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Final report on initial samples supplied by LLNL for task 3.3 binder burnout and sintering schedule optimisation

Description: Sixteen of the twenty-one samples have been investigated using the scanning laser dilatometer. This includes all three types of samples with different preparation routes and organic content. Cracks were observed in all samples, even those only heated to 300 C. It was concluded that the cracking was occurring in the early part of the heat treatment before the samples reached 300 C. Increase in the rate of dilation of the samples occurred above 170 C which coincided with the decomposition of the binder/wax additives as determined by differential thermal analysis. A comparison was made with SYNROC C material (Powder Run 143), samples of which had been CIPed and green machined to a similar diameter and thickness as the 089 mm SRTC pucks. These samples contained neither binder nor other organic processing aids and had been kept in the same desiccator as the SRTC samples. The CIPed Synroc C samples sintered to high density with zero cracks. As the cracks made up only a small contribution to the change in diameter of the sample compared to the sintering shrinkage, useful information could still be gained from the runs. The sintering curves showed that there was much greater shrinkage of the Type III samples containing only the 5% PEG binder compared to the Type I which contained polyolefin wax as processing aid. Slight changes in gradient of the sintering curve were observed, however, due to the masking effect of the cracking, full analysis of the sintering kinetics cannot be conducted. Even heating the samples to 300 C at 1.0 or 0.5 C/min could not prevent crack formation. This indicated that heating rate was not the critical parameter causing cracking of the samples. Sectioning of green bodies revealed the inhomogeneous nature of the binder/lubricant distribution in the samples. Increased homogeneity would reduce the ...
Date: January 4, 1999
Creator: Walls, P
Partner: UNT Libraries Government Documents Department

Final Report on Initial Samples Supplied by LLNL for Task 3.3 Binder Burnout and Sintering Schedule Optimisation

Description: Sixteen of the twenty-one samples have been investigated using the scanning laser dilatometer. This includes all three types of samples with different preparation routes and organic content. Cracks were observed in all samples, even those only heated to 300 C. It was concluded that the cracking was occurring in the early part of the heat treatment before the samples reached 300 C. Increase in the rate of dilation of the samples occurred above 170 C which coincided with the decomposition of the binder/wax additives as determined by differential thermal analysis. A comparison was made with SYNROC C material (Powder Run 143), samples of which had been CIPed and green machined to a similar diameter and thickness as the 089mm SRTC pucks. These samples contained neither binder nor other organic processing aids and had been kept in the same desiccator as the SRTC samples. The CIPed Synroc C samples sintered to high density with zero cracks. As the cracks made up only a small contribution to the change in diameter of the sample compared to the sintering shrinkage, useful information could still be gained from the runs. The sintering curves showed that there was much greater shrinkage of the Type III samples containing only the 5% PEG binder compared to the Type I which contained polyolefin wax as processing aid. Slight changes in gradient of the sintering curve were observed, however, due to the masking effect of the cracking, full analysis of the sintering kinetics cannot be conducted. Even heating the samples to 300 C at 1.0 or 0.5 C/min could not prevent crack formation. This indicated that heating rate was not the critical parameter causing cracking of the samples. Sectioning of green bodies revealed the inhomogeneous nature of the binder/lubricant distribution in the samples. Increased homogeneity would reduce the amount ...
Date: January 4, 1999
Creator: Walls, P
Partner: UNT Libraries Government Documents Department

Annual Meeting of the Texas Society, Sons of the American Revolution, 1999

Description: Program for the 104th annual meeting of the Texas Society Sons of the American Revolution, held from March 12 through the 14, 1999 at the Sheraton North Houston Hotel, in Houston, Texas, including a list of sessions for the meeting and related information about the organization and conference. The meeting was called to order by President Robert W. Coker, in the Ampitheater of the Sheraton North Houston Hotel.
Date: March 1999
Creator: Sons of the American Revolution. Texas Society.
Partner: UNT Libraries Special Collections

Treatment Deployment Evaluation Tool

Description: The U.S. Department of Energy (DOE) is responsible for the final disposition of legacy spent nuclear fuel (SNF). As a response, DOE's National Spent Nuclear Fuel Program (NSNFP) has been given the responsibility for the disposition of DOE -owned SNF. Many treatment technologies have been identified to treat some forms of SNF so that the resulting treated product is acceptable by the disposition site. One of these promising treatment processes is the electrometallurgical treatment (EMT) currently in development; a second is an Acid Wash Decladding process. The NSNFP has been tasked with identifying possible strategies for the deployment of these treatment processes in the event that the treatment path is deemed necessary. To support the siting studies of these strategies, economic evaluations are being performed to identify the least-cost deployment path. This model (tool) was developed to consider the full scope of costs, technical feasibility, process material disposition, and schedule attributes over the life of each deployment alternative. Using standard personal computer (PC) software, the model was developed as a comprehensive technology economic assessment tool using a Life-Cycle Cost (LCC) analysis methodology. Model development was planned as a systematic, iterative process of identifying and bounding the required activities to dispose of SNF. To support the evaluation process, activities are decomposed into lower level, easier to estimate activities. Sensitivity studies can then be performed on these activities, defining cost issues and testing results against the originally stated problem.
Date: August 1, 1999
Creator: Rynearson, Michael Ardel & Plum, Martin Michael
Partner: UNT Libraries Government Documents Department

TITLE III EVALUATION REPORT FOR THE SURFACE AND SUBSURFACE POWER SYSTEM

Description: The objective of this evaluation is to provide recommendations to ensure consistency between the technical baseline requirements, baseline design, and the alternate constructed power system. Recommendations for resolving discrepancies between the alternate constructed power system, the technical baseline requirements, and the baseline design are included in this report. Cost and schedule estimates are provided for all recommended modifications. This report does not address items which do not meet current safety or code requirements. These items are identified to the CMO and immediate action is taken to correct the situation. The report does identify safety and code items for which the A/E is recommending improvements. The recommended improvements will exceed the minimum requirements of applicable code and safety guidelines. These recommendations are intended to improve and enhance the operation and maintenance of the facility. This Title III Evaluation Report (TER) does not include evaluation of surface electrical construction support facilities used to provide temporary construction power where the intent to remove such facilities when construction is completed such as tent storage buildings, shop buildings, fuel storage area etc. Furthermore, this TER does not include the extension of the existing overhead power lines to the booster pump station that was designed, installed, and is maintained by Nevada Test Site (NTS).
Date: August 16, 1999
Creator: REED, W.J.
Partner: UNT Libraries Government Documents Department

RHIC IR Quadrupoles and Field Quality State of the Art in Super Conducting Accelerator Magnets

Description: The interaction region (IR) quadrupoles [1] for the Relativistic Heavy Ion Collider (RHIC)[2]are the best field quality superconducting magnets ever built for any major accelerator. This field quality is primarily achieved with the help of eight tuning shims [3] that remove the residual errors from a magnet after it is built and tested. These shims overcome the limitations from the typical tolerances in parts and manufacturing. This paper describes the tuning shims and discusses the evolution of a flexible approach that allowed changes in the design parameters and facilitated using parts with significant dimensional variations while controlling cost and maintaining schedule and field quality. The RHIC magnet program also discovered that quench and thermal cycles cause small changes [4]in magnet geometry. The ultimate field quality performance is now understood to be determined by these changes rather than the manufacturing tolerances or the measurement errors.
Date: March 8, 1999
Creator: Gupta, R.; Anerella, M.; Cozzolino, J.; Ghosh, A.; Jain, A.; Kahn, S. et al.
Partner: UNT Libraries Government Documents Department

SECONDARY LOW-LEVEL WASTE GENERATION RATE ANALYSIS

Description: The objective of this design analysis is -to update the assessment of estimated annual secondary low-level waste (LLW) generation rates resulting from the repackaging of spent nuclear fuel (SNF) and high-level waste (HLW) for disposal at the Monitored Geologic Repository (MGR). This analysis supports the preparation of documentation necessary for license application (LA) for the MGR. For the purposes of this analysis, secondary LLW is defined, in brief terms, as LLW generated as a direct result of processing SNF/HLW through the receiving and repackaging operations. The current Waste Handling Building (WHB) design is based on the predominant movement of fuel assemblies through the wet handling lines within the WHB. Dry handling lines are also included in the current WHB design to accommodate canistered waste (i.e., SNF and/or HLW packages). Major input changes to this analysis in comparison to previous analyses include: (1) changes in the SNF/HLW arrival schedules; (2) changes to the WHB and the Waste Treatment Building (WTB) dimensions; and (3) changes in operational staff sizes within the WHB and WTB. The rates generated in this analysis can be utilized to define necessary waste processes, waste flow rates, and equipment sizes for the processing of secondary LLW for proper disposal. This analysis is based on the present reference design, i.e., Viability Assessment (VA) design, and present projections on spent fuel delivery and processing. LLW generation rates, for both liquids and solids, are a direct function of square footages in radiological areas, and a direct function of spent fuel throughput. Future changes in the approved reference design or spent fuel throughput will directly impact the LLW generation rates defined in this analysis. Small amounts of wastes other than LLW may be generated on a non-routine basis. These wastes may include transuranic (TRU), hazardous, and mixed wastes. Although the objective of ...
Date: May 10, 1999
Creator: LaRue, D.
Partner: UNT Libraries Government Documents Department

Acceleration schedules for a recirculating heavy-ion accelerator

Description: The recent development of miniature inductive adders has made it feasible to design programmable, high-repetition-rate pulsers with a substantially higher voltage than is possible using a conventional field-effect transistor architecture. Prototype pulsers using the new technology are being developed as part of a series of experiments at LLNL to test the concept of a recirculating induction accelerator. Preliminary numerical work is reported here to determine what effects the higher-voltage pulsers would have on the beam quality of the LLNL small recirculator.
Date: June 1, 1999
Creator: Grote, D. P. & Sharp, W.
Partner: UNT Libraries Government Documents Department

OPTICAL FIBER SENSOR TECHNOLOGIES FOR EFFICIENT AND ECONOMICAL OIL RECOVERY

Description: Efficient and complete recovery of petroleum reserves from existing oil wells has proven difficult due to a lack of robust instrumentation that can monitor processes in the downhole environment. Commercially available sensors for measurement of pressure, temperature, and fluid flow exhibit shortened lifetimes in the harsh downhole conditions, which are characterized by high pressures (up to 20 kpsi), temperatures up to 250 C, and exposure to chemically reactive fluids. Development of robust sensors that deliver continuous, real-time data on reservoir performance and petroleum flow pathways will facilitate application of advanced recovery technologies, including horizontal and multi-lateral wells. The main objective of the research program is to develop cost-effective, reliable fiber sensor instrumentation for real-time monitoring and /or control of various key parameters crucial to efficient and economical oil production. This report presents the detailed research work and technical progress from October 1, 1998 to September 30, 1999. The research performed over the first year of the program has followed the schedule as proposed, and solid research progress has been made in specification of the technical requirements, design and fabrication of the SCIIB sensor probes, development of the sensor systems, development of DSP-based signal processing techniques, and construction of the test systems. These technical achievements will significantly help to advance continued research on sensor tests and evaluation during the second year of the program.
Date: October 29, 1999
Creator: Wang, A.; Xiao, H. & May, R.
Partner: UNT Libraries Government Documents Department

Thermoacoustic Liquefaction of Coal Mine Methane to Produce Lng for Heavy Vehicle Applicaitons

Description: This report describes the activity undertaken by the project members under MORGANTOWN ENERGY TECHNOLOGY CENTER (METC) contract No. DE-AC21-95MC32185 to develop a project that will provide a commercial use for Coal Mine Methane (CMM). In particular, the report describes a project to convert CMM into Liquefied Natural Gas (LNG) and to market that LNG to the transportation sector in and around the I-79 corridor near Morgantown, West Virginia. The report discusses the sources of CMM and provides estimates of the extent of the resource specifically dedicated to the project. It discusses the novel refrigeration technology that will be employed to convert the CMM to LNG and the gas conditioning technology that will be used to bring the raw CMM up to cryogenic processing specifications. Summary capital and operating cost estimates are furnished for the project and specific monetary and schedule requirements are identified so the project can be examined in its entirety. The report discusses the immediate market potential for the successful commercial sale of LNG into the nearby market and provides estimates of future market penetration into local, regional and wider markets. Lastly, the report comments on the environmental effects of the project and extrapolates these benefits to future markets. One of the driving forces for the project is the reduction of environmentally harmful greenhouse gases currently escaping unchecked into the atmosphere. This final section analyzes the TASHER technology's potential net environmental benefits both in terms of greenhouse gases and criteria pollutants.
Date: October 29, 1999
Creator: Aminian, Kashi; English, Lloyd; Patchen, Douglas; Siriwardane, Hema; Estes, Charles D. & Zahradnik, Raymond L.
Partner: UNT Libraries Government Documents Department

Secondary Low-Level Waste Treatment Strategy Analysis

Description: The objective of this analysis is to identify and review potential options for processing and disposing of the secondary low-level waste (LLW) that will be generated through operation of the Monitored Geologic Repository (MGR). An estimate of annual secondary LLW is generated utilizing the mechanism established in ''Secondary Waste Treatment Analysis'' (Reference 8.1) and ''Secondary Low-Level Waste Generation Rate Analysis'' (Reference 8.5). The secondary LLW quantities are based on the spent fuel and high-level waste (HLW) arrival schedule as defined in the ''Controlled Design Assumptions Document'' (CDA) (Reference 8.6). This analysis presents estimates of the quantities of LLW in its various forms. A review of applicable laws, codes, and standards is discussed, and a synopsis of those applicable laws, codes, and standards and their impacts on potential processing and disposal options is presented. The analysis identifies viable processing/disposal options in light of the existing laws, codes, and standards, and then evaluates these options in regard to: (1) Process and equipment requirements; (2) LLW disposal volumes; and (3) Facility requirements.
Date: May 25, 1999
Creator: LaRue, D.M.
Partner: UNT Libraries Government Documents Department

Tank Waste Remediation System (TWRS) Retrieval Authorization Basis Amendment Task Plan

Description: This task plan is a documented agreement between Nuclear Safety and Licensing and Retrieval Engineering. The purpose of this task plan is to identify the scope of work, tasks and deliverables, responsibilities, manpower, and schedules associated with an authorization basis amendment as a result of the Waste Feed Delivery Program, Project W-211, Project W-521, and Project W-522.
Date: August 31, 1999
Creator: HARRIS, J.P.
Partner: UNT Libraries Government Documents Department

Portable Exhauster Position Paper

Description: This document identifies the tasks that are involved in preparing the ''standby'' portable exhauster (POR05 skid C) to support Interim Stabilization's schedule for saltwell pumping.
Date: September 24, 1999
Creator: KRISKOVICH, J.R.
Partner: UNT Libraries Government Documents Department

Project W-521 waste feed delivery systems environmental permits and approvals plan

Description: This document has been prepared to define the specific environmental requirements applicable to Project W-521. The document describes the permits and approvals necessary for the project to design, construct, and install planned upgrades, and provides a schedule of activities and provides cost estimates to complete the required permitting and approval activities.
Date: September 21, 1999
Creator: TOLLEFSON, K.S.
Partner: UNT Libraries Government Documents Department

Radioactive air emissions notice of construction for installation and operation of a waste retrieval system and tanks 241-AP-102 and 241-AP-104 project

Description: This document serves as a notice of construction (NOC) pursuant to the requirements of Washington Administrative Code (WAC) 246 247-060, and as a request for approval to modify pursuant to 40 Code of Federal Regulations (CFR) 61 07 for the installation and operation of one waste retrieval system in the 24 1 AP-102 Tank and one waste retrieval system in the 241 AP 104 Tank Pursuant to 40 CFR 61 09 (a)( 1) this application is also intended to provide anticipated initial start up notification Its is requested that EPA approval of this application will also constitute EPA acceptance of the initial start up notification Project W 211 Initial Tank Retrieval Systems (ITRS) is scoped to install a waste retrieval system in the following double-shell tanks 241-AP 102-AP 104 AN 102, AN 103, AN-104, AN 105, AY 102 AZ 102 and SY-102 between now and the year 2011. Because of the extended installation schedules and unknowns about specific activities/designs at each tank, it was decided to submit NOCs as that information became available This NOC covers the installation and operation of a waste retrieval system in tanks 241 AP-102 and 241 AP 104 Generally this includes removal of existing equipment installation of new equipment and construction of new ancillary equipment and buildings Tanks 241 AP 102 and 241 AP 104 will provide waste feed for immobilization into a low activity waste (LAW) product (i.e. glass logs) The total effective dose equivalent (TEDE) to the offsite maximally exposed individual (MEI) from the construction activities is 0 045 millirem per year The unabated TEDE to the offsite ME1 from operation of the mixer pumps is 0 042 millirem per year.
Date: November 15, 1999
Creator: DEXTER, M.L.
Partner: UNT Libraries Government Documents Department

Advanced Reactors Transition Program Resource Loaded Schedule

Description: The Advanced Reactors Transition (ART) Resource Loaded Schedule (RLS) provides a cost and schedule baseline for managing the project elements within the ART Program. The Fast Flux Test Facility (FFTF) activities are delineated through the end of FY 2000, assuming continued standby. The Nuclear Energy (NE) Legacies and Plutonium Recycle Test Reactor (PRTR) activities are delineated through the end of the deactivation process. This document reflects the 1 Oct 1999 baseline.
Date: November 8, 1999
Creator: Bowen, W. W.
Partner: UNT Libraries Government Documents Department

Hanford science and technology needs statements, 2000

Description: In the aftermath of the Cold War, the United States has begun addressing the environmental consequences of five decades of nuclear weapons production. In November 1989, DOE established the Office of Environmental Restoration and Waste Management (EM) as the central authority for cleaning up the DOE weapons complex legacy of pollution, for preventing further environmental contamination, and for instituting responsible environmental management. While performing its tasks, EM found that many aspects of its large and complex mission could not be achieved using existing science and technology or without incurring unreasonable costs, risks, or schedule impacts. Consequently, a process was developed to solicit needs from around the DOE complex and focus the science and technology resources of EM-50, the National Laboratories, private industry, and colleges and universities on those needs. This document describes those needs that the Hanford Site has identified as requiring additional science or technology to complete.
Date: July 16, 1999
Creator: BERLIN, G.T.
Partner: UNT Libraries Government Documents Department

Hanford tank waste operation simulator operational waste volume projection verification and validation procedure

Description: The Hanford Tank Waste Operation Simulator is tested to determine if it can replace the FORTRAN-based Operational Waste Volume Projection computer simulation that has traditionally served to project double-shell tank utilization. Three Test Cases are used to compare the results of the two simulators; one incorporates the cleanup schedule of the Tri Party Agreement.
Date: October 28, 1999
Creator: HARMSEN, R.W.
Partner: UNT Libraries Government Documents Department

License Application Design Selection Enhanced Design Alternative V: Very High Thermal Loading

Description: The major goals of Enhanced Design Alternative (EDA) V are to keep the temperature of the cladding on the spent nuclear fuel (SNF) within the waste package below 350 C (Section 4.2.3), the temperature of the emplacement drift walls below 225 C (Section 4.2.3), and to keep the emplacement drifts dry for several thousand years. In addition, the design would produce relatively consistent heat output from waste package to waste package and ensure that waste package thermal outputs are spread more evenly across the repository. The design would also provide defense in depth (Section 5.3). The goals of this design would be achieved by the combination of design features described below. This EDA would have an areal mass loading (AML) of 150 metric tons of uranium equivalent (MTU) per acre (Section 4.1.16) as opposed to the 85 MTU/acre in the Viability Assessment (VA) reference design. To achieve this loading and the elements necessary to the EDA's overall goals, the design would require approximately 420 acres of emplacement area, within the lower repository block (Appendix A, Section A.2). A conceptual layout was developed for EDA V (Section 5.4.3). The layout, as shown in Figure 2, contains openings that are sized and arranged in a similar configuration as the VA reference design. A total of 54 emplacement drifts will be required for emplacement of the 70,000 MTU of spent nuclear fuel and high level waste packages. A total of four ventilation shafts, one intake and three exhausts are anticipated for the layout in order to provide sufficient air quantities to the emplacement drifts. Two exhaust mains will be located below the level of the emplacement drifts to provide exhaust from the emplacement drifts. In addition, the evaluation has confirmed that the decision to close the repository is possible 50 years after start ...
Date: June 22, 1999
Creator: Linden, C. L.
Partner: UNT Libraries Government Documents Department

OIT Times Newsletter: Volume 3, Number 1, Winter 2000

Description: The Winter 2000 edition of the OIT Times newsletter, a quarterly publication produced by the Office of Industrial Technologies, highlights the 1999 start-up projects, announces the OIT solicitation schedule for FY2000, and features the success of the Ohio diecasting showcase. One of the quarterly highlights was Secretary Richardson's presentation of a Certificate of Partnership to Malden Mills CEO Aaron Feuerstein at the dedication of the plant's new, advanced cogeneration system.
Date: December 16, 1999
Creator: Sousa, L.
Partner: UNT Libraries Government Documents Department

Aluminum-fly ash metal matrix composites for automotive parts. [Reports for October 1 to December 1998, and January 31 to March 31, 1999]

Description: Some highlights are: (1) Material development, process development, and part validation are occurring simultaneously on a fast track schedule. (2) Prior project activity has resulted in a program emphasis on three components--manifolds, mounting brackets, and motor mounts; and three casting techniques--squeeze casting, pressure die casting, and sand casting. (3) With the project focus, it appears possible to offer manifolds and mounting brackets for automotive qualification testing on a schedule in line with the PNGV Year 2004 goal. (4) Through an iterative process of fly ash treatment, MMC ingot preparation, foundry process refinement, and parts production, both foundries (Eck Industries and Thompson Aluminum Casting Company) are addressing the pre-competitive issues of: (a) Optimum castability with fly ash shapes and sizes; (b) Best mechanical properties derived from fly ash shapes and sizes; (c) Effective fly ash classification processes; (d) Mechanical properties resulting from various casting processes and fly ash formulations. Eck and TAC continued experiments with batch ingot provided by both Eck and the University of Wisconsin at Milwaukee. Castings were run that contained varying amounts of fly ash and different size fractions. Components were cast using cenosphere material to ascertain the effects of squeeze casting and to determine whether the pressure would break the cenospheres. Test parts are currently being machined into substandard test bars for mechanical testing. Also, the affect of heat treatments on ashalloy are being studied through comparison to two lots, one heat treated and one in the ''as cast'' condition.
Date: April 21, 1999
Creator: Weiss, David; Purgert, Robert; Rhudy, Richard & Rohatgi, P.
Partner: UNT Libraries Government Documents Department

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center

Description: A potential option in the program for long-term management of high-level wastes at the Idaho Nuclear Technology and Engineering Center (INTEC), at the Idaho National Engineering and Environmental Laboratory, calls for retrieving calcine waste and converting it to a more stable and less dispersible form. An inventory of calcine produced during the period December 1963 to May 1999 has been prepared based on calciner run, solids storage facilities operating, and miscellaneous operational information, which gives the range of chemical compositions of calcine waste stored at INTEC. Information researched includes calciner startup data, waste solution analyses and volumes calcined, calciner operating schedules, solids storage bin capacities, calcine storage bin distributor systems, and solids storage bin design and temperature monitoring records. Unique information on calcine solids storage facilities design of potential interest to remote retrieval operators is given.
Date: June 1, 1999
Creator: Staiger, M. D.
Partner: UNT Libraries Government Documents Department

Hanford Site waste treatment/storage/disposal integration

Description: In 1998 Waste Management Federal Services of Hanford, Inc. began the integration of all low-level waste, mixed waste, and TRU waste-generating activities across the Hanford site. With seven contractors, dozens of generating units, and hundreds of waste streams, integration was necessary to provide acute waste forecasting and planning for future treatment activities. This integration effort provides disposition maps that account for waste from generation, through processing, treatment and final waste disposal. The integration effort covers generating facilities from the present through the life-cycle, including transition and deactivation. The effort is patterned after the very successful DOE Complex EM Integration effort. Although still in the preliminary stages, the comprehensive onsite integration effort has already reaped benefits. These include identifying significant waste streams that had not been forecast, identifying opportunities for consolidating activities and services to accelerate schedule or save money; and identifying waste streams which currently have no path forward in the planning baseline. Consolidation/integration of planned activities may also provide opportunities for pollution prevention and/or avoidance of secondary waste generation. A workshop was held to review the waste disposition maps, and to identify opportunities with potential cost or schedule savings. Another workshop may be held to follow up on some of the long-term integration opportunities. A change to the Hanford waste forecast data call would help to align the Solid Waste Forecast with the new disposition maps.
Date: February 24, 1999
Creator: MCDONALD, K.M.
Partner: UNT Libraries Government Documents Department

Engineering task plan for development, fabrication, and deployment of nested, fixed depth fluidic sampling and at-tank analysis systems

Description: An engineering task plan was developed that presents the resources, responsibilities, and schedules for the development, test, and deployment of the nested, fixed-depth fluidic sampling and at-tank analysis system. The sampling system, deployed in the privatization contract double-shell tank feed tank, will provide waste samples for assuring the readiness of the tank for shipment to the privatization contractor for vitrification. The at-tank analysis system will provide ''real-time'' assessments of the sampled wastes' chemical and physical properties. These systems support the Hanford Phase 1B Privatization Contract.
Date: May 18, 1999
Creator: REICH, F.R.
Partner: UNT Libraries Government Documents Department