonium ``Can in Can`` demonstrations  

SciTech Connect

The proposed use for these gloveboxes are: (1) to utilize the Pu metal glovebox system for the primary containment associated with the Pre-Processing/Re-Processing Laboratory for obtaining radioactive glass compound viscometer analysis, and (2) to utilize the Pu oxide glovebox system for primary containment associated with the Pu Can in Can Demonstration for proof of principle testing specific to long term Pu immobilization and storage technology. This report presents objective evidence that supports the engineering judgment indicating the existing gloveboxes can be requalified for the proposed uses indicated above. SRS has the ability to duplicate the test parameters, with site forces, that will meet or exceed the identical acceptance criteria established to qualify the existing gloveboxes. The qualification effort will be a documented procedure using the leak test criteria characteristic of the original glovebox purchase. Two equivalent tests will be performed, one for post modification leak test acceptance and one for post installation leak test acceptance. Assurance of this approach is substantiated by thorough reviews of glovebox, leak test and weld standard guidance documents, as well as review of historical Project 3253 design and vendor information specific to the existing gloveboxes. Reuse of these gloveboxes will eliminate the need for competitive procurement of new gloveboxes.

Hinds, S.; Hidlay, J.

1997-04-16

323

RCRA FACILITIES  

EPA Science Inventory

Points represent facilities that are regulated by the EPA under the Resource Conservation and Recovery Act (RCRA). Facilities regulated under RCRA generate, dispose of, treate or transport hazardous waste. RCRA is a law enacted by Congress in 1976 and amended in 1984 to include ...

324

Nuclear Facilities  

NSDL National Science Digital Library

In order to produce nuclear weapons, each country must have facilities to produce and refine the nuclear materials, conduct research on weapon design, and store the completed weapons. The interactives in this collection allow you to explore the nuclear facilities of the nuclear powers (both declared and undeclared).

Christopher Griffith

325

Solar production of industrial process hot water: operation and evaluation of the Campbell Soup hot water solar facility. Final report, September 1, 1979-December 10, 1980  

SciTech Connect

The operation and evaluation of a solar hot water facility designed by Acurex Corporation and installed (November 1977) at the Campbell Soup Company Sacramento, California canning plant is summarized. The period of evaluation was for 12 months from October 1979 through September 1980. The objective of the work was to obtain additional, long term data on the operation and performance of the facility. Minor modifications to the facility were completed. The system was operated for 15 months, and 12 months of detailed data were evaluated. The facility was available for operation 99% of the time during the last 8 months of evaluation. A detailed description of the solar facility and of the operating experience is given, and a summary of system performance for the 12 month operation/evaluation period is presented. Recommendations for large-scale solar facilities based on this project's experience are given, and an environmental impact assessment for the Campbell Soup solar facility is provided. (WHK)

Kull, J. I.; Niemeyer, W. N.; Youngblood, S. B.

1980-12-01

326

Processes to Open the Container and the Sample Catcher of the Hayabusa Returned Capsule in the Planetary Material Sample Curation Facility of JAXA  

NASA Technical Reports Server (NTRS)

Japanese spacecraft Hayabusa, which returned from near-Earth-asteroid Itokawa, successfully returned its reentry capsule to the Earth, the Woomera Prohibited Area in Australia in Jun 13th, 2010, as detailed in another paper [1]. The capsule introduced into the Planetary Material Sample Curation Facility in the Sagamihara campus of JAXA in the early morning of June 18th. Hereafter, we describe a series of processes for the returned capsule and the container to recover gas and materials in there. A transportation box of the recovered capsule was cleaned up on its outer surface beforehand and introduced into the class 10,000 clean room of the facility. Then, the capsule was extracted from the box and its plastic bag was opened and checked and photographed the outer surface of the capsule. The capsule was composed of the container, a backside ablator, a side ablator, an electronic box and a supporting frame. The container consists of an outer lid, an inner lid, a frame for latches, a container and a sample catcher, which is composed of room A and B and a rotational cylinder. After the first check, the capsule was packed in a plastic bag with N2 again, and transferred to the Chofu campus in JAXA, where the X-ray CT instrument is situated. The first X-ray CT analysis was performed on the whole returned capsule for confirming the conditions of latches and O-ring seal of the container. The analysis showed that the latches of the container should have worked normally, and that the double Orings of the container seemed to be sealed its sample catcher with no problem. After the first X-ray CT, the capsule was sent back to Sagamihara and introduced in the clean room to exclude the electronic box and the side ablator from the container by hand tools. Then the container with the backside ablator was set firmly to special jigs to fix the lid of container tightly to the container and set to a milling machine. The backside ablator was drilled by the machine to expose heads of bolts, which combined the ablator to the outer lid of the container, and after the drilling had been finished, all the bolts were unscrewed and the backside ablator was removed from the container. Then, the container was sent to the Chofu X-ray facility again to examine in detail by a micro X-ray CT instrument in order to reconfirm that the condition of the latches of the lid of container was normal and that its double O-ring seemed to have been sealed after the last X-ray CT analysis.

Fujimura, A.; Abe, M.; Yada, T.; Nakamura, T.; Noguchi, T.; Okazaki, R.; Ishibashi, Y.; Shirai, K.; Okada, T.; Yano, H.; Zolensky, M. E.; Sandford, S.; Ueno, M.; Mukai, T.; Yoshikawa, M.; Kawaguchi, J.

2011-01-01

327

Business Planning Core Facilities  

PubMed Central

Thoughtful business planning is pivotal to the success of any business/operational venture. When planned in a thoughtful and detailed manner there are very few operational or financial surprises for an institution or facility (service center) to contend with. At Stony Brook Medicine we include SWOT analysis and a detailed Market Analysis as part of the process. This is bolstered by an initiative to ensure institutional policies are met so that facilities remain in compliance throughout their lifecycle. As we operate 14 facilities we have had the opportunity to become creative in our approach to coordinate activities, virtualize services, integrate new software business-to-business partners, and finally coordinate plans for phased consolidation instead of outright termination of services when required. As the Associate Dean for Scientific Operations and Research Facilities, the shared research facilities (cores) of the Medical School are in my direct line of sight. We understand their value to the meeting our overall research mission. We have found that an active process of monitoring to predict trouble as much as possible is the best approach for facilities. Some case analysis of this type of interaction will be presented as well.

Itzkowitz, G.N.

2014-01-01

328

Ames Hybrid Combustion Facility  

NASA Technical Reports Server (NTRS)

The report summarizes the design, fabrication, safety features, environmental impact, and operation of the Ames Hybrid-Fuel Combustion Facility (HCF). The facility is used in conducting research into the scalability and combustion processes of advanced paraffin-based hybrid fuels for the purpose of assessing their applicability to practical rocket systems. The facility was designed to deliver gaseous oxygen at rates between 0.5 and 16.0 kg/sec to a combustion chamber operating at pressures ranging from 300 to 900. The required run times were of the order of 10 to 20 sec. The facility proved to be robust and reliable and has been used to generate a database of regression-rate measurements of paraffin at oxygen mass flux levels comparable to those of moderate-sized hybrid rocket motors.

Zilliac, Greg; Karabeyoglu, Mustafa A.; Cantwell, Brian; Hunt, Rusty; DeZilwa, Shane; Shoffstall, Mike; Soderman, Paul T.; Bencze, Daniel P. (Technical Monitor)

2003-01-01

329

FACILITY DATABASE  

Cancer.gov

January 2008 LASP FACILTY Database Form 5.000 Issue Reporting Form This form is used to report data and/or program related issues regarding the FACILITY database, Supplemental, or the LASP Online Access System. Before submitting this form,

330

Health Facilities  

MedlinePLUS

Health facilities are places that provide health care. They include hospitals, clinics, outpatient care centers, and specialized care centers, such as birthing centers and psychiatric care centers. When you choose ...

331

Facility Planning.  

ERIC Educational Resources Information Center

This article reviews recommendations on policies for leasing surplus school space made during the Council of Educational Facility Planners/International conference. A case study presentation of a Seattle district's use of lease agreements is summarized. (MJL)

Graves, Ben E.

1984-01-01

332

FEASIBILITY EVALUATION AND RETROFIT PLAN FOR COLD CRUCIBLE INDUCTION MELTER DEPLOYMENT IN THE DEFENSE WASTE PROCESSING FACILITY AT SAVANNAH RIVER SITE - 8118  

SciTech Connect

Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste glass melting at the Defense Waste Processing Facility (DWPF) at Savannah River Site (SRS) as well as for other waste vitrification facilities. Proponents of this technology cite high temperature operation, high tolerance for noble metals and aluminum, high waste loading, high throughput capacity, and low equipment cost as the advantages over existing Joule Heated Melter (JHM) technology. This paper describes the CCIM technology and identifies technical challenges that must be addressed in order to implement CCIMs in the DWPF. The CCIM uses induction heating to maintain molten glass at high temperature. A water-cooled helical induction coil is connected to an AC current supply, typically operating at frequencies from 100 KHz to 5 MHz. The oscillating magnetic field generated by the oscillating current flow through the coil induces eddy currents in conductive materials within the coil. Those oscillating eddy currents, in turn, generate heat in the material. In the CCIM, the induction coil surrounds a 'Cold Crucible' which is formed by metal tubes, typically copper or stainless steel. The tubes are constructed such that the magnetic field does not couple with the crucible. Therefore, the field generated by the induction coil couples primarily with the conductive medium (hot glass) within. The crucible tubes are water cooled to maintain their temperature between 100 C to 200 C so that a protective layer of molten glass and/or batch material, referred to as a 'skull', forms between them and the hot, corrosive melt. Because the protective skull is the only material directly in contact with the molten glass, the CCIM doesn't have the temperature limitations of traditional refractory lined Joule heated melters. It can be operated at melt temperatures in excess of 2000 C, allowing processing of high waste loading batches and difficult-to-melt compounds. The CCIM is poured through a bottom drain, typically through a water-cooled slide valve that starts and stops the pour stream. To promote uniform temperature distribution and increase heat transfer to the slurry fed High Level Waste (HLW) sludge, the CCIM may be equipped with bubblers and/or water cooled mechanical agitators. The DWPF could benefit from use of CCIM technology, especially in light of our latest projections of waste volume to be vitrified. Increased waste loading and increased throughput could result in substantial life cycle cost reduction. In order to significantly surpass the waste throughput capability of the currently installed Joule Heated Melter, it may be necessary to install two 950 mm CCIMs in the DWPF Melt Cell. A cursory evaluation of system design requirements and modifications to the facility that may be required to support installation and operation of two 950 mm CCIMs was performed. Based on this evaluation, it appears technically feasible to position two CCIMs in the Melt Cell of the DWPF within the existing footprint of the current melter. Interfaces with support systems and controls including Melter Feed, Power, Melter Cooling Water, Melter Off-gas, and Canister Operations must be designed to support dual CCIM operations.

Barnes, A; Dan Iverson, D; Brannen Adkins, B

2007-11-15

333

FEASIBILITY EVALUATION AND RETROFIT PLAN FOR COLD CRUCIBLE INDUCTION MELTER DEPLOYMENT IN THE DEFENSE WASTE PROCESSING FACILITY AT SAVANNAH RIVER SITE 8118  

SciTech Connect

Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste glass melting at the Defense Waste Processing Facility (DWPF) at Savannah River Site (SRS) as well as for other waste vitrification facilities. Proponents of this technology cite high temperature operation, high tolerance for noble metals and aluminum, high waste loading, high throughput capacity, and low equipment cost as the advantages over existing Joule Heated Melter (JHM) technology. The CCIM uses induction heating to maintain molten glass at high temperature. A water-cooled helical induction coil is connected to an AC current supply, typically operating at frequencies from 100 KHz to 5 MHz. The oscillating magnetic field generated by the oscillating current flow through the coil induces eddy currents in conductive materials within the coil. Those oscillating eddy currents, in turn, generate heat in the material. In the CCIM, the induction coil surrounds a 'Cold Crucible' which is formed by metal tubes, typically copper or stainless steel. The tubes are constructed such that the magnetic field does not couple with the crucible. Therefore, the field generated by the induction coil couples primarily with the conductive medium (hot glass) within. The crucible tubes are water cooled to maintain their temperature between 100 C to 200 C so that a protective layer of molten glass and/or batch material, referred to as a 'skull', forms between them and the hot, corrosive melt. Because the protective skull is the only material directly in contact with the molten glass, the CCIM doesn't have the temperature limitations of traditional refractory lined JHM. It can be operated at melt temperatures in excess of 2000 C, allowing processing of high waste loading batches and difficult-to-melt compounds. The CCIM is poured through a bottom drain, typically through a water-cooled slide valve that starts and stops the pour stream. To promote uniform temperature distribution and increase heat transfer to the slurry fed High Level Waste (HLW) sludge, the CCIM may be equipped with bubblers and/or water cooled mechanical agitators. The DWPF could benefit from use of CCIM technology, especially in light of our latest projections of waste volume to be vitrified. Increased waste loading and increased throughput could result in substantial life cycle cost reduction. In order to significantly surpass the waste throughput capability of the currently installed JHM, it may be necessary to install two 950 mm CCIMs in the DWPF Melt Cell. A cursory evaluation of system design requirements and modifications to the facility that may be required to support installation and operation of two 950 mm CCIMs was performed. Based on this evaluation, it appears technically feasible to position two CCIMs in the Melt Cell of the DWPF within the existing footprint of the current melter. Interfaces with support systems and controls including Melter Feed, Power, Melter Cooling Water, Melter Off-gas, and Canister Operations must be designed to support dual CCIM operations. This paper describes the CCIM technology and identifies technical challenges that must be addressed in order to implement CCIMs in the DWPF.

Barnes, A; Dan Iverson, D; Brannen Adkins, B

2008-02-06

334

Feasibility Evaluation and Retrofit Plan for Cold Crucible Induction Melter Deployment in the Defense Waste Processing Facility at Savannah River Site  

SciTech Connect

Cold crucible induction melters (CCIM) have been proposed as an alternative technology for waste glass melting at the Defense Waste Processing Facility (DWPF) at Savannah River Site (SRS) as well as for other waste vitrification facilities. Proponents of this technology cite high temperature operation, high tolerance for noble metals and aluminum, high waste loading, high throughput capacity, and low equipment cost as the advantages over existing Joule Heated Melter (JHM) technology. The CCIM uses induction heating to maintain molten glass at high temperature. A water-cooled helical induction coil is connected to an AC current supply, typically operating at frequencies from 100 kHz to 5 MHz. The oscillating magnetic field generated by the oscillating current flow through the coil induces eddy currents in conductive materials within the coil. Those oscillating eddy currents, in turn, generate heat in the material. In the CCIM, the induction coil surrounds a 'Cold Crucible' which is formed by metal tubes, typically copper or stainless steel. The tubes are constructed such that the magnetic field does not couple with the crucible. Therefore, the field generated by the induction coil couples primarily with the conductive medium (hot glass) within. The crucible tubes are water cooled to maintain their temperature between 100 deg. C to 200 deg. C so that a protective layer of molten glass and/or batch material, referred to as a 'skull', forms between them and the hot, corrosive melt. Because the protective skull is the only material directly in contact with the molten glass, the CCIM doesn't have the temperature limitations of traditional refractory lined JHM. It can be operated at melt temperatures in excess of 2000 deg. C, allowing processing of high waste loading batches and difficult-to-melt compounds. The CCIM is poured through a bottom drain, typically through a water-cooled slide valve that starts and stops the pour stream. To promote uniform temperature distribution and increase heat transfer to the slurry fed High Level Waste (HLW) sludge, the CCIM may be equipped with bubblers and/or water cooled mechanical agitators. The DWPF could benefit from use of CCIM technology, especially in light of our latest projections of waste volume to be vitrified. Increased waste loading and increased throughput could result in substantial life cycle cost reduction. In order to significantly surpass the waste throughput capability of the currently installed JHM, it may be necessary to install two 950 mm CCIMs in the DWPF Melt Cell. A cursory evaluation of system design requirements and modifications to the facility that may be required to support installation and operation of two 950 mm CCIMs was performed. Based on this evaluation, it appears technically feasible to position two CCIMs in the Melt Cell of the DWPF within the existing footprint of the current melter. Interfaces with support systems and controls including Melter Feed, Power, Melter Cooling Water, Melter Off-gas, and Canister Operations must be designed to support dual CCIM operations. This paper describes the CCIM technology and identifies technical challenges that must be addressed in order to implement CCIMs in the DWPF. (authors)

Barnes, A.B. [Savannah River National Laboratory, Washington Savannah River Company, Aiken, SC (United States); Iverson, D.C.; Adkins, B.J. [Liquid Waste Operations, Washington Savannah River Company, Aiken, SC (United States); Tchemitcheff, E. [AREVA NC Inc., Richland Office, Richland, WA (United States)

2008-07-01

335

CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT  

SciTech Connect

The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

J.F. Beesley

2005-04-21

336

Verification of the Accountability Method as a Means to Classify Radioactive Wastes Processed Using THOR Fluidized Bed Steam Reforming at the Studsvik Processing Facility in Erwin, Tennessee, USA - 13087  

SciTech Connect

Studsviks' Processing Facility Erwin (SPFE) has been treating Low-Level Radioactive Waste using its patented THOR process for over 13 years. Studsvik has been mixing and processing wastes of the same waste classification but different chemical and isotopic characteristics for the full extent of this period as a general matter of operations. Studsvik utilizes the accountability method to track the movement of radionuclides from acceptance of waste, through processing, and finally in the classification of waste for disposal. Recently the NRC has proposed to revise the 1995 Branch Technical Position on Concentration Averaging and Encapsulation (1995 BTP on CA) with additional clarification (draft BTP on CA). The draft BTP on CA has paved the way for large scale blending of higher activity and lower activity waste to produce a single waste for the purpose of classification. With the onset of blending in the waste treatment industry, there is concern from the public and state regulators as to the robustness of the accountability method and the ability of processors to prevent the inclusion of hot spots in waste. To address these concerns and verify the accountability method as applied by the SPFE, as well as the SPFE's ability to control waste package classification, testing of actual waste packages was performed. Testing consisted of a comprehensive dose rate survey of a container of processed waste. Separately, the waste package was modeled chemically and radiologically. Comparing the observed and theoretical data demonstrated that actual dose rates were lower than, but consistent with, modeled dose rates. Moreover, the distribution of radioactivity confirms that the SPFE can produce a radiologically homogeneous waste form. The results of the study demonstrate: 1) the accountability method as applied by the SPFE is valid and produces expected results; 2) the SPFE can produce a radiologically homogeneous waste; and 3) the SPFE can effectively control the waste package classification. (authors)

Olander, Jonathan [Studsvik Processing Facility Erwin, 151 T.C. Runnion Rd., Erwin, TN 37650 (United States)] [Studsvik Processing Facility Erwin, 151 T.C. Runnion Rd., Erwin, TN 37650 (United States); Myers, Corey [Studsvik, Inc., 5605 Glenridge Drive, Suite 705, Atlanta, GA 30342 (United States)] [Studsvik, Inc., 5605 Glenridge Drive, Suite 705, Atlanta, GA 30342 (United States)

2013-07-01

337

Physical processes at work in sub-30 fs, PW laser pulse-driven plasma accelerators: Towards GeV electron acceleration experiments at CILEX facility  

NASA Astrophysics Data System (ADS)

Optimal regimes and physical processes at work are identified for the first round of laser wakefield acceleration experiments proposed at a future CILEX facility. The Apollon-10P CILEX laser, delivering fully compressed, near-PW-power pulses of sub-25 fs duration, is well suited for driving electron density wakes in the blowout regime in cm-length gas targets. Early destruction of the pulse (partly due to energy depletion) prevents electrons from reaching dephasing, limiting the energy gain to about 3 GeV. However, the optimal operating regimes, found with reduced and full three-dimensional particle-in-cell simulations, show high energy efficiency, with about 10% of incident pulse energy transferred to 3 GeV electron bunches with sub-5% energy spread, half-nC charge, and absolutely no low-energy background. This optimal acceleration occurs in 2 cm length plasmas of electron density below 1018 cm-3. Due to their high charge and low phase space volume, these multi-GeV bunches are tailor-made for staged acceleration planned in the framework of the CILEX project. The hallmarks of the optimal regime are electron self-injection at the early stage of laser pulse propagation, stable self-guiding of the pulse through the entire acceleration process, and no need for an external plasma channel. With the initial focal spot closely matched for the nonlinear self-guiding, the laser pulse stabilizes transversely within two Rayleigh lengths, preventing subsequent evolution of the accelerating bucket. This dynamics prevents continuous self-injection of background electrons, preserving low phase space volume of the bunch through the plasma. Near the end of propagation, an optical shock builds up in the pulse tail. This neither disrupts pulse propagation nor produces any noticeable low-energy background in the electron spectra, which is in striking contrast with most of existing GeV-scale acceleration experiments.

Beck, A.; Kalmykov, S. Y.; Davoine, X.; Lifschitz, A.; Shadwick, B. A.; Malka, V.; Specka, A.

2014-03-01

338

MEASUREMENT AND CALCULATION OF RADIONUCLIDE ACTIVITIES IN SAVANNAH RIVER SITE HIGH LEVEL WASTE SLUDGE FOR ACCEPTANCE OF DEFENSE WASTE PROCESSING FACILITY GLASS IN A FEDERAL REPOSITORY  

SciTech Connect

This paper describes the results of the analyses of High Level Waste (HLW) sludge slurry samples and of the calculations necessary to decay the radionuclides to meet the reporting requirement in the Waste Acceptance Product Specifications (WAPS) [1]. The concentrations of 45 radionuclides were measured. The results of these analyses provide input for radioactive decay calculations used to project the radionuclide inventory at the specified index years, 2015 and 3115. This information is necessary to complete the Production Records at Savannah River Site's Defense Waste Processing Facility (DWPF) so that the final glass product resulting from Macrobatch 5 (MB5) can eventually be submitted to a Federal Repository. Five of the necessary input radionuclides for the decay calculations could not be measured directly due to their low concentrations and/or analytical interferences. These isotopes are Nb-93m, Pd-107, Cd-113m, Cs-135, and Cm-248. Methods for calculating these species from concentrations of appropriate other radionuclides will be discussed. Also the average age of the MB5 HLW had to be calculated from decay of Sr-90 in order to predict the initial concentration of Nb-93m. As a result of the measurements and calculations, thirty-one WAPS reportable radioactive isotopes were identified for MB5. The total activity of MB5 sludge solids will decrease from 1.6E+04 {micro}Ci (1 {micro}Ci = 3.7E+04 Bq) per gram of total solids in 2008 to 2.3E+01 {micro}Ci per gram of total solids in 3115, a decrease of approximately 700 fold. Finally, evidence will be given for the low observed concentrations of the radionuclides Tc-99, I-129, and Sm-151 in the HLW sludges. These radionuclides were reduced in the MB5 sludge slurry to a fraction of their expected production levels due to SRS processing conditions.

Bannochie, C; David Diprete, D; Ned Bibler, N

2008-12-31

339

FULL-SCALE LABORATORY SIMULATION FACILITY TO TEST PARTICULATE AND ORGANIC EMISSIONS FROM A THIRD WORLD RESIDENTIAL COMBUSTION PROCESS. I. FACILITY DESCRIPTION AND RESULTS OF TESTS OF THREE RURAL CHINA RESIDENTIAL COALS, A U.S. COAL, AND WOOD  

EPA Science Inventory

The paper gives results of a series of 12 tests for 3 coals from a rural area of China with abnormally high lung cancer rates, a U. S. coal, and pine wood fuel. It also discusses a residential combustion simulator, built at EPA's Research Triangle Park, NC, facility to conduct em...

340

EVALUATION OF THE IMPACT OF THE DEFENSE WASTE PROCESSING FACILITY (DWPF) LABORATORY GERMANIUM OXIDE USE ON RECYCLE TRANSFERS TO THE H-TANK FARM  

SciTech Connect

When processing High Level Waste (HLW) glass, 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 feed stream, rather than on the downstream melt or glass product. This strategy is known as 'feed forward statistical process control.' The DWPF depends on chemical analysis of the feed streams from the Sludge Receipt and Adjustment Tank (SRAT) and the Slurry Mix Evaporator (SME) where the frit plus adjusted sludge from the SRAT are mixed. The SME is the last vessel in which any chemical adjustments or frit additions can be made. Once the analyses of the SME product are deemed acceptable, the SME product is transferred to the Melter Feed Tank (MFT) and onto the melter. The SRAT and SME analyses have been analyzed by the DWPF laboratory using a 'Cold Chemical' method but this dissolution did not adequately dissolve all the elemental components. A new dissolution method which fuses the SRAT or SME product with cesium nitrate (CsNO{sub 3}), germanium (IV) oxide (GeO{sub 2}) and cesium carbonate (Cs{sub 2}CO{sub 3}) into a cesium germanate glass at 1050 C in platinum crucibles has been developed. Once the germanium glass is formed in that fusion, it is readily dissolved by concentrated nitric acid (about 1M) to solubilize all the elements in the SRAT and/or SME product for elemental analysis. When the chemical analyses are completed the acidic cesium-germanate solution is transferred from the DWPF analytic laboratory to the Recycle Collection Tank (RCT) where the pH is increased to {approx}12 M to be released back to the tank farm and the 2H evaporator. Therefore, about 2.5 kg/yr of GeO{sub 2}/year will be diluted into 1.4 million gallons of recycle. This 2.5 kg/yr of GeO{sub 2} may increase to 4 kg/yr when improvements are implemented to attain an annual canister production goal of 400 canisters. Since no Waste Acceptance Criteria (WAC) exists for germanium in the Tank Farm, the Effluent Treatment Project, or the Saltstone Production Facility, DWPF has requested an evaluation of the fate of the germanium in the caustic environment of the RCT, the 2H evaporator, and the tank farm. This report evaluates the effect of the addition of germanium to the tank farm based on: (1) the large dilution of Ge in the RCT and tank farm; (2) the solubility of germanium in caustic solutions (pH 12-13); (3) the potential of germanium to precipitate as germanium sodalites in the 2H Evaporator; and (4) the potential of germanium compounds to precipitate in the evaporator feed tank. This study concludes that the impacts of transferring up to 4 kg/yr germanium to the RCT (and subsequently the 2H evaporator feed tank and the 2H evaporator) results in <2 ppm per year (1.834 mg/L) which is the maximum instantaneous concentration expected from DWPF. This concentration is insignificant as most sodium germanates are soluble at the high pH of the feed tank and evaporator solutions. Even if sodium aluminosilicates form in the 2H evaporator, the Ge will likely substitute for some small amount of the Si in these structures and will be insignificant. It is recommended that the DWPF continue with their strategy to add germanium as a laboratory chemical to Attachment 8.2 of the DWPF Waste Compliance Plan (WCP).

Jantzen, C.; Laurinat, J.

2011-08-15

341

Cathode Life Test Facility  

Microsoft Academic Search

The Cathode Life Test Facility (CLTF) has been in operation for ten years and has tested ten different cathode types for a total of approximately 2.0 million hours of life test data. As part of the defense management review (DMR) process, Rome Laboratory (RL) has eliminated internal research efforts pertaining to cathode life testing. Based on this directive, the CLTF

Ronald J. Jardieu

1994-01-01

342

FACILITIES MAINTENANCE MAIN WAREHOUSE  

E-print Network

Validation 19 Process Description (PD) & 20 - 21 Operational Audit (OA) Summary CUSTOMER SERVICE SURVEY-hour Availability Factor (MAF) unique to Facilities Management's operating schedule was developed incorporating & MEASUREMENT 22 ­ 24 Customer Service Survey 22 Customer Service Survey Charts 22 ­ 23 Customer Service

Hemmers, Oliver

343

NISCO Cogeneration Facility  

E-print Network

The NISCO Cogeneration facility utilizes two fluidized bed boilers to generate 200 MW of electricity and up to 80,000 LBS/HR of steam for process use. The partnership, of three industrial electricity users, Citgo, Conoco, and Vista Chemical...

Zierold, D. M.

344

Accreditation for Indoor Climbing Facilities.  

ERIC Educational Resources Information Center

To ensure that the rapidly growing climbing gym industry maintains the excellent safety record established so far, the Climbing Gym Association (CGA) has developed the Peer Review and Accreditation Program, a process of review between qualified and experienced CGA reviewers and a climbing facility operator to assess the facility's risk management…

Mayfield, Peter

345

Ecological studies related to the construction of the Defense Waste Processing Facility on the Savannah River Site. Annual report, FY-1991 and FY-1992  

SciTech Connect

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 14 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 (10 CFR 1022).

Scott, D.E.; Chazel, A.C.; Pechmann, J.H.K.; Estes, R.A.

1993-06-01

346

Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site. FY 1989--1990 annual report  

SciTech Connect

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).

Pechmann, J.H.K.; Scott, D.E.; McGregor, J.H.; Estes, R.A.; Chazal, A.C.

1993-02-01

347

Facilities Manager.  

ERIC Educational Resources Information Center

Presents a series of articles that cover a range of issues with regard to the Association of Higher Education Facilities Officers. Papers explore ways to balance natural and human settings, provide an overview of a professional leadership academy, describe the preparations for an effectiveness skills program, and outline some of the concerns…

Facilities Manager, 1998

1998-01-01

348

Music Facilities.  

ERIC Educational Resources Information Center

The layouts and specifications in this booklet are intended to assist those involved in planning music facilities for elementary and secondary schools. Drawings, room plans, and text illustrate specifications for location; space relationship; combined and separate instrumental and vocal rooms; practice rooms; and auxiliary areas. Particular…

Ontario Dept. of Education, Toronto. School Planning and Building Research Section.

349

Lurie Nanofabrication Facility  

NSDL National Science Digital Library

The Michigan Nanofabrication Facility (MNF) at the University of Michigan Solid-State Electronics Laboratory (SSEL) is one of the leading centers worldwide on micro electromechanical systems (MEMS) and microsystems. It provides facilities and processes for the integration of Si integrated circuits and MEMS with nanotechnology, with applications in biology, medical systems, chemistry, and environmental monitoring. The MNF builds on its experience in integration of Si-based electronics with MEMS transducers and micropackaging to push these interfaces into the nanometer regime with emphasis on the fabrication, packaging, and testing of integrated devices for chemical and biological sensing, electrical stimulation of biological systems, and integrated fluidic systems.

2008-11-04

350

From Seismic Characterization to Coupled Process Testing Along Drifts at LSBB as an Example of Establishing an International Facility for a Worldwide Network of Underground Research Laboratories  

NASA Astrophysics Data System (ADS)

The Laboratoire Souterrain à Bas Bruit (LSBB) at Rustrel France is a French National Instrumented Infrastructure, CNRS, dedicated to inter-Disciplinary Underground Science and Technology. The underground galleries and the surrounding carbonate rock formations are well characterized by seismic imaging studies obtained with sensors both along the ridges and underground along the drifts. The facility is horizontally accessible with the main tunnel following an L-shape. The deepest is 518m below the surface. The main tunnel continues with a long gallery below the ridge, and ends with an escape shaft to the surface. Electrical and fiber optic communication cables connect the galleries and the underground to the huts on the surface. All data from LSBB are distributed on line (http://lsbb.oca.eu) and data from the 3D broadband seismic array are fed in real time (delay of ~4s) to the European Union seismic network (see streams RUSF_01, 03, 04, 05, 06, and 07 at http://www.orfeus-eu.org/Data-info/orbstats.html). Concurrently with establishing the seismic network, the LSBB characterizes its low noise environment, including its low ambient magnetic noise with a (SQUID)2 magnetometer, located 518m below the surface in a shielded cage. The magnetic noise floor in the cage is lower than 2fT/SQRT(Hz). Together with the seismic network and the magnetic sensor, tiltmeters, radiation sensors, groundwater pressure and chemistry monitoring devices are installed to characterize the unsaturated environment along the tunnel. Seasonal seepage observations are also collected. 3 national research projects are currently carried out along dedicated tunnels: (1) the project on High-Pulse Poroelasticity Protocol (HPPP) for geophysical monitoring of CO2 injection in reservoirs (http://hppp.unice.fr/), focusing currently on hydromechanical testing in carbonate rock; (2) the MAXWELL electromagnetic project on broadband imaging which employs joint resistivity and permittivity inversion (http://lsbb.oca.eu/spip.php?article46); and (3) the project LINES on fiber optic instrumentation to detect small vibrations and deformations (http://lsbb.oca.eu/spip.php?article99). The LSBB, under continuous improvement, is an underground laboratory dedicated to the permanent observation of coupled processes in the shallow crust. The results obtained at LSBB contribute to the knowledge of the solid Earth and space physics. The escape tunnel at the end of the tunnel network is used for hydrogeological monitoring. We plane to use this space and new vertical boreholes for CO2 injection studies in that carbonate rock medium. Carbonate reservoirs play a crucial role in the analysis of water resources, petroleum reserves, and CO2 and other fluids sequestrations. These studies are pursued worldwide, including the ones planned in the USA’s Deep Underground Science and Engineering Laboratory in metamorphic rock. We plan to expand our collaborations between laboratories to include other underground research facilities and collectively pursue international, interdisciplinary initiatives, leading to innovation in energy, water resource, and environmental studies.

Gaffet, S.; Wang, J. S.

2009-12-01

351

Facility effluent monitoring plan for the 325 Facility  

SciTech Connect

The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous 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 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, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination 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.

NONE

1998-12-31

352

Comprehensive facilities plan  

SciTech Connect

The Ernest Orlando Lawrence Berkeley National Laboratory`s Comprehensive Facilities Plan (CFP) document provides analysis and policy guidance for the effective use and orderly future development of land and capital assets at the Berkeley Lab site. The CFP directly supports Berkeley Lab`s role as a multiprogram national laboratory operated by the University of California (UC) for the Department of Energy (DOE). The CFP is revised annually on Berkeley Lab`s Facilities Planning Website. Major revisions are consistent with DOE policy and review guidance. Facilities planing is motivated by the need to develop facilities for DOE programmatic needs; to maintain, replace and rehabilitate existing obsolete facilities; to identify sites for anticipated programmatic growth; and to establish a planning framework in recognition of site amenities and the surrounding community. The CFP presents a concise expression of the policy for the future physical development of the Laboratory, based upon anticipated operational needs of research programs and the environmental setting. It is a product of the ongoing planning processes and is a dynamic information source.

NONE

1997-09-01

353

Medical Image Analysis Facility  

NASA Technical Reports Server (NTRS)

To improve the quality of photos sent to Earth by unmanned spacecraft. NASA's Jet Propulsion Laboratory (JPL) developed a computerized image enhancement process that brings out detail not visible in the basic photo. JPL is now applying this technology to biomedical research in its Medical lrnage Analysis Facility, which employs computer enhancement techniques to analyze x-ray films of internal organs, such as the heart and lung. A major objective is study of the effects of I stress on persons with heart disease. In animal tests, computerized image processing is being used to study coronary artery lesions and the degree to which they reduce arterial blood flow when stress is applied. The photos illustrate the enhancement process. The upper picture is an x-ray photo in which the artery (dotted line) is barely discernible; in the post-enhancement photo at right, the whole artery and the lesions along its wall are clearly visible. The Medical lrnage Analysis Facility offers a faster means of studying the effects of complex coronary lesions in humans, and the research now being conducted on animals is expected to have important application to diagnosis and treatment of human coronary disease. Other uses of the facility's image processing capability include analysis of muscle biopsy and pap smear specimens, and study of the microscopic structure of fibroprotein in the human lung. Working with JPL on experiments are NASA's Ames Research Center, the University of Southern California School of Medicine, and Rancho Los Amigos Hospital, Downey, California.

1978-01-01

354

A continuous silicon-coating facility  

NASA Technical Reports Server (NTRS)

Automatic continuous silicon-coating facility is used to process 100 by 10 cm graphite-coated ceramic substrates for silicon solar cells. Process reduces contamination associated with conventional dip-coating processes, improving material service life.

Butter, C.; Heaps, J. D.

1979-01-01

355

Real-time radiographic inspection facility  

NASA Technical Reports Server (NTRS)

A real time radiographic inspection facility has been developed for nondestructive evaluation applications. It consists of an X-ray source, an X-ray sensitive television imaging system, an electronic analog image processing system, and a digital image processing system. The digital image processing system is composed of a computer with the necessary software to drive the overall facility. Descriptions are given of the design strategy, the facility's components, and its current capabilities.

Roberts, E., Jr.

1977-01-01

356

CSAR 79-034 ADDENDUM 2, storing the man-basket in the process cell in 236-Z Building, Plutonium Finishing Plant/Plutonium Reclamation Facility  

SciTech Connect

The man-basket is stored in the Plutonium Reclamation Facility canyon area and this addendum reports on a technical evaluation for the storage inside the canyon to ensure consistency with the requirements of the Nuclear Criticality Safety Manual, WHC-CM-4-29.

Chiao, T.

1994-10-25

357

New Trends in Facility Asset Management.  

ERIC Educational Resources Information Center

Explains new, positive trends in facility asset management that encompasses greater acceptance and involvement of facility managers in the financial planning process, greater awareness of the need for maintenance, and facility administrators taking a greater role with business officers. The new climate for alternative renewal financing proposals…

Adams, Matt

2000-01-01

358

Cold vacuum drying facility design requirements  

SciTech Connect

This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

IRWIN, J.J.

1999-07-01

359

National Ignition Facility (NIF)  

NSDL National Science Digital Library

The National Ignition Facility (NIF) promotes its two main programs, Laser Science and Technology (LS&T) and Inertial Confinement Fusion (ICF), at this website. Individuals can view images, animations, and short movies of crystal growth, the Optics Processing Laboratory, Beamline Operations, and additional NIF-related projects and science. Researchers can discover the science and successes of NIF, including setting the world record for high-energy laser performance. Students can discover the fundamental concepts about laser operations.

360

MODELING THE IMPACT OF ELEVATED MERCURY IN DEFENSE WASTE PROCESSING FACILITY MELTER FEED ON THE MELTER OFF-GAS SYSTEM - PRELIMINARY REPORT  

SciTech Connect

The Defense Waste Processing Facility (DWPF) is currently evaluating an alternative Chemical Process Cell (CPC) flowsheet to increase throughput. It includes removal of the steam-stripping step, which would significantly reduce the CPC processing time and lessen the sampling needs. However, its downside would be to send 100% of the mercury that come in with the sludge straight to the melter. For example, the new mercury content in the Sludge Batch 5 (SB5) melter feed is projected to be 25 times higher than that in the SB4 with nominal steam stripping of mercury. This task was initiated to study the impact of the worst-case scenario of zero-mercury-removal in the CPC on the DWPF melter off-gas system. It is stressed that this study is intended to be scoping in nature, so the results presented in this report are preliminary. In order to study the impact of elevated mercury levels in the feed, it is necessary to be able to predict how mercury would speciate in the melter exhaust under varying melter operating conditions. A homogeneous gas-phase oxidation model of mercury by chloride was developed to do just that. The model contains two critical parameters pertaining to the partitioning of chloride among HCl, Cl, Cl{sub 2}, and chloride salts in the melter vapor space. The values for these parameters were determined at two different melter vapor space temperatures by matching the calculated molar ratio of HgCl (or Hg{sub 2}Cl{sub 2}) to HgCl{sub 2} with those measured during the Experimental-Scale Ceramic Melter (ESCM) tests run at the Pacific Northwest National Laboratory (PNNL). The calibrated model was then applied to the SB5 simulant used in the earlier flowsheet study with an assumed mercury stripping efficiency of zero; the molar ratio of Cl-to-Hg in the resulting melter feed was only 0.4, compared to 12 for the ESCM feeds. The results of the model run at the indicated melter vapor space temperature of 650 C (TI4085D) showed that due to excessive shortage of chloride, only 6% of the mercury fed is expected to get oxidized, mostly as HgCl, while the remaining mercury would exist either as elemental mercury vapor (90%) or HgO (4%). Noting that the measured chloride level in the SB5 qualification sample was an order of magnitude lower than that used in the SB5 simulant, the degree of chloride shortage will be even greater. As a result, the projected level of HgCl in the actual SB5 melter exhaust will be even lower than 6% of the total mercury fed, while that of elemental mercury is likely to be greater than 90%. The homogeneous oxidation of mercury in the off-gas was deemed to be of primary importance based on the postulation that mercury and other volatile salts form submicron sized aerosols upon condensation and thus remain largely in the gas stream downstream of the quencher where they can deposit in the off-gas lines, Steam-Atomized Scrubbers (SAS), and High-Efficiency Mist Eliminator (HEME). Formation of these submicron semi-volatile salts in the condensate liquid is considered to be unlikely, so the liquid phase reactions were considered to be less important. However, subsequent oxidation of mercury in the liquid phase in the off-gas system was examined in a simplified model of the off-gas condensate. It was found that the condensate chemistry was consistent with further oxidation of elemental mercury to Hg{sub 2}Cl{sub 2} and conversion of HgO to chlorides. The results were consistent with the available experimental data. It should also be noted that the model predictions presented in this report do not include any physically entrained solids, which typically account for much of the off-gas carryover on a mass basis. The high elemental mercury vapor content predicted at the DWPF Quencher inlet means that physically entrained solids could provide the necessary surface onto which elemental mercury vapor could condense, thereby coating the solids as well as the internal surfaces of the off-gas system with mercury. Clearly, there are many process benefits to be gained by removing the steam-stripping step from the CPC c

Zamecnik, J.; Choi, A.

2009-03-25

361

MODELING THE IMPACT OF ELEVATED MERCURY IN DEFENSE WASTE PROCESSING FACILITY MELTER FEED ON THE MELTER OFF-GAS SYSTEM-PRELIMINARY REPORT  

SciTech Connect

The Defense Waste Processing Facility (DWPF) is currently evaluating an alternative Chemical Process Cell (CPC) flowsheet to increase throughput. It includes removal of the steam-stripping step, which would significantly reduce the CPC processing time and lessen the sampling needs. However, its downside would be to send 100% of the mercury that comes in with the sludge straight to the melter. For example, the new mercury content in the Sludge Batch 5 (SB5) melter feed is projected to be 25 times higher than that in the SB4 with nominal steam stripping of mercury. This task was initiated to study the impact of the worst-case scenario of zero-mercury-removal in the CPC on the DWPF melter offgas system. It is stressed that this study is intended to be scoping in nature, so the results presented in this report are preliminary. In order to study the impact of elevated mercury levels in the feed, it is necessary to be able to predict how mercury would speciate in the melter exhaust under varying melter operating conditions. A homogeneous gas-phase oxidation model of mercury by chloride was developed to do just that. The model contains two critical parameters pertaining to the partitioning of chloride among HCl, Cl, Cl{sub 2}, and chloride salts in the melter vapor space. The values for these parameters were determined at two different melter vapor space temperatures by matching the calculated molar ratio of HgCl (or Hg{sub 2}Cl{sub 2}) to HgCl{sub 2} with those measured during the Experimental-Scale Ceramic Melter (ESCM) tests run at the Pacific Northwest National Laboratory (PNNL). The calibrated model was then applied to the SB5 simulant used in the earlier flowsheet study with an assumed mercury stripping efficiency of zero; the molar ratio of Cl-to-Hg in the resulting melter feed was only 0.4, compared to 12 for the ESCM feeds. The results of the model run at the indicated melter vapor space temperature of 650 C (TI4085D) showed that due to excessive shortage of chloride, only 6% of the mercury fed is expected to get oxidized, mostly as HgCl, while the remaining mercury would exist either as elemental mercury vapor (90%) or HgO (4%). Noting that the measured chloride level in the SB5 qualification sample was an order of magnitude lower than that used in the SB5 simulant, the degree of chloride shortage will be even greater. As a result, the projected level of HgCl in the actual SB5 melter exhaust will be even lower than 6% of the total mercury fed, while that of elemental mercury is likely to be greater than 90%. The homogeneous oxidation of mercury in the off-gas was deemed to be of primary importance based on the postulation that mercury and other volatile salts form submicron sized aerosols upon condensation and thus remain largely in the gas stream downstream of the quencher where they can deposit in the off-gas lines, Steam-Atomized Scrubbers (SAS), and High-Efficiency Mist Eliminator (HEME). Formation of these submicron semi-volatile salts in the condensate liquid is considered to be unlikely, so the liquid phase reactions were considered to be less important. However, subsequent oxidation of mercury in the liquid phase in the off-gas system was examined in a simplified model of the off-gas condensate. It was found that the condensate chemistry was consistent with further oxidation of elemental mercury to Hg{sub 2}Cl{sub 2} and conversion of HgO to chlorides. The results were consistent with the available experimental data. It should also be noted that the model predictions presented in this report do not include any physically entrained solids, which typically account for much of the off-gas carryover on a mass basis. The high elemental mercury vapor content predicted at the DWPF Quencher inlet means that physically entrained solids could provide the necessary surface onto which elemental mercury vapor could condense, thereby coating the solids as well as the internal surfaces of the off-gas system with mercury. Clearly, there are many process benefits to be gained by removing the steam-stripping step from the CPC c

Zamecnik, J.; Choi, A.

2010-08-18

362

Scaling properties of urban facilities  

NASA Astrophysics Data System (ADS)

Two measurements are employed to quantitatively investigate the scaling properties of the spatial distribution of urban facilities: the K function [whose derivative gives the radial distribution function ? (t ) =K'(t ) /2 ? t ] by number counting and the variance-mean relationship by the method of expanding bins. The K function and the variance-mean relationship are both power functions. This means that the spatial distributions of urban facilities are scaling invariant. Further analysis of more data (which includes eight types of facilities in 37 major Chinese cities) shows that the the power laws broadly hold for all combinations of facilities and cities. A double stochastic process (DSP) model is proposed as a mathematical mechanism by which spatial point patterns can be generated that resemble the actual distribution of urban facilities both qualitatively and quantitatively. Simulation of the DSP yields a better agreement with the urban data than the correlated percolation model.

Wu, Liang; Yan, Xin; Du, Jiang

2014-12-01

363

Cathode Life Test Facility  

NASA Astrophysics Data System (ADS)

The Cathode Life Test Facility (CLTF) has been in operation for ten years and has tested ten different cathode types for a total of approximately 2.0 million hours of life test data. As part of the defense management review (DMR) process, Rome Laboratory (RL) has eliminated internal research efforts pertaining to cathode life testing. Based on this directive, the CLTF was moved to the Naval Surface Warfare Center (NSWC) at Crane, Indiana. This report summarizes the process of moving the CLTF from RL to the NSWC.

Jardieu, Ronald J.

1994-10-01

364

Lightning Protection for Explosive Facilities  

SciTech Connect

Lawrence Livermore National Laboratory funds construction of lightning protection systems to protect explosive processing and storage facilities. This paper provides an intuitive understanding of the lighting risks and types of lightning protection available. Managers can use this information to decide if limited funds should be spent constructing a lightning protection system for their own facilities. This paper answers the following questions: (1) Why do you need lightning protection systems? (2) How do lightning protection systems work? and (3) Why are there no documented cases of lightning problems at existing explosive facilities?

Ong, M

2001-12-01

365

Supporting NASA Facilities Through GIS  

NASA Technical Reports Server (NTRS)

The NASA GIS Team supports NASA facilities and partners in the analysis of spatial data. Geographic Information System (G[S) is an integration of computer hardware, software, and personnel linking topographic, demographic, utility, facility, image, and other geo-referenced data. The system provides a graphic interface to relational databases and supports decision making processes such as planning, design, maintenance and repair, and emergency response.

Ingham, Mary E.

2000-01-01

366

Stanford Nanofabrication Facility  

NSDL National Science Digital Library

The purpose of the Stanford Nanofabrication Facility (SNF) is to âÂÂprovide researchers with effective and efficient access to advanced nanofabrication equipment and expertise.â The site serves as a network for researchers, and even provides remote access via a live microscope and webcams, for researchers who cannot access the equipment in person. Although there are fees associated with becoming a labmember (this pertains to researchers who wish to use the lab facilities, or have a technician work on a project for them), some of the still images are made available, and there are a variety of resources on nanofabrication equipment, processes and materials also available for general use. Be sure to check out the âÂÂContact Mask Design Principles Tutorialâ in the âÂÂProcessesâ section in order to gain understanding of some of the technical aspects of nanofabrication.

2007-09-17

367

Digital image processing  

NASA Technical Reports Server (NTRS)

The Federal Systems Division of IBM has developed an image processing facility to experimentally process, view, and record digital image data. This facility has been used to support LANDSAT digital image processing investigations and advanced image processing research and development. A brief description of the facility is presented, some techniques that have been developed to correct the image data are discussed, and some results obtained by users of the facility are described.

Bernstein, R.; Ferneyhough, D. G., Jr.

1975-01-01

368

Breadboard Facility  

NASA Technical Reports Server (NTRS)

In the sixties, Chrysler was NASA's prime contractor for the Saturn I and IB test launch vehicles. The company installed and operated at Huntsville what was known as the Saturn I/IB Development Breadboard Facility. "Breadboard," means an array of electrical and electronic equipment for performing a variety of development and test functions. This work gave Chrysler a broad capability in computerized testing to assure quality control in development of solid-state electronic systems. Today that division is manufacturing many products not destined for NASA, most of them being associated with the company's automotive line. A major project is production and quality-control testing of the "lean-burn" engine, one that has a built-in Computer to control emission timing, and allow the engine to run on a leaner mixture of fuel and air. Other environment-related products include vehicle emission analyzers. The newest of the line is an accurate, portable solid state instrument for testing auto exhaust gases. The exhaust analyzers, now being produced for company dealers and for service

1977-01-01

369

Succinonitrile Purification Facility  

NASA Technical Reports Server (NTRS)

The Succinonitrile (SCN) Purification Facility provides succinonitrile and succinonitrile alloys to several NRA selected investigations for flight and ground research at various levels of purity. The purification process employed includes both distillation and zone refining. Once the appropriate purification process is completed, samples are characterized to determine the liquidus and/or solidus temperature, which is then related to sample purity. The lab has various methods for measuring these temperatures with accuracies in the milliKelvin to tenths of milliKelvin range. The ultra-pure SCN produced in our facility is indistinguishable from the standard material provided by NIST to well within the stated +/- 1.5mK of the NIST triple point cells. In addition to delivering material to various investigations, our current activities include process improvement, characterization of impurities and triple point cell design and development. The purification process is being evaluated for each of the four vendors to determine the efficacy of each purification step. We are also collecting samples of the remainder from distillation and zone refining for analysis of the constituent impurities. The large triple point cells developed will contain SCN with a melting point of 58.0642 C +/- 1.5mK for use as a calibration standard for Standard Platinum Resistance Thermometers (SPRTs).

2003-01-01

370

{sup 99m}Tc generators for clinical use based on zirconium molybdate gel and (n, gamma) produced {sup 99}Mo: Indian experience in the development and deployment of indigenous technology and processing facilities  

SciTech Connect

The Indian pursuit of gel generator technology for {sup 99m}Tc was driven mainly by three considerations, namely, (i) well-established and ease of reliable production of (n, gamma)-based {sup 99}Mo in several tens of GBq quantities in the research reactors in Trombay/Mumbai, India, (ii) need for relatively low-cost alternate technology to replace the solvent (MEK) extraction generator system in use in India since 1970s and (iii) minimize dependency on weekly import of fission-produced {sup 99}Mo raw material required for alumina column generator. Extensive investigations on process standardisation for zirconium molybdate gel (ZMG) led to a steady progress, achieved both in terms of process technology and final performance of {sup 99m}Tc gel generators. The {sup 99m}Tc final product purity from the Indian gel system was comparable to that obtained from the gold-standard alumina column generators. Based on the feasibility established for reliable small-scale production, as well as satisfactory clinical experience with a number of gel generators used in collaborating hospital radiopharmacies, full-fledged mechanised processing facilities for handling up to 150 g of ZMG were set up. The indigenous design and development included setting up of shielded plant facilities with pneumatic-driven as well as manual controls and special gadgets such as, microwave heating of the zirconium molybdate cake, dispenser for gel granules, loading of gel columns into pre-assembled generator housing etc. Formal review of the safety features was carried out by the regulatory body and stage-wise clearance for processing low and medium level {sup 99}Mo activity was granted. Starting from around 70 GBq {sup 99}Mo handling, the processing facilities have since been successfully operated at a level of 740 GBq {sup 99}Mo, twice a month. In all 18 batches of gel have been processed and 156 generators produced. The individual generator capacity was 15 to 30 GBq with an elution yield of nearly 75%. 129 generators were supplied to 11 user hospitals and the estimated number of clinical studies done is well over 5000. The salient aspects of the Indian experience have been reported in many a forum and shared with the IAEA through the on-going CRP. The detailed process know-how is available for technology transfer from BRIT, India. (author)

Saraswathy, P.; Dey, A.C.; Sarkar, S.K.; Kothalkar, C.; Naskar, P.; Arjun, G.; Arora, S.S.; Kohli, A.K. [Board of Radiation and Isotope Technology (BRIT), BARC Vashi Complex, Navi Mumbai 400705 (India); Meera, V.; Venugopal, V. [Radiochemistry and Isotope Group, Bhabha Atomic Research Centre (BARC), Mumbai 400085 (India); Ramamoorthy, N. [Division of Physical and Chemical Sciences, International Atomic Energy Agency (IAEA), A-1400 Vienna (Austria)

2008-07-15

371

Heavy oil recovery process: Conceptual engineering of a downhole methanator and preliminary estimate of facilities cost for application to North Slope Alaska  

SciTech Connect

The West Sak (Upper Cretaceous) sands, overlaying the Kuparuk field, would rank among the largest known oil fields in the US, but technical difficulties have so far prevented its commercial exploitation. Steam injection is the most successful and the most commonly-used method of heavy oil recovery, but its application to the West Sak presents major problems. Such difficulties may be overcome by using a novel approach, in which steam is generated downhole in a catalytic Methanator, from Syngas made at the surface from endothermic reactions (Table 1). The Methanator effluent, containing steam and soluble gases resulting from exothermic reactions (Table 1), is cyclically injected into the reservoir by means of a horizontal drainhole while hot produced fluids flow form a second drainhole into a central production tubing. The downhole reactor feed and BFW flow downward to two concentric tubings. The large-diameter casing required to house the downhole reactor assembly is filled above it with Arctic Pack mud, or crude oil, to further reduce heat leaks. A quantitative analysis of this production scheme for the West Sak required a preliminary engineering of the downhole and surface facilities and a tentative forecast of well production rates. The results, based on published information on the West Sak, have been used to estimate the cost of these facilities, per daily barrel of oil produced. A preliminary economic analysis and conclusions are presented together with an outline of future work. Economic and regulatory conditions which would make this approach viable are discussed. 28 figs.

Gondouin, M.

1991-10-31

372

New hydrofracture facility at ORNL  

SciTech Connect

The new hydrofracture facility has been designed and built about 250 m south of the existing facility. At the new location, the disposal zone is about 60 m deeper, while the geology is similar in other respects. A site-proof test was made at the new site to verify its suitability for waste disposal by shale fracturing. An environmental impact statement, written to cover the operations of the facility, concluded that the overall impact would be beneficial. The new facility has improved shielding and containment so that wastes of higher specific activity can be handled. Process modifications were made to permit the pumping, mixing, and injection of waste slurries. The operating pressures and flow rates for the new facility are similar to those of the existing facility. The dry-solids handling equipment, which has been a source of chronic difficulty in the existing facility, has been improved so that the flow of solids to the mixer is smooth and controlled. The process instrumentation has been improved by the incorporation of a weigh-belt feeder to measure the flow of solids more precisely. Improved mix ratio indicators have been installed to determine and display the ratio of the weight of solids and the volume of liquid going to the mixer, which should help maintain the rather narrow limits required for good process control. Construction of the new facility has been completed; a preoperating check of all equipment has been made; and the necessary approvals are being obtained. Injection of the first batch of waste is scheduled for June 1982.

Weeren, H.O.; Dunwoody, N.E.; Lasher, L.C.; Godsey, A.R.

1982-01-01

373

Facility Effluent Monitoring Plan for the uranium trioxide facility  

SciTech Connect

A facility effluent monitoring plan is required by the US Department of Energy in DOE 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-0438-01. 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 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 it must be updated at a minimum of every three years.

Lohrasbi, J.; Johnson, D.L. [Westinghouse Hanford Co., Richland, WA (United States); De Lorenzo, D.S. [Los Alamos Technical Associates, Inc., NM (United States)

1993-12-01

374

Facility Focus: Sports and Recreation Facilities.  

ERIC Educational Resources Information Center

Examines projects that demonstrate three different commitments administrators make to their athletic facilities: convenience; excellence; and comfort. Projects discussed involve a fitness center, a football stadium, and a multi-sport indoor practice facility. (GR)

College Planning & Management, 2000

2000-01-01

375

R2 REGULATED FACILITIES  

EPA Science Inventory

The Facility Registry System (FRS) is a centrally managed database that identifies facilities, sites or places subject to environmental regulations or of environmental interest. FRS creates high-quality, accurate, and authoritative facility identification records through rigorous...

376

Nursing Facilities (Medicaid)  

MedlinePLUS

Nursing Facilities (NF) Nursing Facility Services are provided by Medicaid certified nursing homes, which primarily provide three ... provided by Medicaid or other state agencies. Where Nursing Facility Services are provided Medicaid coverage of Nursing ...

377

SERAPH facility capabilities  

SciTech Connect

The SERAPH (Solar Energy Research and Applications in Process Heat) facility addresses technical issues concerning solar thermal energy implementation in industry. Work will include computer predictive modeling (refinement and validation), system control and evaluation, and the accumulation of operation and maintenance experience. Procedures will be consistent (to the extent possible) with those of industry. SERAPH has four major components: the solar energy delivery system (SEDS); control and data acquisition (including sequencing and emergency supervision); energy distribution system (EDS); and areas allocated for storage development and load devices.

Castle, J.; Su, W.

1980-06-01

378

Solar observing facilities  

NASA Astrophysics Data System (ADS)

An overview is given of current and planned ground-based solar telescopes and instruments, balloon-borne and suborbital solar telescopes, and solar and heliospheric space missions. These observing facilities operate in all areas of solar physics, from the solar interior to interplanetary space and from regimes of high energy to observations requiring high resolution. The next generation of solar telescopes and instruments promise us the ability to investigate solar processes on their fundamental scales, whether sub-arc second or global in nature.

Fleck, B.; Keller, C. U.

379

Evaluation of existing United States` facilities for use as a mixed-oxide (MOX) fuel fabrication facility for plutonium disposition  

SciTech Connect

A number of existing US facilities were evaluated for use as a mixed-oxide fuel fabrication facility for plutonium disposition. These facilities include the Fuels Material Examination Facility (FMEF) at Hanford, the Washington Power Supply Unit 1 (WNP-1) facility at Hanford, the Barnwell Nuclear Fuel Plant (BNFP) at Barnwell, SC, the Fuel Processing Facility (FPF) at Idaho National Engineering Laboratory (INEL), the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), and the P-reactor at the Savannah River Site (SRS). The study consisted of evaluating each facility in terms of available process space, available building support systems (i.e., HVAC, security systems, existing process equipment, etc.), available regional infrastructure (i.e., emergency response teams, protective force teams, available transportation routes, etc.), and ability to integrate the MOX fabrication process into the facility in an operationally-sound manner that requires a minimum amount of structural modifications.

Beard, C.A.; Buksa, J.J.; Chidester, K.; Eaton, S.L.; Motley, F.E.; Siebe, D.A.

1995-12-31

380

FMIT facility control system  

SciTech Connect

The control system for the Fusion Materials Irradiation Test (FMIT) Facility, under construction at Richland, Washington, uses current techniques in distributed processing to achieve responsiveness, maintainability and reliability. Developmental experience with the system on the FMIT Prototype Accelerator (FPA) being designed at the Los Alamos National Laboratory is described as a function of the system's design goals and details. The functional requirements of the FMIT control system dictated the use of a highly operator-responsive, display-oriented structure, using state-of-the-art console devices for man-machine communications. Further, current technology has allowed the movement of device-dependent tasks into the area traditionally occupied by remote input-output equipment; the system's dual central process computers communicate with remote communications nodes containing microcomputers that are architecturally similar to the top-level machines. The system has been designed to take advantage of commercially available hardware and software.

Suyama, R.M.; Machen, D.R.; Johnson, J.A.

1981-01-01

381

Fourth Calcined Solids Storage Facility. Final safety analysis report  

Microsoft Academic Search

This safety analysis report describes the Fourth Calcined Solids Storage Facility and presents the results of a safety evaluation of the facility including a design basis accident. The Idaho Chemical Processing Plant (ICPP) is a multi-purpose facility for recovering enriched U-235 from a wide variety of spent reactor fuels. Solvent extraction processes employed in recovery of fissile materials generate radioactive

Schindler

1980-01-01

382

National Biomedical Tracer Facility: Project definition study  

SciTech Connect

The Los Alamos National Laboratory is an ideal institution and New Mexico is an ideal location for siting the National Biomedical Tracer Facility (NBTF). The essence of the Los Alamos proposal is the development of two complementary irradiation facilities that combined with our existing radiochemical processing hot cell facilities and waste handling and disposal facilities provide a low cost alternative to other proposals that seek to satisfy the objectives of the NBTF. We propose the construction of a 30 MeV cyclotron facility at the site of the radiochemical facilities, and the construction of a 100 MeV target station at LAMPF to satisfy the requirements and objectives of the NBTF. We do not require any modifications to our existing radiochemical processing hot cell facilities or our waste treatment and disposal facilities to accomplish the objectives of the NBTF. The total capital cost for the facility defined by the project definition study is $15.2 M. This cost estimate includes $9.9 M for the cyclotron and associated facility, $2.0 M for the 100 MeV target station at LAMPF, and $3.3 M for design.

Heaton, R.; Peterson, E. [Los Alamos National Lab., NM (United States); Smith, P. [Smith (P.A.) Concepts and Designs (United States)

1995-05-31

383

Wastewater Disposal Facility in Colorado  

USGS Multimedia Gallery

Oilfield waste arrives by tanker truck at a wastewater disposal facility near Platteville, Colo. After removal of solids and oil, the wastewater is injected into a deep well for permanent storage underground. This disposal process has the potential to trigger earthquakes, but very few wastewater dis...

384

Facility management in German hospitals.  

PubMed

Facility management and optimum building management offer for hospitals a chance to reduce costs and to increase quality, process sequences, employee motivation and customer satisfaction. Some years ago simple services such as cleaning, catering or laundry were outsourced. Now, German hospitals progress to more complex fields such as building and medical technology, clinical support processes such as pharmacy, central laboratory and sterilization, goods and logistics services. PMID:11066999

Gudat, H

2000-04-01

385

Future-oriented maintenance strategy based on automated processes is finding its way into large astronomical facilities at remote observing sites  

NASA Astrophysics Data System (ADS)

With expanding sizes and increasing complexity of large astronomical observatories on remote observing sites, the call for an efficient and recourses saving maintenance concept becomes louder. The increasing number of subsystems on telescopes and instruments forces large observatories, like in industries, to rethink conventional maintenance strategies for reaching this demanding goal. The implementation of full-, or semi-automatic processes for standard service activities can help to keep the number of operating staff on an efficient level and to reduce significantly the consumption of valuable consumables or equipment. In this contribution we will demonstrate on the example of the 80 Cryogenic subsystems of the ALMA Front End instrument, how an implemented automatic service process increases the availability of spare parts and Line Replaceable Units. Furthermore how valuable staff recourses can be freed from continuous repetitive maintenance activities, to allow focusing more on system diagnostic tasks, troubleshooting and the interchanging of line replaceable units. The required service activities are decoupled from the day-to-day work, eliminating dependencies on workload peaks or logistic constrains. The automatic refurbishing processes running in parallel to the operational tasks with constant quality and without compromising the performance of the serviced system components. Consequentially that results in an efficiency increase, less down time and keeps the observing schedule on track. Automatic service processes in combination with proactive maintenance concepts are providing the necessary flexibility for the complex operational work structures of large observatories. The gained planning flexibility is allowing an optimization of operational procedures and sequences by considering the required cost efficiency.

Silber, Armin; Gonzalez, Christian; Pino, Francisco; Escarate, Patricio; Gairing, Stefan

2014-08-01

386

Space Power Facility Reverberation Chamber Calibration Report  

NASA Technical Reports Server (NTRS)

This document describes the process and results of calibrating the Space Environmental Test EMI Test facility at NASA Plum Brook Space Power Facility according to the specifications of IEC61000-4-21 for susceptibility testing from 100 MHz to 40 GHz. The chamber passed the field uniformity test, in both the empty and loaded conditions, making it the world's largest Reverberation Chamber.

Lewis, Catherine C.; Dolesh, Robert J.; Garrett, Michael J.

2014-01-01

387

Assessment of the quality of groundwater and the Little Wind River in the area of a former uranium processing facility on the Wind River Reservation, Wyoming, 1987 through 2010  

USGS Publications Warehouse

In 2010, the U.S Geological Survey (USGS), in cooperation with the Wind River Environmental Quality Commission (WREQC), began an assessment of the effectiveness of the existing monitoring network at the Riverton, Wyoming, Uranium Mill Tailings Remedial Action (UMTRA) site. The USGS used existing data supplied by the U.S. Department of Energy (DOE). The study was to determine (1) seasonal variations in the direction of groundwater flow in the area of the former uranium processing facility toward the Little Wind River, (2) the extent of contaminated groundwater among the aquifers and between the aquifers and the Little Wind River, (3) whether current monitoring is adequate to establish the effectiveness of natural attenuation for the contaminants of concern, and (4) the influence of groundwater discharged from the sulfuric-acid plant on water quality in the Little Wind River.

Ranalli, Anthony J.; Naftz, David L.

2014-01-01

388

VISAR diagnostic at LIL facility  

NASA Astrophysics Data System (ADS)

A Velocity Interferometer for Any Reflector (VISAR) [1, 2] and a Streaked Optical Pyrometer (SOP) [3] were implemented on the "Ligne integration Laser" (LIL) facility. Spatial resolution as good as 10 ?m in the target plane and velocity resolution as good as 0.1 km/s can be achieved. Several campaigns were performed in 2010 involving various experimental setups and physical processes: Boron EOS, Pre-compress H2 with special setup of diamond anvil cell and Shock coalescence. This feedback will be of a great help for the Laser Mégajoule facility (LMJ) VISAR design.

Darbon, S.; Duval, A.; Masclet-Gobin, I.; Marchet, B.; Brygoo, S.; Courtois, C.; Debras, G.; Patissou, L.; Parreault, R.; Lobios, O.; Mangeant, M.; Parrot, S.; Hartmann, O.

2013-11-01

389

Facility effluent monitoring plan for the tank farms facilities  

SciTech Connect

A facility effluent monitoring plan is required by the US Department of Energy 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 specific guidelines. 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 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 it must be updated as a minimum every three years.

Bachand, D.D.; Crummel, G.M.

1995-05-01

390

Evapotranspiration And Geochemical Controls On Groundwater Plumes At Arid Sites: Toward Innovative Alternate End-States For Uranium Processing And Tailings Facilities  

SciTech Connect

Management of legacy tailings/waste and groundwater contamination are ongoing at the former uranium milling site in Tuba City AZ. The tailings have been consolidated and effectively isolated using an engineered cover system. For the existing groundwater plume, a system of recovery wells extracts contaminated groundwater for treatment using an advanced distillation process. The ten years of pump and treat (P&T) operations have had minimal impact on the contaminant plume – primarily due to geochemical and hydrological limits. A flow net analysis demonstrates that groundwater contamination beneath the former processing site flows in the uppermost portion of the aquifer and exits the groundwater as the plume transits into and beneath a lower terrace in the landscape. The evaluation indicates that contaminated water will not reach Moenkopi Wash, a locally important stream. Instead, shallow groundwater in arid settings such as Tuba City is transferred into the vadose zone and atmosphere via evaporation, transpiration and diffuse seepage. The dissolved constituents are projected to precipitate and accumulate as minerals such as calcite and gypsum in the deep vadose zone (near the capillary fringe), around the roots of phreatophyte plants, and near seeps. The natural hydrologic and geochemical controls common in arid environments such as Tuba City work together to limit the size of the groundwater plume, to naturally attenuate and detoxify groundwater contaminants, and to reduce risks to humans, livestock and the environment. The technical evaluation supports an alternative beneficial reuse (“brownfield”) scenario for Tuba City. This alternative approach would have low risks, similar to the current P&T scenario, but would eliminate the energy and expense associated with the active treatment and convert the former uranium processing site into a resource for future employment of local citizens and ongoing benefit to the Native American Nations.

Looney, Brian B.; Denham, Miles E.; Eddy-Dilek, Carol A.; Millings, Margaret R.; Kautsky, Mark

2014-01-08

391

Facility issues of the 1990s.  

PubMed

In the 1980s there was overbuilding of facilities of all kinds, including facilities with acute psychiatric beds. A subsequent decrease in patient days in most of these hospitals caused significant excess capacity. With all the problems now confronting mental healthcare facilities, it may be difficult to focus attention on hospital buildings; however, intelligent planning for the use of these large investments may be part of an overall solution. An awareness of problems facing our facility managers should enhance the planning process and minimize unwanted surprises. PMID:10122626

Williams, W E

1991-01-01

392

Mixed Waste Management Facility  

SciTech Connect

The DOE has developed a National Mixed Waste Strategic Plan which calls for the construction of 2 to 9 mixed waste treatment centers in the Complex in the near future. LLNL is working to establish an integrated mixed waste technology development and demonstration system facility, the Mixed Waste Management Facility (MWMF), to support the DOE National Mixed Waste Strategic Plan. The MWMF will develop, demonstrate, test, and evaluate incinerator-alternatives which will comply with regulations governing the treatment and disposal of organic mixed wastes. LLNL will provide the DOE with engineering data for design and operation of new technologies which can be implemented in their mixed waste treatment centers. MWMF will operate under real production plant conditions and process samples of real LLNL mixed waste. In addition to the destruction of organic mixed wastes, the development and demonstration will include waste feed preparation, material transport systems, aqueous treatment, off-gas treatment, and final forms, thus making it an integrated ``cradle to grave`` demonstration. Technologies from offsite as well as LLNL`s will be tested and evaluated when they are ready for a pilot scale demonstration, according to the needs of the DOE.

Brummond, W.; Celeste, J.; Steenhoven, J.

1993-08-01

393

Size and shape controllable synthesis and luminescent properties of BaGdF5:Ce3+/Ln3+ (Ln = Sm, Dy, Eu, Tb) nano/submicrocrystals by a facile hydrothermal process.  

PubMed

In this paper, we present a facile and environmentally-friendly hydrothermal process to synthesize BaGdF(5): 2.5 mol% Ce(3+)/2.5 mol% Ln(3+) (Ln = Sm, Dy, Eu and Tb) nano/submicroparticles. X-ray diffraction (XRD), transmission electron microscopy (TEM), scanning electron microscopy (SEM), as well as photoluminescence (PL) spectra are used to characterize the resulting samples. The size, shape, and composition of the products could be tuned just by varying the organic additives and the pH values of the initial reaction solutions. The morphologies for the products include nanospheres, submicrospheres, peanut-like particles, as well as the spindle-like and star-like aggregates. Moreover, the size of the samples can be tuned from 50 nm to 150 nm. Additionally, we systematically investigate the luminescence properties of different lanthanide ions in BaGdF(5) host. Under single-wavelength excitation at 260 nm, the samples doped with different lanthanide ions show intensive multicolor visible emissions depending on the doped Ln(3+) ions. The luminescence process can be attributed to the strong absorption of UV irradiation by Ce(3+) ions, followed by energy transfer to Gd(3+) ions, from which the energy is transferred to Ln(3+), resulting in the emission from the luminescent Ln(3+) centers. The Gd(3+) ions play an intermediate role in this process. PMID:21505713

Yang, Dongmei; Kang, Xiaojiao; Shang, Mengmeng; Li, Guogang; Peng, Chong; Li, Chunxia; Lin, Jun

2011-06-01

394

Size and shape controllable synthesis and luminescent properties of BaGdF5:Ce3+/Ln3+ (Ln = Sm, Dy, Eu, Tb) nano/submicrocrystals by a facile hydrothermal process  

NASA Astrophysics Data System (ADS)

In this paper, we present a facile and environmentally-friendly hydrothermal process to synthesize BaGdF5: 2.5 mol% Ce3+/2.5 mol% Ln3+ (Ln = Sm, Dy, Eu and Tb) nano/submicroparticles. X-ray diffraction (XRD), transmission electron microscopy (TEM), scanning electron microscopy (SEM), as well as photoluminescence (PL) spectra are used to characterize the resulting samples. The size, shape, and composition of the products could be tuned just by varying the organic additives and the pH values of the initial reaction solutions. The morphologies for the products include nanospheres, submicrospheres, peanut-like particles, as well as the spindle-like and star-like aggregates. Moreover, the size of the samples can be tuned from 50 nm to 150 nm. Additionally, we systematically investigate the luminescence properties of different lanthanide ions in BaGdF5 host. Under single-wavelength excitation at 260 nm, the samples doped with different lanthanide ions show intensive multicolor visible emissions depending on the doped Ln3+ ions. The luminescence process can be attributed to the strong absorption of UV irradiation by Ce3+ ions, followed by energy transfer to Gd3+ ions, from which the energy is transferred to Ln3+, resulting in the emission from the luminescent Ln3+ centers. The Gd3+ ions play an intermediate role in this process.

Yang, Dongmei; Kang, Xiaojiao; Shang, Mengmeng; Li, Guogang; Peng, Chong; Li, Chunxia; Lin, Jun

2011-06-01

395

40 CFR 60.640 - Applicability and designation of affected facilities.  

Code of Federal Regulations, 2010 CFR

...for Onshore Natural Gas Processing: SO2 Emissions...affected facilities that process natural gas: each sweetening unit, and each sweetening...located onshore which process natural gas produced from either...subpart do not apply to sweetening facilities...

2010-07-01

396

Facile preparation of carbon coated magnetic Fe{sub 3}O{sub 4} particles by a combined reduction/CVD process  

SciTech Connect

Graphical abstract: Magnetic carbon coated Fe{sub 3}O{sub 4} particles are prepared by a one step combined reduction of Fe{sub 2}O{sub 3} together with a CVD process of using methane. Analyses show that the Fe{sub 2}O{sub 3} is reduced by methane to produce mainly Fe{sub 3}O{sub 4} particles coated with amorphous carbon. These materials can be separated into two fractions by simple dispersion in water and can be used as adsorbents, catalyst supports and rapid coagulation systems. Research highlights: {yields} Magnetic Fe{sub 3}O{sub 4} particles coated with a very thin layer of amorphous carbon (4 wt%). {yields} Combined reduction of Fe{sub 2}O{sub 3} with a Chemical Vapor Deposition process using methane. {yields} Nanoparticles with an average size of 100-200 nm. {yields} Uses as adsorbent, catalyst support and rapid coagulation systems. -- Abstract: In this work, we report a simple method for the preparation of magnetic carbon coated Fe{sub 3}O{sub 4} particles by a single step combined reduction of Fe{sub 2}O{sub 3} together with a Chemical Vapor Deposition process using methane. The temperature programmed reaction monitored by Moessbauer, X-ray Diffraction and Raman analyses showed that Fe{sub 2}O{sub 3} is directly reduced by methane at temperatures between 600 and 900 {sup o}C to produce mainly Fe{sub 3}O{sub 4} particles coated with up to 4 wt% of amorphous carbon. These magnetic materials can be separated into two fractions by simple dispersion in water, i.e., a settled material composed of large magnetic particles and a suspended material composed of nanoparticles with an average size of 100-200 nm as revealed by Scanning Electron Microscopy and High-resolution Transmission Electron Microscopy. Different uses for these materials, e.g., adsorbents, catalyst supports, rapid coagulation systems, are proposed.

Tristao, Juliana C.; Oliveira, Aline A.S. [Departamento de Quimica, Universidade Federal de Minas Gerais, Belo Horizonte-MG, 31270-901 (Brazil)] [Departamento de Quimica, Universidade Federal de Minas Gerais, Belo Horizonte-MG, 31270-901 (Brazil); Ardisson, Jose D. [Laboratorio de Fisica Aplicada, CDTN, Belo Horizonte, MG 30123-970 (Brazil)] [Laboratorio de Fisica Aplicada, CDTN, Belo Horizonte, MG 30123-970 (Brazil); Dias, Anderson [Departamento de Quimica, Universidade Federal de Ouro Preto, Ouro Preto-MG, 35400-000 (Brazil)] [Departamento de Quimica, Universidade Federal de Ouro Preto, Ouro Preto-MG, 35400-000 (Brazil); Lago, Rochel M., E-mail: rochel@ufmg.br [Departamento de Quimica, Universidade Federal de Minas Gerais, Belo Horizonte-MG, 31270-901 (Brazil)

2011-05-15

397

A facile and rapid process to fabricate platinum counter electrode in dye-sensitized solar cell using nanosecond pulsed laser sintering at room temperature.  

PubMed

To fabricate the platinum (Pt) counter electrode in dye-sensitized solar cells (DSSCs), rapid and low sintering process was carried out using nanosecond pulsed laser sintering (LS) method based on third harmonic (355 nm) of an Nd:YAG laser at room temperature. The surface morphology of LS-Pt on fluorine-doped tin oxide (FTO) electrode showed thin and compact structure, consisting of particles size of - 10-30 nm and thickness of below 30 nm. The DSSCs with the LS-Pt/FTO counter electrodes displayed the power conversion efficiency of 4.4% with short-circuit current = 9.07 mA/cm2, open-circuit voltage = 0.79 V and fill factor = 61.3. PMID:24758023

Kang, Tae Yeon; Yoo, Kicheon; Lee, Jin Ah; Lee, Wonjoo; Kim, Kyungkon; Lee, Doh-Kwon; Kim, Honggon; Ko, Min Jae

2014-07-01

398

9 CFR 590.538 - Defrosting facilities.  

Code of Federal Regulations, 2010 CFR

... FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.538 Defrosting...

2010-01-01

399

9 CFR 590.534 - Freezing facilities.  

Code of Federal Regulations, 2010 CFR

... FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION INSPECTION OF EGGS AND EGG PRODUCTS (EGG PRODUCTS INSPECTION ACT) Sanitary, Processing, and Facility Requirements § 590.534 Freezing...

2010-01-01

400

9 CFR 149.6 - Slaughter facilities.  

Code of Federal Regulations, 2014 CFR

...footnote 4). (3) Testing sample size and frequency . Process-verification...minimum requirements relating to sample size and frequency: (i) Slaughter...Certification Slaughter Facility Sample Size Determination Table on the...

2014-01-01

401

9 CFR 149.6 - Slaughter facilities.  

Code of Federal Regulations, 2011 CFR

...footnote 4). (3) Testing sample size and frequency . Process-verification...minimum requirements relating to sample size and frequency: (i) Slaughter...Certification Slaughter Facility Sample Size Determination Table on the...

2011-01-01

402

9 CFR 149.6 - Slaughter facilities.  

Code of Federal Regulations, 2010 CFR

...footnote 4). (3) Testing sample size and frequency . Process-verification...minimum requirements relating to sample size and frequency: (i) Slaughter...Certification Slaughter Facility Sample Size Determination Table on the...

2010-01-01

403

9 CFR 149.6 - Slaughter facilities.  

Code of Federal Regulations, 2013 CFR

...footnote 4). (3) Testing sample size and frequency . Process-verification...minimum requirements relating to sample size and frequency: (i) Slaughter...Certification Slaughter Facility Sample Size Determination Table on the...

2013-01-01

404

9 CFR 149.6 - Slaughter facilities.  

Code of Federal Regulations, 2012 CFR

...footnote 4). (3) Testing sample size and frequency . Process-verification...minimum requirements relating to sample size and frequency: (i) Slaughter...Certification Slaughter Facility Sample Size Determination Table on the...

2012-01-01

405

BioChroma – A New and Patented Technology for Processing Radioactive Wastewater from Nuclear Medicine Therapy Facilities in Hospitals and Clinics  

PubMed Central

After undergoing radionuclide therapy, patients generate wastewater with a considerable amount of radioactivity, which can reach levels of as much as 90% of the administered dose. Due to the risk of accumulation after discharge into the sewer, it is advisable to collect this effluent for its treatment prior to final discharge. Delay and decay (natural decomposition of the isotope) is the most commonly used technical method of abating radioactive iodine, but it is frequently criticized as being complex and very expensive. BioChroma is a technology that has been developed as an alternative to these complicated and expensive systems. This paper describes this new technology and presents, as an example, a system that was installed and successfully commissioned in the middle of 2008 in a nuclear medicine ward with 12 beds in Stuttgart (Germany). Based on existing legislation, the responsible authorities and the company that operated the hospital agreed on a maximum activity level of 5 Bq/l. If a typical delay and decay system would have been installed, the 180 m3 treatment plant that was already available in the hospital cellar would have to be extended by additional 150 m3. By implementing the patented BioChroma process, the space requirements were reduced by 75%. For instance, since the new system was integrated into the existing installation, tanks accounting for 120 m³ could be used as buffering volume in the new wastewater treatment plant. The operation of the referred plant is currently producing very good results with values below the specified limit of 5 Bq/l for the isotope 131I. In addition, 90Y has been reported to be eliminated at the same time. Over the past 2 years of operation, the wastewater treatment plant has been able to achieve a maximum processing capacity of more than 2,000 l/day, which equates to a nuclear medicine ward with approx. 20 beds. The highest level recorded during the test period (of 180 days after start-up) was a peak of nearly 2,800 l/day. PMID:22942776

Rodríguez, José Canga

2012-01-01

406

Graph algorithms experimentation facility  

E-print Network

We provide a facility to experiment with graph algorithms. The facility is implemented as a client to XAGE, a software environment developed under the direction of Dr. James Abello. XAGE allows a user to visually animate algorithmic actions...

Sonom, Donald George

1994-01-01

407

Facility safety study  

NASA Technical Reports Server (NTRS)

The safety of NASA's in house microelectronics facility is addressed. Industrial health standards, facility emission control requirements, operation and safety checklists, and the disposal of epitaxial vent gas are considered.

1979-01-01

408

THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY The Radiological Research Accelerator Facility  

E-print Network

THE RADIOLOGICAL RESEARCH ACCELERATOR FACILITY 1 The Radiological Research Accelerator Facility for Radiological Research (CRR). Using the mi- crobeam facility, 10% of the cells were irradiated through

409

Facile preparation of titania hollow spheres by combination of the mixed solvent method and the sol-gel process and post-calcination  

SciTech Connect

Polystyrene (core)-titania (shell) composite spheres consisting were readily prepared by a sol-gel process of titanium tetrabutoxide (TBOT) in a mixed solvent of ethanol/acetonitrile (3:1, v/v). Smooth and homogeneous titania coatings formed when the mixed solvent was dehydrated by anhydrous sodium sulfate. The thickness and surface roughness of titania coating increase with increase of the TBOT concentration. By adjusting the TBOT concentration in the range of 5.8-29.0 mM, the size of titania-coated PS spheres could be varied from 990 to 1125 nm. Calcination at elevated temperature gave dense, homogeneous, robust shells of anatase titania. The sizes of titania hollow spheres are 11.3-16.9% smaller than those of the titania-coated PS spheres as a result of calcination-induced shrinkage. The composite and hollow spheres were characterized by scanning electron microscopy, transmission electron microscopy and electron diffraction measurements. These core-shell organic-inorganic spheres and hollow ceramic spheres may have wide applications in catalysts, adsorbents, lightweight fillers, capsules, etc.

Du Xin [Functional Nanomaterials Laboratory and Key Laboratory of Photochemical Conversion and Optoelectronic Materials, Technical Institute of Physics and Chemistry, Chinese Academy of Sciences (CAS), Zhongguancun Beiyitiao 2, Haidianqu, Beijing 100049 (China); Graduate University of Chinese Academy of Sciences, Beijing 100864 (China); He Junhui, E-mail: jhhe@mail.ipc.ac.cn [Functional Nanomaterials Laboratory and Key Laboratory of Photochemical Conversion and Optoelectronic Materials, Technical Institute of Physics and Chemistry, Chinese Academy of Sciences (CAS), Zhongguancun Beiyitiao 2, Haidianqu, Beijing 100049 (China)

2009-06-03

410

Facile spray-coating process for the fabrication of tunable adhesive superhydrophobic surfaces with heterogeneous chemical compositions used for selective transportation of microdroplets with different volumes.  

PubMed

In this paper, tunable adhesive superhydrophobic ZnO surfaces have been fabricated successfully by spraying ZnO nanoparticle (NP) suspensions onto desired substrates. We regulate the spray-coating process by changing the mass percentage of hydrophobic ZnO NPs (which were achieved by modifying hydrophilic ZnO NPs with stearic acid) in the hydrophobic/hydrophilic ZnO NP mixtures to control heterogeneous chemical composition of the ZnO surfaces. Thus, the water adhesion on the same superhydrophobic ZnO surface could be effectively tuned by controlling the surface chemical composition without altering the surface morphology. Compared with the conventional tunable adhesive superhydrophobic surfaces, on which there were only three different water sliding angle values: lower than 10°, 90° (the water droplet is firmly pinned on the surface at any tilted angles), and the value between the two ones, the water adhesion on the superhydrophobic ZnO surfaces has been tuned effectively, on which the sliding angle is controlled from 2 ± 1° to 9 ± 1°, 21 ± 2°, 39 ± 3°, and 90°. Accordingly, the adhesive force can be adjusted from extremely low (?2.5 ?N) to very high (?111.6 ?N). On the basis of the different adhesive forces of the tunable adhesive superhydrophobic surfaces, the selective transportation of microdroplets with different volumes was achieved, which has never been reported before. In addition, we demonstrated a proof of selective transportation of microdroplets with different volumes for application in the droplet-based microreactors via our tunable adhesive superhydrophobic surfaces for the quantitative detection of AgNO3 and NaOH. The results reported herein realize the selective transportation of microdroplets with different volumes and we believe that this method would potentially be used in many important applications, such as selective water droplet transportation, biomolecular quantitative detection and droplet-based biodetection. PMID:24807195

Li, Jian; Jing, Zhijiao; Zha, Fei; Yang, Yaoxia; Wang, Qingtao; Lei, Ziqiang

2014-06-11

411

Knowledge based facilities management  

Microsoft Academic Search

Purpose – Facilities management has inherited the understanding of how organisations work as value creators from various management models such as Porter's, where value is created through “primary” and “support” activities. The gap between the aspiration of strategic relevance and reality has prompted the facilities management profession to begin to address the question of whether facilities management is a legitimate

Zehra Waheed; Scott Fernie

2009-01-01

412

Perimeter security for Minnesota correctional facilities  

SciTech Connect

For the past few years, the Minnesota Department of Corrections, assisted by Sandia National Laboratories, has developed a set of standards for perimeter security at medium, close, and maximum custody correctional facilities in the state. During this process, the threat to perimeter security was examined and concepts about correctional perimeter security were developed. This presentation and paper will review the outcomes of this effort, some of the lessons learned, and the concepts developed during this process and in the course of working with architects, engineers and construction firms as the state upgraded perimeter security at some facilities and planned new construction at other facilities.

Crist, D. [Minnesota Department of Corrections, St. Paul, MN (United States); Spencer, D.D. [Sandia National Labs., Albuquerque, NM (United States)

1996-12-31

413

Automated semiconductor diffusion and oxidation facility  

NASA Technical Reports Server (NTRS)

A semiconductor diffusion and oxidation facility (totally automated) was developed. Wafers arrived on an air track, automatically loaded into a furnace tube, processed, returned to track, and sent on to the next process. The entire process was controlled by a computer.

1982-01-01

414

Texas Facilities Commission's Facility Management Strategic Plan  

E-print Network

, Texas, November 17 - 19, 2009 Facility Strategic Plan ?High Performance Building Approach ? Envelope ? Load Reduction ? (Re)Design ? Advanced Tactics ?Building Automation ? Sub-metering ? Controls ?Commissioning ? Assessment ? Continuous ?Facility... Envelope ?Window Film ?Roof Load Reduction ?Motors/VFD ?Lights ?Equipment (Re)Design ?Loops ?Panels ?Distribution Advanced Tactics ?TES & Loop ?Load Shedding ESL-IC-09-11-12 Proceedings of the Ninth International Conference for Enhanced Building Operations...

Ramirez, J. A.

415

Data Analysis Facility (DAF)  

NASA Technical Reports Server (NTRS)

NASA-Dryden's Data Analysis Facility (DAF) provides a variety of support services to the entire Dryden community. It provides state-of-the-art hardware and software systems, available to any Dryden engineer for pre- and post-flight data processing and analysis, plus supporting all archival and general computer use. The Flight Data Access System (FDAS) is one of the advanced computer systems in the DAF, providing for fast engineering unit conversion and archival processing of flight data delivered from the Western Aeronautical Test Range. Engineering unit conversion and archival formatting of flight data is performed by the DRACO program on a Sun 690MP and an E-5000 computer. Time history files produced by DRACO are then moved to a permanent magneto-optical archive, where they are network-accessible 24 hours a day, 7 days a week. Pertinent information about the individual flights is maintained in a relational (Sybase) database. The DAF also houses all general computer services, including; the Compute Server 1 and 2 (CS1 and CS2), the server for the World Wide Web, overall computer operations support, courier service, a CD-ROM Writer system, a Technical Support Center, the NASA Dryden Phone System (NDPS), and Hardware Maintenance.

1991-01-01

416

Constructibility review process framework for transportation facilities  

E-print Network

Constructibility is the optimum use of construction knowledge and experience in planning, design, procurement, and field operations in order to achieve overall project objectives ("Constructibility: a primer" 1986). This Thesis presents a framework...

Liman, Majed

2012-06-07

417

Consolidated Incineration Facility model videotape  

SciTech Connect

A Consolidated Incineration Facility (CIF) is in final design for construction at the Savannah River Plant in Aiken, South Carolina. The CIF will detoxify and volume reduce combustible radioactive, hazardous and mixed waste. A study model was constructed during scope development for project authorization to assist with equipment layout and insure sufficient maintenance access. To facilitate the Department of Energy Validation process, a videotape of the model was developed. This ten minute videotape includes general information about the incineration process and a tour of the study model with a discussion of activities in each area. The videotape will be shown and the current status and schedule for the CIF presented.

Krolewski, J F; Augsburger, S T

1988-01-01

418

WIRELESS FOR A NUCLEAR FACILITY  

SciTech Connect

The introduction of wireless technology into a government site where nuclear material is processed and stored brings new meaning to the term ''harsh environment''. At SRNL, we are attempting to address not only the harsh RF and harsh physical environment common to industrial facilities, but also the ''harsh'' regulatory environment necessitated by the nature of the business at our site. We will discuss our concepts, processes, and expected outcomes in our attempts to surmount the roadblocks and reap the benefits of wireless in our ''factory''.

Shull, D; Joe Cordaro, J

2007-03-28

419

Space simulation facilities providing a stable thermal vacuum facility  

NASA Technical Reports Server (NTRS)

CBI has recently constructed the Intermediate Thermal Vacuum Facility. Built as a corporate facility, the installation will first be used on the Boost Surveillance and Tracking System (BSTS) program. It will also be used to develop and test other sensor systems. The horizontal chamber has a horseshoe shaped cross section and is supported on pneumatic isolators for vibration isolation. The chamber structure was designed to meet stability and stiffness requirements. The design process included measurement of the ambient ground vibrations, analysis of various foundation test article support configurations, design and analysis of the chamber shell and modal testing of the chamber shell. A detailed 3-D finite element analysis was made in the design stage to predict the lowest three natural frequencies and mode shapes and to identify local vibrating components. The design process is described and the results are compared of the finite element analysis to the results of the field modal testing and analysis for the 3 lowest natural frequencies and mode shapes. Concepts are also presented for stiffening large steel structures along with methods to improve test article stability in large space simulation facilities.

Tellalian, Martin L.

1990-01-01

420

Chemical facility vulnerability assessment project.  

PubMed

Sandia National Laboratories, under the direction of the Office of Science and Technology, National Institute of Justice, conducted the chemical facility vulnerability assessment (CFVA) project. The primary objective of this project was to develop, test and validate a vulnerability assessment methodology (VAM) for determining the security of chemical facilities against terrorist or criminal attacks (VAM-CF). The project also included a report to the Department of Justice for Congress that in addition to describing the VAM-CF also addressed general observations related to security practices, threats and risks at chemical facilities and chemical transport. In the development of the VAM-CF Sandia leveraged the experience gained from the use and development of VAs in other areas and the input from the chemical industry and Federal agencies. The VAM-CF is a systematic, risk-based approach where risk is a function of the severity of consequences of an undesired event, the attack potential, and the likelihood of adversary success in causing the undesired event. For the purpose of the VAM-CF analyses Risk is a function of S, L(A), and L(AS), where S is the severity of consequence of an event, L(A) is the attack potential and L(AS) likelihood of adversary success in causing a catastrophic event. The VAM-CF consists of 13 basic steps. It involves an initial screening step, which helps to identify and prioritize facilities for further analysis. This step is similar to the prioritization approach developed by the American Chemistry Council (ACC). Other steps help to determine the components of the risk equation and ultimately the risk. The VAM-CF process involves identifying the hazardous chemicals and processes at a chemical facility. It helps chemical facilities to focus their attention on the most critical areas. The VAM-CF is not a quantitative analysis but, rather, compares relative security risks. If the risks are deemed too high, recommendations are developed for measures to reduce the risk. This paper will briefly discuss the CFVA project and VAM-CF process. PMID:14602410

Jaeger, Calvin D

2003-11-14

421

Safety of magnetic fusion facilities: Guidance  

SciTech Connect

This document provides guidance for the implementation of the requirements identified in DOE-STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements. This guidance is intended for the managers, designers, operators, and other personnel with safety responsibilities for facilities designated as magnetic fusion facilities. While the requirements in DOE-STD-6002-96 are generally applicable to a wide range of fusion facilities, this Standard, DOE-STD-6003-96, is concerned mainly with the implementation of those requirements in large facilities such as the International Thermonuclear Experimental Reactor (ITER). Using a risk-based prioritization, the concepts presented here may also be applied to other magnetic fusion facilities. This Standard is oriented toward regulation in the Department of Energy (DOE) environment as opposed to regulation by other regulatory agencies. As the need for guidance involving other types of fusion facilities or other regulatory environments emerges, additional guidance volumes should be prepared. The concepts, processes, and recommendations set forth here are for guidance only. They will contribute to safety at magnetic fusion facilities.

NONE

1996-05-01

422

PSL Icing Facility Upgrade Overview  

NASA Technical Reports Server (NTRS)

The NASA Glenn Research Center Propulsion Systems Lab (PSL) was recently upgraded to perform engine inlet ice crystal testing in an altitude environment. The system installed 10 spray bars in the inlet plenum for ice crystal generation using 222 spray nozzles. As an altitude test chamber, the PSL is capable of simulating icing events at altitude in a groundtest facility. The system was designed to operate at altitudes from 4,000 to 40,000 ft at Mach numbers up to 0.8M and inlet total temperatures from -60 to +15 degF. This paper and presentation will be part of a series of presentations on PSL Icing and will cover the development of the icing capability through design, developmental testing, installation, initial calibration, and validation engine testing. Information will be presented on the design criteria and process, spray bar developmental testing at Cox and Co., system capabilities, and initial calibration and engine validation test. The PSL icing system was designed to provide NASA and the icing community with a facility that could be used for research studies of engine icing by duplicating in-flight events in a controlled ground-test facility. With the system and the altitude chamber we can produce flight conditions and cloud environments to simulate those encountered in flight. The icing system can be controlled to set various cloud uniformities, droplet median volumetric diameter (MVD), and icing water content (IWC) through a wide variety of conditions. The PSL chamber can set altitudes, Mach numbers, and temperatures of interest to the icing community and also has the instrumentation capability of measuring engine performance during icing testing. PSL last year completed the calibration and initial engine validation of the facility utilizing a Honeywell ALF502-R5 engine and has duplicated in-flight roll back conditions experienced during flight testing. This paper will summarize the modifications and buildup of the facility to accomplish these tests.

Griffin, Thomas A.; Dicki, Dennis J.; Lizanich, Paul J.

2014-01-01

423

ORNL irradiation creep facility  

SciTech Connect

A machine was developed at ORNL to measure the rates of elongation observed under irradiation in stressed materials. The source of radiation is a beam of 60 MeV alpha particles from the Oak Ridge Isochronous Cyclotron (ORIC). This choice allows experiments to be performed which simulate the effects of fast neutrons. A brief review of irradiation creep and experimental constraints associated with each measurement technique is given. Factors are presented which lead to the experimental choices made for the Irradiation Creep Facility (ICF). The ICF consists of a helium-filled chamber which houses a high-precision mechanical testing device. The specimen to be tested must be thermally stabilized with respect to the temperature fluctuations imposed by the particle beam which passes through the specimen. Electrical resistance of the specimen is the temperature control parameter chosen. Very high precision in length measurement and temperature control are required to detect the small elongation rates relevant to irradiation creep in the test periods available (approx. 1 day). The apparatus components and features required for the above are presented in some detail, along with the experimental procedures. The damage processes associated with light ions are discussed and displacement rates are calculated. Recent irradiation creep results are given, demonstrating the suitability of the apparatus for high resolution experiments. Also discussed is the suitability of the ICF for making high precision thermal creep measurements.

Reiley, T.C.; Auble, R.L.; Beckers, R.M.; Bloom, E.E.; Duncan, M.G.; Saltmarsh, M.J.; Shannon, R.H.

1980-09-01

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